ML20303A192
| ML20303A192 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 09/29/2020 |
| From: | Southern Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20303A202 | List: |
| References | |
| NL-20-1084 | |
| Download: ML20303A192 (417) | |
Text
{{#Wiki_filter:LET- PLATE COMP TER DI MEN- COLOR ND . LABEL CONTENTS SIZE SIONS CODING NOTES CLxVl 001 RX PRESS 2c32--* -~- J/16~-J/4'x
- 1*
EY}2\
\.. 2B21-D004B 11~* 2 12~VD~ ~AB 2B 002 RX llTR LVL- - - -
2CJ2 -*
\..2B21-D0048 J/16~-J/4'x 1/8' 2 1* ~
12~V~ c;_AB_ 2B 003 RFP FLO\/ A 3/16' 1-3/4'x B-CJll-11 2N21-R636A I' INST BUS 2A 1/8' 004 RFP FLO\/ B 3/16' 1-3/4'x B-DN-11 2N21-R636B 1* INST BUS 2A 1/8' 005 RX PRESS/RX VTR L VL 3/16' 4' x I' B-DN-11 2C32-R608 VITAL AC 1/8' 006 A 3/16' 1-3/4'x B-ON-V RESET PUSHBUTTON VITAL AC 1/8' 718' 007 B 3/16' l-J/4'x B-ON-11 RESET PUSHBUTTON 125VDC CAB 2A 1/8' 718' 008 c 3/16' 1-3/4'x B-DN-V RESET PUSHBUTTON 125VDC CAB 28 1/8' 7/8' 009 ROii A 3116' l-J/4'x B-ON-V 2C32-R604A I' VITAL AC 118' 010 FLO\/ B J/16' l-3/4'x B-ON-11 2C32-R6048 I' 125VDC CAB 2A 1/8' 011 PRESS CONTROL 3/16' 3-l/4'x B-ON-V VLV F127 1-1 /4' 2Cll-R607 INST BUS 2A 1/8' ( ACAD r A2160301 ) I 2 /f./gy LCF ""L'> Jj. RtVIS£0 PER AllN 94-0207 {"' OCRl ASJ: ~ 1 J-21-93 ows HEW REVISED PER ABN 93-0041 WfB OEK >< >< >< 0 l-5-9( BAS APPROVED ISSUED PER ABC OEK RBV WLO GDI! ABN 89-840 ANO WCN 88-246-1 Rev. Date By Checked Description Appr. 1 Appr. 2 Appr. l Appr. 4 Appr. 5 Southern Company Services, Inc . b Georgia Power Company EDWIN I. HATCH NUCLEAR POWER PLANT - UNIT No. 2 NAMEPLATE ENGRAVING UST FOR PROJECT 1.0. I DRAWING NUMBER I SHEET I REV. PANEL 2H11-P60l Drown: 8 Snow ITyped: JOM IC~ecked: 10-502 I A-21603 I 01 1 2
LET- PLATE COMP TER DI MEN- COLOR ND. LABEL CONTENTS SIZE SIDNS CODI NG NOTES
<Lx\J) 012 TANK LEVEL 3/16' 1-3/4' x B-DN-W 2C41-R601 1.
2R25-S011 118' 013 DI SCH PRESS 3/16' 1-3/4' x B-DN-W 2C41-R600 1. 2R25-S011 118' 014 FW clp 3/16' 1-3/4'x B-DN-W 2N21-R610 1. INST BUS 2A 118' 015 A 3/16' 1-3/4'x B-DN-W 2C32-R603A 1. VITAL AC 118' 016 B 3/16' 1-3/4' x B-DN-W 2C32-R603B 1. 125VDC CAB 2A 118' 017 c 3/16' 1-3/4' x 1. B-DN-W 2C32-R603C 125VDC CAB 2B 118' 018 D 3/16' 1-3/4'x B-DN-W 2C32-R603D 1. INST BUS 2B 118' 019 RX PRESS/TURB STM FLOW 3/16' 4' x 1* B-DN-DRANGE 2C32-R609 2B21-D003A 1/8'
~ VITAL AC
~~~~ 3/16' 2-5/8'x B-DN-W 021 FW A TD RX 2N21-F006A 718' 2R24-S013 118' 022 FW B TD RX 3/16' 2-5/8'x B-DN-W 2N21-F006B 718' 2R24-S013 118' 023 DR WTR FLOW 3/16' 1-3/4' x B-DN-W 2C11-R604 1.
INST BUS 2A 118' 024 CLG WTR FLOW 3/16' 1-3/4'x B-DN-W 2Cll-R605 1. INST BUS 2A 118' 4 7-23-97 D.K. REVISED PER ABN 94-0008-017. HEW ccs Rev. Dote t:Sy Description Checked Appr. l Southem Company Services, Inc. for Georgia Power Company ( ACADR13J A2160302) "This document contains proprietary. confidential, and/or trade secret Information of the subsidiaries of The Southern Company or of third parties. It is intended for use only by employees of, or authorized contractors of, the subsidiaries of The Southern Company. Unauthorized possession, use, distribution, copyino, dissemination, or disclosure of anv portion hereof is prohibited.* EDWIN I. HATCH NUCLEAR PLANT UNIT No. 2 NAMEPLATE ENGRAVING LIST FOR PROJECT l.D. DRAWING NUMBER SHEET' REV. PANEL 2H 11 -P603 Drawn: D.K . I Designed: JDM I Dote: 10-502 A-21603 02 4
LET- PLATE CDHP TER DIHEN- COL DR NO. LABEL CONTENTS SIZE SIClNS CODING NOTES (lx\I) 025 CHG \ITR PRESS 3/16. l-3/4*x B-DN-\1 2C1 l-R60l 1* INST BUS 2A 11a* 026 CLG \HR dp 3/16. 1-3/4*x B-DN-\1 2Clt-R603 t* 2R2S-St02 1/8* 027 DR \ITR dp 3/16. l-3/4*x B-ON-V 2Cl 1-R602 1* 2R25-S102 11e* 028 STH fLDV/fV fLO\I 3/t6* 4* x 1* B-DN-\1 2C32-R607 VITAL AC 029 030 B-DN-GRAY 031 032 2-s1e*x 110* 033 034 035 036 s* x 1* \1-DN-R 037 IRH BYPASS 3/t6* B-DN-V REVISED PER ABN 94-0207 NO OCR APPROVED ISSUED PER ABN 89-840 AND VCN BB-246-1 Rev. Dote By Checked Description Appr. 1 Appr. 2 Appr. l Appr. 4 Southern Compan y Services , Inc. ,. Georgia Power Company EDWIN I. HATCH NUCLEAR POWER PLANT - UNIT No. 2 NAMEPLATE ENGRAVING LIST FOR PROJECT 1.0. DRAWING NUMBER SHEET REV. PANEL 2H11-P603 Drown: B Snow Typed: JOM Checked: 10-502 A-21603 03 1
LET- PLATE COMP TER DIMEN- COLOR ND. LABEL CONTENTS SIZE SIDNS CODING NOTES
< Lx\.J) 038 DELETED 038A DELETED 039 3.0 DELETED 040 IRM-APRM 3/16' 4' x l' B-DN-\.J LABEL 2C51-R 0 A 3/16' BELOW VITAL AC 1/ '
041 RX HI LEVEL TRIP 1/4' 3-1/2'x B-DN-W 1/2' 042 FEEDWATER ISOLATION 1/4' 3-l/2'x B-DN-W 1/2'
~
043 IRM-APRM/RBM 3/16' B-DN-W LABEL 0c 3/16' BELOW VITAL AC 1/8' 3.0 044 DELETED 045 DELETED 046 DELETED 047 DELETED 048 DELETED 049 DELETED 050 051 RBM 1/2' 2-1/2'x B-DN-W 1' 3.0 04/21/15 GTR REVISED PER ABN SNC345312J004 VER 1.0 HBF JTL VER. Date By Description Checked Appr . Southern Company Services, Inc. for Georgia Power Company [ACAD2000I A21 60304 ) "This document contains proprietary, confidential , and/or trade secret information of the subsidiaries of The Southern Company or of third parties. It is intended for use only by emp loyees of , or authorized contractors of, the subsidiaries of Th e Southern Company. Unauthorized possession , distribution co in dissemination or disclosure of on ortion her eof is rohibited ." EDWIN I. HATCH NUCLEAR PLANT UNIT No . 2 NAMEPLATE ENGRAVING LIST FOR PROJECT 1.0 DRAWING NUMBER SHEET VER PANEL 2H 11 -P603 Drawn- D.K. Designed : JDM Date: 10-502 A-21603 04 3.0
LET- PLATE COMP TER DI MEN- COLOR ND. LABEL CONTENTS SIZE SIDNS CODING NOTES ( LxW) 052 RBM BYPASS 3/ 16' 2' x B-DN-W 3/ 4' 053 REACTOR MODE 3/ 16' 2-5/ Wx B-DN-W 7/ 8' 054 DELETED 055 SCRAM GROUP B 1/4' 5' X 1H W-DN-R 1 2 3 4 056 DELETED 057 APRM BYPASS 3116' 2' x B-DN-W 314' 058 IRM BYPASS 3/ 16' 2' x B-DN-W 3/ 4' 058A DELETED 059 3/ 16' B-DN-W LABEL 3116' BELOW l /8n 4.0 060 DELETED 061 IRM-APRM B- DN-W LABEL 2C51-R603D BELOW VITAL A 062-1 DELETED 062-2 DELETED 4.0 04/ 21 / 15 GTR REVISED PER ABN: SNC345312J005 HBF JTL VER. Date By Descri tion Checked Appr. Southern Company Services, Inc. for Georgia Power Company (ACAD2000l A2160305 ) This document contains proprietary, confidential, and/ or trade secret information of the subsidiaries of The Southern Company or of third parties. It is intended for use only by employees of, or authorized contractors of, the subsidiaries of The Southern Company. Unauthorized possession, use distribution co in dissemination or disclosure of an ortion hereof is rohibited." EDWIN I. HATCH NUCLEAR PLANT UNIT No. 2 NAMEPLATE ENGRAVING LIST FOR PROJECT l.D. DRAWING NUMBER SHEET VER. PANEL 2H 1 1-P603 Drawn: D.K. Designed: J DM Date: 10-502 A-21603 05 4.0
LE T- PLATE COMP TER DI MEN - COLOR ND. LABEL CONTENTS SIZE SIDNS CODING NOTES
< Lx\.I)
DELETED \)
/ -v V' -v V' -v v -v -v V' v -v -v -v v V' -v -v V' -v 063 v v v I
064 DELETED 065 DELETED I I 066 DELETED I I 067 DELETED 068 DELETED
)
*- M 069 "--A-- - J/l6' 1::-374;-x- B-DN-\.1 2C5 1-R60 1A 1' 24/48VDC CAB 2A 1/8' 070 B 3/ 16' 1-3/4'x B-D N- \.1 2C5 1-R60 1B 1' 24/48VDC CAB 2B 1/8' 071 c 3/ 16' 1- 3/4'x B-D N-\.1 2C5 1-R60 1C 1' 24/48VDC CAB 2A 1/8' 072 D 3/ 16' 1- 3/4'x B-DN-\.1 2C5 1-R60 1D 1' 24/48VDC CAB 2B 1/8' 073 SO URCE RANGE MONITOR PERIOD 1/4' 7' xl/2' B-D N- \.1 074 A 3/16' 1-3/4'x B-DN-\.1 2C51-R600A 1' 24/48VDC CAB 2A 1/8' 075 B 3/ 16' 1-3/4'x B-D N- \.1 2C5 1-R600B 1' 24/48VDC CAB 2B 1/8' 076 c 3/ 16' 1-3/4'x B-DN-\.1 2C51-R600C 1' 24/48VDC CAB 2A 1/8' 2.0 04/22/ 15 GTR REVISED PER ABN SNC34531 2J006, VER 1.0 HBF JTL VER Date By Description Checked Appr .
Southern Company Services, Inc. for Georgia Power Company (ACAD2000 I A2160306 l "This document contains proprietary, confidential , and/or trade secret information of the subsidiaries of The Southern Company or of third parties. It is intended for use only by employees of , or authorized contractors of, the subsidiaries of The Southern Company. Unauthorized possession , use distribution coovino dissemination or disclosure of onv oortion hereof is orohibited ." EDWIN I. HATCH NUCLEAR PLANT UNIT No . 2 NAMEPLATE ENGRAVING LIST FOR PROJECT 1.0 I DRAWING NUMBER I SHEET I VER PANEL 2H 11 -P603 Draww B. SNOW I Designed : JDM I Date: 10-502 I A-21603 I 06 I 2.0
LET- PLATE ClllP TER DIIEN- ~ l<<1 LABEL CllfTENTS SIZE sum CODING tmES
<Lxll>
on D 3/16' 1-3/4'x B-clf-V 2C51-R600D 1* 24/48VDC CAB 2B 1/8' 078 SllRCE RANGE IDHTIR LEVIl. 114' 7'x112' B-clf-V 079 SllRCE RANGE LEVEL 3/16' 4* x 1* B-clf-V 2C51-R602 VITAL N; 1/8' 080-1 IELETEll 080-2 IELETEll 080-3 IELETEll 080-4 IELETEll 080-5 IELETEll c===;i A, 083 IELETEll 084 IELETEll 085 ROD VCRTH 112' s* x 2' B-clf-V MINIMIZER 086 CIH: PLATE ~/RX CIH: FLOV 2121 13 3/16' 4* x 1* B-clf-V INST BUS 2A 118' (ACAD2000( A2160307) 3.0 1041??1151 GTR I HBF IREVISED PER ABN SNC 345312J007 VER 1.0 I JTL VER I 0ate I ey I Checked I Deecrfptlon I Appr. Southern Company Services, Inc. fir Georgia Power Company EDWIN I. HATCH NUCLEAR POWER Pl.ANT - UNIT No. 2 NAMEPLATE ENGRAVING UST FOR PROJECT 1.0. I DRAWING NUMBER I SHEET I VER I 0113.o PANEL 2H11-P603 Drawn: B Snow !Typed: JDM !Checked: JMR 10-502 I A-21603
LET- PLATE COMP TER DIMEN- COLOR ND. LABEL CONTENTS SIZE SIONS CODING NOTES
<Lx\.I) 087 CRD 1/2° 5" x l" B-DN-W ORA FFFD\.JATFR cnNTRnl 1/?O 9 11 x 111 R-nN-\.J 089 REACTOR PRESSURE 3/16° 2-5/8° x B-DN-W SELECT 7/8" 090 REACTOR WATER 3/16° 2-5/8"x B-DN-W LEVEL SELECT 7/8" 091 REACTOR LEVEL 3/16' 2-5/8' x B-ON-W MODE SELECT 7/8" 092 FEED\.JATER CONTROL 3/16° 2-5/8"x B-ON-W MODE SELECT 718' 093 PUMP dp CONTROL 2-3/4"x B-DN-W l"
1/8° 3/16° 2-3/4"x B-DN-W 1// 1/8° 3/16° 2-3/4"x B-DN-W 1" 1/8° 096 RFP A EAP SPEED CNTL 3/16° 2-3/4"x B-DN-W M.097 1" 1/8° RFP B EAP SPEED CNTL 3/16° 2-3/4"x B-ON-W II 1 1/8°
- - 098 1106A 1106B 3/16° 2-5/8"x B-ON-W SQUIB VLV READY 7/8" 099 SBLC PUMP 2A 3/16° 2-5/8"x B-DN-W 2C41-C001A 7 /8" 2R24-SO 11 1/8° lUU ~BLC PUMP 2B j/16° 2-J/8"x B-UN-W 2C41-C001B 7/8" 2R24-SO 12 1/8° 4.0 7-22-10 Vep REVISED PER ABN-H01625, VER. 1.0 MLH WCN (SEE MICROFILM FOR PREVIOUS VERSION SIGNATURES)
Ver. Date By Description Checked Appr. 1 A.
"Thi~ docun1ent contain~ proprieta1y, confidential, and/or trade ~ec.ret information of the subsidiaries of The Southern Company or of third parties.
It is intended for use only by employees of, or authorized contractors of, SOUTHERN the subsidiaries of The Southern Company. Unauthorized possession, use, (ACAD2KJ A2160308 COMPANY distribution, copying, dissemination, or disclosure of any portion hereof is prohibited." EDWIN I. HATCH NUCLEAR PLANT UNIT No. 2 NAMEPLATE ENGRAVING LIST FOR PROJECT l.D. DRAWING NUMBER SHEET VER. PANEL 2H11-P603 Drawn: B.Snow Designed: JDM Date: 3-5-90 10-502 A-21603 08 4.0
LET- PLATE COMP TER DI MEN- COLOR ND. LABEL CONTENTS SIZE SIDNS CODING NOTES
<LxW) 101 SBLC MANUAL INJ 3/16' 2-5/8'x B-DN-W VLV 2C41-F008 7/8' lOlA PUMP SELECT 3/16' 2-5/8'x B-DN-W SWITCH 7/8' 102 CRD PUMP 3/16' 2-5/8'x B-DN-W 2Cll-C001B 7/8' 2R22-S006 1/8' 103 RETURN TD VESSEL 3/16' 2-5/8'x B-DN-W FLOW CONTROL 2Cll-F005 7/8' 2R24-S012 1/8' 104 PUMP B 3/16' 2-5/8'x B-DN-W LDCA TRIP RESET 7/8' 2R25-S006 1/8' 105 (DELETED
------ - - -- - - ~
y y
~>
~
A
- - - - - _J 106 CRD PUMP 3/16' 2-5/8'x B-DN-W 2C11-C001A 7/8' 2R22-S005 1/8' 107 DRIVE PRESS CNTL 3/16' 2-5/8'x B-DN-W VLV 2Cll-F003 7/8' 2R24-S012 1/8' 108 PUMP A 3/16' 2-5/8'x B-DN-W LDCA TRIP RESET 7/8' 2R25-S004 1/8' 109 FLOW CONTROL 3/16' 2-5/8'x B-DN-W VL V 2C 11 -F002A 7/8' 110 FLOW CONTROL 3/16' 2-5/8'x B-DN-W VLV 2C11-F002B 7/8' 111 STAB VALVES A8cB 3/16' 2-5/8'x B-DN-W 7/8' 112 IRM A I APRM A 3/16' 2-3/4'x B-DN-W 1.
113 IRM C I APRM C 3/16' 2-3/4'x B-DN-W 1* 1 6-24-03 DFV MDN REVISED PER ABN 00-039-007 DEW ~ ~ ~ ~ (SEE MICROFILM FOR PREVIOUS REVISION SIGNATURES Rev. Date By Checked Description Appr. 1 Appr. 2 Appr. 3 Appr. 4 Appr. 5 Southern Company Services, Inc. FoR Georgia Power Company EDWIN I. HATCH NUCLEAR POWER PLANT - UNIT No. 2 NAMEPLATE ENGRAVING UST FOR PROJECT l.D. DRAWING NUMBER SHEET REV. PANEL 2H11-P603 Drawn: B Snow I Typed: JDM IChecked: 10-502 A-21603 09 1
LET- PLATE COMP TER DI MEN- COLOR ND. LABEL CONTENTS SIZE SIDNS CODING NOTES
<LxW)
$6D 115 IRM G I RBM A 3/16' 3/16' 2-3/4' x 1.
2-3/4' x B-DN-W B-DN-W 1. 116 IRM A RANGE SW 3/16' 2-3/4' x B-DN-W 2C51-K602A 1. 117 IRM C RANGE SW 3/16' 2-3/4' x B-DN-W 2C51-K602C 1. 118 IRM E RANGE SW 3/16' 2-3/4' x B-DN-W 2C51-K602E 1. 119 IRM G RANGE SW 3/16' 2-3/4'x B-DN-W 2C51-K602G 1. 120 P603 ANNUNCIATOR 114' 4* x B-DN-W 112* 121 CRD FLOW CONTROL 3/16' 2-5/8' x B-DN-W 2Cll-R600 718' INST BUS 2A 118' 122 P603-1 112* 4* x 1' B-DN-W l c:~ P603-2 l4 IC:
'""' .. x ..
Al l B-DN-W 124 REFUEL MODE 3/16' 2-5/8' x B-DN-W SELECT PERMISSIVE 718' 125 ROD SELECT 3/16' 2-5/8' x B-DN-W POWER 718' 126 EMERG IN 3/16' 2-5/8' x B-DN-W NOTCH OVERRIDE 718' 127 SCRAM CHANNEL A 3/16' 5'x B-DN-W A2 Al 112* 128 SCRAM CHANNEL B 3/16' 5'x B-DN-W Bl B2 112* 129 CONTROL ROD SELECT 112* 9* x 1' B-DN-W 1 7-23-97 D.K. REVISED PER ABN 94-0008-017 . HEW CCS Rev. Date t:!V Descriotion Checked llPpr. l Southam Company Services, Inc. for Georgia Power Company I ( ACADR 13 A21 6031 0 ) "This document contains proprietary, confidential, and/or trade secret information of the subsidiaries of The Southern Company or of third parties. It Is Intended for use only by employees of, or authorized contractors of, the subsidiaries of The Southern Company. Unauthorized possession, use, distribution, coovina, dissemination, or disclosure of anv oortion hereof is orohibited." EDWIN I. HATCH NUCLEAR PLANT UNIT No. 2 NAMEPLATE ENGRAVING LIST FOR PROJECT l.D. DRAWING NUMBER SHEET REV. PANEL 2H 11 -P603 Drawn: D .. K. I Designed: JDM I 0ote: 10-502 A-21603 10 1
LET- PLATE COMP TER DI MEN- COLOR ND. LABEL CONTENTS SIZE SIDNS CODING NOTES
<Lx\rl) 130 REACTOR SCRAM 3/16' 2-5/8'x B-DN-W RESET 7/8' 131 ROD DRIFT 3/16' 2-5/8'x B-DN-\rl ALARM TEST INST BUS 2A 118' 7/8' 132 TIMER MALFUNCTION 3/16' 2-5/8'x B-DN-\rl SELECT BLOCK 718' 133 TI MER TEST 3/16' 2-5/8'x B-DN-\rl VITAL AC i 1s* 718' 134 ROD I ROD 3/16' 2-5/8'x B-DN-W SETTLE I OUT 314' 135 ROD I ROD 3/16' 2-5/8'x B-DN-W IN I OUT 314' 136 ROD MOVEMENT 3/16' 2-5/8'x B-DN-W CONTROL 7/8' 137 I RM B I APRM B 3/16' 2-3/4'x B-DN-W 1'
138 I RM D I RBM B 3/16' 2-3/4'x B-DN-W A:::=- 1* 3/16' 2-3/4'x B-DN-\rl 1.
~ !R! H~ !P~ A 3/16' 2-3/4'x B-DN-W 141 I RM B RANGE SW
- - 3/16' 1'
2-3/4'x B-DN-W 2C51-K602B 1' 142 I RM D RANGE SW 3/16' 2-3/4'x B-DN-W 2C51-K602D 1, 143 I RM F RANGE SW 3/16' 2-3/4'x B-DN-W 2C51-K602F 1' 144 I RM H RANGE SW 3/16' 2-3/4'x B-DN-W 2C51-K602H 1' 145 SEQUENCE MODE 3/16' 2-5/8'x B-DN-W SELECTOR 7/8' 3 7-23-97 D.K . REVISED PER ABN 94-0008-017. HEW CCS Rev. Dote l:lv Descriotlon Checked APPr. 1 Southem Company Services, Inc. for Georgia Power Company ( ACADR 13 I A21 60311 ) "lhis document contxins proprietary, c:onfidenlial, ond/or !rude 3eCIVl information of the !Ubsaaries af The Southern ~ny or of third parties, It i! idended for use only by ~ of, or authorized c:ootroctors of, the subsidiaries of The Southern Company. Unauthorized possession, use, disbibution, copying, dlssemilation, or disclosure of any portion '-of i! prohl>lted." EDWIN I. HATCH NUCLEAR PLANT UNIT No. 2 NAMEPLATE ENGRAVING LIST FOR PROJECT l.D. DRAWING NUMBER SHEET REV. PANEL 2H 11 -P603 Drnwn: D.K. I Designed: JDM I Dote : 10-502 A-21603 11 3
LET- PLATE COMP TER DIMEN- COLOR ND. LABEL CONTENTS SIZE SIONS CODING NOTES
< Lx\D 146 147 148 SRM BYPASS 3/16' 3° X B-DN-W 3/4 8 24/48VDC CAB 2A 24/48VDC CAB 2B 1/8' 149 SRM/IRM 1/2' 3-l/2°x B-DN-W 1u 150 SOURCE RANGE MONITOR 3/16' 3-l/2°x B-DN-W A B C D 718° 2R25-S101 1/8' 151 SRM/IRM 3/16' 3-l/2°x B-DN-W DRIVE CONTROL 718° 2R25-S101 1/8' 152 INBOARD VENT 3116' 2-5/8° x B-DN-W VLV 2T48-F339 1-3/8° MSL HI PRESS DVRD 2C61-S34A 153 INBOARD VENT 3/16' 2-5/8° x B-DN-W VLV 2T48-F341 1-3/8° MSL HI PRESS DVRD 2C61-S34C 154 OUTBOARD VENT 3/16' 2-5/8° x B-DN-W VLV 2T48-F338 1-3/8° MSL HI PRESS DVRD 2C61-S34B 155 OUTBOARD VENT 3/16' 2-5/8° x B-DN-W VLV 2T48-F340 1-3/8° MSL HI PRESS DVRD 2C61-S34D 156 MASTER RECIRC FLOW CONTROL
/\r--y-.,. 3/J.6' 3-114° x B-DN-W
~ ~ - ~ ~ - ~ ~718° 157 VENT - - - J/l6;- - 2-5/8° x B-DN-W VLV 2Cll-F035B 7/8° 3.0 04/27 /09 KB REVISED PER ABN 2040048501 J035, VER. 1.0. CFC JMR (SEE MICROFILM FOR PREVIOUS VERSION SIGNATURES)
Ver. Dote By Description Checked Appr. 1 A. ihis document contains proprietary, confidential, and/or trade secret information of the subsidiaries of The Southern Company or of third parties. SOUTHERN It is intended for use only by employees of, or authorized contractors of, the subsidiaries of The Southern Company. Unauthorized possession, use, ( ACAD I A2160312 ) COMPANY distribution, copying, dissemination, or disclosure of any portion hereof is prohibited." EDWIN I. HATCH NUCLEAR PLANT UNIT No. 2 NAMEPLATE ENGRAVING LIST FOR PROJECT l.D. DRAWING NUMBER SHEET VER. PANEL 2H 11-P603 Drown: B.SNOW I Designed: IDote: 03/05/90 10-502 A-21603 12 3.0
LET- PLATE COMP TER DI MEN- COLOR ND. LABEL CONTENTS SIZE SIDNS CODING NOTES
<LxW>
158 VENT 3/16 1 2-5/8 x 1 B-DN-W VL V 2C 11-F 035A 110* 159 DRAIN 3/16 1 2-51a*x B-ON-W VLV 2Cl1-F037 7/8' 160 VENT 3/16 1 2-5/e*x B-ON-W VLV 2Cll-F010B 110* 161 VENT 3/16 1 2-5/S'x B-ON-W VLV 2C11-F01 OA 7/8' 162 DRAIN 3/16' 2-5/S*x B-ON-\1 VLV 2C11-F01 l 7/8 1 163 SCRAM DISCHARGE 1/2' 5* x 2* B-ON-W VOLUME 164 DISCH VOL 3/16' 2-5/8 x 1 B-ON-W HI LEVEL BYP 719* 167 PRI CONTAINMENT 112' 5* x 1* B-ON-W 168 ROD 112* 4* x B-DN-W MOVEMENT 2-112* *~ CONTROL : :::D 169 IRM/APRM 1/2 1 5' x l' B-ON-W ts: n; s* I-' 170 SRM 112' x 1* B-ON-W ~ u.:
~
171 RMCS 112' 2' x l' B-ON-\1
~
(.,. 172 REACTOR 1/2 1 s* x 2* W-DN-R SCRAM 1 REVISED PER WCN 90-231-02 ./.ec 0 3-5-90 JMR APPROVED ISSUED PER ABC DEK RBV WLO GDM ABN 89-840 & WCN 88-246-1 Rev. Date By Checked Description Appr. 1 Appr. 2 Appr. 3 Appr. 4 Appr. 5 Southern Company Services, Inc. F<fl Georgia Power Company EDWIN I. HATCH NUCL..EAR POWER PLAf'.lT - UNIT No. 2 NAMEPLATE ENGRAVING LIST FOR PROJECT 1.0. DRAWING NUMBER SHEET REV. PANEL 2H 1 1-P60J Drawn: B Snow Typed: JDM Checked: JMR 10-502 A-21603 13 1
LET- PLATE COMP TER DI MEN- COLOR ND. LABEL CONTENTS SIZE SI DNS CODI NG NOTES
<LxW) 173 ROD 112' 4' x 2' B-DN-W DI SPLAY 174 REACTOR WATER LEVEL 1/4' 3-1 / 2' x B-DN-W 112' 175 REACTOR PRESSURE 1/4' 3-l/2'x B-DN-W 112' 176 DELETED 178 FW I NDI CATI ON l /2' 5* x 1, B-DN-w 179 MAIN STEAM LINE FLOW 1/ 4' 7' x 1/2' B-DN-W 180 DELETED 181 CRD INDICATION 112' 5' X 1 N B-DN-W 182 I RM/APRM l /2' 5' x 1, B-DN-W 183 CONTROL ROD DISPLAY 1/2' 10 6 x B-DN-W 1*
184 REACTOR CONTROL 2H11-P603
- 1. 20' x B-DN-W MFG 2 2' LABEL PLATES ONE FDR FRONT I ONE FDR BACK 185 SBLC
- 112' 4 H X 1 N B-DN-W 186 1 8-28-97 Vep REVISED PER ABN 95-0054-004 . JAB KDT (S EE MICROFILM FOR PREVIOUS REVISION SIGNATURES)
Rev, Date By Descriotian Checked Appr. 1 Southern Company Services, Inc. for Georgia Power Company ( ACAD13 I A2160314) "This document contains proprietary, confidentia l, and / or trade secret information of the subsid iaries of The Southern Company or of third parties , It is intended for use on ly by employees of, or authorized contractors of. the subsidiaries of The Southern Company. Unauthorized possession. use , distribution, copyinq, dissemination, or disclosure of any portion hereof is prohibited ." EDWIN I. HATCH NUCLEAR PLANT UNIT No . 2 NAMEPLATE ENGRAVING UST FOR PROJECT ID DRAWING NUMBER SHEIT REV. PANEL 2H 11-P603 Drawn : B.Snow I Designed ABC I Date : 3-5-90 10-502 A-21603 14 1
LET- PLATE COMP TER DIMEN- COLOR NO. LABEL CONTENTS SIZE S!ONS CODING NOTES
<Lx'w')
187 SBLC 1/2. 2-1/2'x W-DN-R 1* 188 ROD 3/8' 2-5/B'x B-DN-W MOVEMENT 2* CONTROL 189 TORUS 1/4, l-7/8'x B-ON-W 112* 190 DRYWELL 114' 2-l/8'x B-ON-W 112* 191 DISCH VOL 3/16' 2-5/8 'x B-ON-IJ PLACE BELO~ ISDL TEST 7/8' COMPONENT 1&2 192 CORE dp 3/16' 2' x B-ON-W INFORMATION 100%=30 PSI 3/4' LABEL PLACE BELOW RECORDER 193 READY 3116. 2' x B-ON-W TO RESET i/8' 194 MANUAL 3/ 16' 2' x B-DN-IJ INITIATION 7/8, 195 PDIJER 3/16' 2' x B-ON-W AVAILABLE 7/8' 196 MANUAL INITIATION 3116' 2-5/B'x B-DN-W CH A. 718'
\I~:iyuf CA~ 2D 197 MANUAL INITIATION !/~ 2-5/8'x 3/16' B-ON-W CH B 718'
\l~J~Dk CM 2D 118.'I 1 198 RESET 3116'/ 2-5/8'x B-ON-W
\125VDC C_A~ _2D ll_if 718' 1 ~ ..14<1 T.N. :PW,..$ REVISED PER ABN 93-0236 ;.J\ l(~I ><= >< .:::><::.
0 3-5-90 8.A. JMR APPROVED, ISSUED PER ABN 89-840 ABC DEK RBV WLO GDM ANO WCN 88-246- l Rev. Dote By Checked Description Appr. 1 Appr. 2 Appr. J Appr. 4 Appr. 5 Southern Company Services, Inc. FOR Georgia Power Company( ACAD I A2160315) EDWIN I. HATCH NUCLEAR POWER PLANT - UNIT No. 2 NAMEPLATE ENGRAVING LIST FOR PROJECT LD . DRAWING NUMBER SHEET REV. PANEL 2H11 -P603 Drawn: B Snow jTyped: JDM !Checked: 10-502 A-21603 15 1
LET- PLATE COMP TER DI MEN- COLOR ND. LABEL CONTENTS SIZE SIDNS CODI NG NOTES
<Lx\J) 199 ARI 112* 3* x 1* W-DN-R 200 ARI 3/16' 2' x B-DN-W SYSTEM 2-7 /8' TEST 201 A ARI ANNUNCIATOR 114' 3-l/2'x B-DN-W 112*
201. B ARI ANNUNCIATOR 114' 4* x B-DN-1.1 112* 202A DELETED DELETED INFO LABEL CONTENTS CONTROLLED BY DPS cU4 l N~ LI LA.81:..L CONTENTS CONTROLLED BY DPS 205 DELETED 206 DELETED 207 INFO LABEL CONTENTS CONTROLLED BY DPS 208 RWM OPERATOR 3/16' 2-5/8' x B-DN-W DI SPLAY 1-114' 2C11-J600 3 7-23-97 D.K. REVISED PER ABN 94-0008-017 . HEW CCS Rev. Date Descri tion Checked r. Southem Company Services, Inc. for Georgia Power Company (ACADR13l A2160316) "This document contains proprietary, confidential, and/or trade secret information of the subsidiaries of The Southern Company or of third parties. It Is Intended for use only by employees of. or authorized contractors of, the subsidiaries of The Southern Company. Unauthorized possession, use, distribution, co in , dissemination, or disclosure of an ortion hereof is rohibited ." EDWIN I. HATCH NUCLEAR PLANT UNIT No. 2 NAMEPLATE ENGRAVING LIST FOR PROJECT l.D. DRAWING NUMBER SHEET REV. PANEL 2H 11-P603 Drawn: B SNOW Designed: JDM Date: 10-502 A-21603 16 3
LET- PLATE CDMP TER DI MEN- CDLDR ND. LABEL CONTENTS SIZE SIDNS CODING NDTES
<Lx\O CDRE DISPLAY MATRIX 50 3/16' 3/4' x B-DN-W 3/4' 46 3/16' 3/4' x B-DN-W 3/4' 42 3/16' 3/4' x B-DN-\1 3/4' 38 3/16' 3/4' x B-DN-\1 3/4' 34 3/16' 3/4' x B-DN-W 3/4' 30 3/16' 3/4' x B-DN-W 3/4' 26 3/16' 3/4' x B-DN-W 3/4' 22 3/16' 3/4' x B-DN-W 3/4' 18 3/16' 3/4' x B-DN-W 3/4' 14 3/16' 3/4' x B-DN-W 3/4' 10 3/16' 3/4' x B-DN-W 3/4' 06 3/16' 3/4' x B-DN-W 3/4' 02 3/16' 3/4' x B-DN-W 3/4' 03 3/16' 3/4' x B-DN-W 3/4' 07 3/16' 3/4' x B-DN-W 3/4' 11 3/16' 3/4' x B-DN-W 3/4' 15 3/16' 3/4' x B-DN-W 3/4' 19 3/16' 3/4' x B-DN-W 3/4' 23 3/16' 3/4' x B-DN-W 3/4' 27 3/16' 3/4' x B-DN-W 3/4'
- .~ ~
0 =<-5-~ 'B--1. J.M R APPROVED. ISSUED PER l~C ~ .-!<._ f),/ lffA'l' JKan ABN 89-840 AND WCN 88-246-1 Rev. D<lte By Checked Description Appr. 1 Appr. 2 Appr. 3 Appr. 4 Appr. 5 Southern Company Services, Inc. Georgia Power Company EDWIN I. HATCH NUCLEAR POWER PLANT - UNIT No. 2 NAMEPLATE ENGRAVING usr FOR PROJECT l.D. DRAWING NUMBER SHEET REV. PANEL 2H11-P603 10-502 A-21603 17 0 Drawn: 8 Snow I Typed: JDM IChecked: T f1 R.
LET- PLATE COMP TER DI MEN- COLOR ND. LABEL CONTENTS SIZE SIDNS CODI NG NOTES
<Lx\I)
CORE DISPLAY MATRIX 31 3/16' 314' x B-DN-\./ 314' 35 3/16' 314' x B-DN-\./ 314' 39 3/16' 314' x B-DN-\./ 314' 43 3/16' 314' x B-DN-\./ 314' 47 3/16' 314' x B-DN-\./ 314' 3/16' 314' x B-DN-\./ 314' 209 APRM OPERATOR 3/16' 2-5/8'x B-DN-W DI SPLAY 1, 2C51-K620A 2R25-S063 1/8' 210 APRM OPERATOR 3/16' 2-5/8'x B-DN-W DI SPLAY 1. 2C51-K620B 2R25-S063 1/8' 211 RBM OPERATOR 3/16' 2-5/8'x B-DN-W DI SPLAY 1. 2C51-K620C 2R25-S063 1/8' 212 RBM OPERATOR 3/16' 2-5/8'x B-DN-W DI SPLAY 1. 2C51-K620D 2R25-S063 1/8' 213 214 DELETED 215 DELETED 7-23-97 D.K. REVISED PER ABN 94-0008-017 . HEW CCS Rev. Date Descri tion Checked r. Southem Company Services, Inc. for Georgia Power Company I ( ACADR 13 A21 60318 ) "This document contains proprietary, confidential, and/or trade secret information of the subsidiaries of The Southern Company or of third parties. It is intended for use only by employees of, or authorized contractors of, the subsidiaries of The Southern Company. Unauthorized possession. use, distribution, co in , dissemination, or disclosure of an ortion hereof is rohibited.
- EDWIN I. HATCH NUCLEAR PLANT UNIT No. 2 NAMEPLATE ENGRAVING LIST FOR PROJECT l.D. DRAWING NUMBER SHEET REV.
PANEL 2H 11 -P603 Drown: D.K. Designed: JDM Date: 10-502 A-21603 18 1
LET- PLATE COMP TER DIMEN- CDLDR NO. LABEL CONTENTS SIZE SIDNS CODING NOTES
<Lxll) s RHR HX SERV WTR fUl\I 3/ 16' 1-3/4'>< B-DN-W LABEL ON 2E 11-R071 l' LEH 6 DOME TEMP 3/ 16' 2-S/8'x B-DN-W 2T47-R070 7/8' 8 SACRIFICIAL SHIELD 3/16. 2-5/B* x B-DN-W EXIT TEMP 1-1/ 41 2T47-R071 9 UPPER SPHERE TEMP 3/16' 2-5/B'x B-DN-W 2T47-R072 7/8 10 PRESS 3/ 16' 1-3/4'x B-DN-W 2T48-R071 l' 11 CRD CAVITY TEMP 3/16' 2-5/B'x B-DN-W 2T47-R073 7/8' 12 WATER TEMP 3/ 16' 2-5/S'x B-DN-W R072 7/8' 13 LEVEL 3/16' 1-3/4'x B-DN-W RESTRICTED R070 1/2' SPACING 14 VAPOR TEMP 3/tt>* 2-5/B'x B-DN-W R073 7/8' IS 5 CIRCUIT PWR SPLY 3/16' 2-5/8'x B-ON-W LABEL ON 2E11-K070 718' RIGHT 19 RHR HX SERV WTR fUlV 3/t6* 2-5/B'x B-ON-w LABEL ON 2E 11-K071 7/8' LEFT 20 2P41-COO lB 3/t6* 2-5/B'x B-ON-W 7/8' 21 2C 11-COO 1B 3/16. 2-5/B'x B-DN-W 7/8' 22 XFER S\I 3/t&* 2-5/B'x B-DN-W 2C82-S70 7/8' 23 XfER SW 3/t(,* 2-5/B'x B-DN-W 2C82-S71 7/8' AJL._
0 BAS APPROVED. ISSUED PER ABN 90-296 (NO OCR) Rev. Dote By Checked Deecription Appr. 1 Appr. 2 Appr. 3 Appr. 4 Appr. 5 Southern Company Services, Inc. '" Georgia Power Company EDWIN t. HATCH NUCLEAR POWER PL.ANT - UNIT No. 2 NAMEPLATE ENGRAVING LIST FOR PROJECT 1.0. DRAWING NUMBER SHEET REV. PANEL 2H21-Pl7J Drawn: B Snow I Typed: JOM !Checked: 10-502 A-21725 01 0
1 LET- PLATE COMP TER DI MEN- COLOR NO. LABEL CONTENTS SIZE SIONS CODING NOTES (lx\I ) 24 REMOTE SHUTDOllN INST 3/4' 23'x 2* B-ON-W CONDENSE 2H21-P 173 SPACING TD - FIT 23' 25 DRY WELL 112* s* x i* B-ON-W r
- 2*
~
- 3. B-DN-W 26 SUPP CHAMB l/2' x 27 2T48 112' ,t 2* x 3* ) B-DN-W
~
1, I~ 2' 3* B-DN-W 1 28 1/2' ~ X
~
~
I 29 ~ CRD \ 112* B-DN-W
~x!)
/2\-
PUMP ~
-A -
~ '.
.,-~
( ACAD I A2 172502 ) 2 3-1
- 1-~ BAS HiAJ R'S£0 PER ABN 92-0517 LtP ~// ""><' ~ ><
1 11-27-90 BAS KWH REVISED PER ABN 90-573 JAH DE K ~ 0 7-26-90 BAS RLE N'PRCMO ISSUED PER ABN 90-296 (NO OCR) ABC WTB >< >< >< Rev. Date By Checked Description Appr . 1 Appr. 2 Appr. 3 Appr . 4 Appr. 5 Southern Company Services, Inc. FM Georgia Power Company EDWIN I. HATCH NUCLEAR POWER PLANT - UNIT No. 2 SHEET REV. NAMEPlATE ENGRAVING UST fOR PROJECT l.D. DRAWING NUMBER PANEL 2H21-P173 I Typed: JDM !checked: 10-502 A-21725 02 2 Drown: B Snow
LET- PLATE COMP TER DI MEN- COLOR ND. LABEL CONTENTS SIZE SID NS CODING NOTES ClxW) I TURB SPEED 3/I6' 1-3/4'x B-ON-W 2C82-R003 l' PF - LAMP/KEY l/4' 2-112* x 8- 0N-W 1 ( 2 PF - LIGHT 3/16' l-1/2' ON SETPOI NT OFF fl OW 3 ceu, END B~ 3/16' 2-5/A""x 8-0N-W HIGH TEMP 7/8' 4 BRG OIL 3/I 6' 2-5/8' x 8-0N-W LOW PRESS 7/8' 6 SDC SUCTION VLV 3/I6' 2-5/8' x 8-0N-W 2El l-F009 7/8' 2R24-S0ll I /8' 7 2El l - F006A 3/16' 2-5/9' x 8- 0N- W 2R24-SOl I I /8' 7/8' 8 COND PUMP 3/16' 2- 5/8' x B- ON- W 2E5l -C002 - I 7/8' 2R24-S021 l /8' 9 2C82-KI 3/16' l-3/4'x B-ON-W I' IO 2C82-R001 3/16' 1-314' B-ON-W l' II TURBINE 1/4' 3-1 /2' x B-ON- W 5/8' 12 GOV BRG 3/16' 2-5/8' )( B-ON-W HIGH TEMP 7/8' 13 XFER SW 3/16' 2-5/8' x B-ON-W 2C82-S7 718' 14 2E5I -F007 3/16' 2- 5/8' x B- ON-W 2R24-S012B l/8' 7/8' 15 XFER SW 3/16' 2-5/8' x B-ON-W 2C82-S53 7/8' 16A SID CLG VLV 1/4' 3-l/2'x B-ON-W 5/8' ( ACAD [ A2172601) 0 712519 RAS RLB APPROVED ISSUED PER ASK WTB ABN 90 296 fNO OCR'\ l L?-5'11* CRP ,~ APPROVED ISSUED PER ABN 92-093-002 Rov. Dote Checked Description Appr, 1 Appr. 2 Appr. 3 Appr. 4 Appr. 5 Southern Company Services, Inc. *r Georgia Power Company I EDWIN I. HATCH NUCLEAR POWER PLANT - UNIT No. 2 NAMEPLATE ENGRAViNG UST fOR I PROJECT 1.D. I DRAWING NUMeER I SHEET f REV. I oiT PANEL 2CB2-P001 I
. ... Drawn: B Snow ! Typed: JOM lchecked: 10-502 I A-21726 1 I f
LET- PLATE COMP TER DI MEN- COLOR ND. LABEL CONTENTS SIZE SIDNS CODI NG NOTES ClxW> 16B SID l /2" 2-5/B*x B-DN-W CLG 2* 17 2E11-F006C 3/16 1 2-5/B* x B-DN-W 2R24-S011 110* 7/8" 18 XFER SW 3/16" 2-5/B*x B-ON-W 2C82-S52 110* 19 BAROMETRIC CNDSR 1/4" 3-l/2 x 1 B-ON-W 5/8 1 20 VAC PUMP 3/16 1 2-5/B*x B-ON-W 2E51-C002-2 7/8" 2R24-S021 110* 21 XFER SW 3/t 6* 2-5/B"x B-DN-W 2CB2-S6 110* 22 2CB2-K2 3/16' 1-3/4' x B-ON-W 1. c----- 23 FLOW CONTROL 1/4' 3-112*x B-ON-W -,,A 5/8'
........ .................... - - -- - . 1 24 25 TRIP 3/16' 2-5/B'x B-DN-W 7/8' 26 STEAM SUPPLY 3/8' s* x B-DN-W INBD ISOL VLV 1-1/4' 27 TORUS !NBD SUCTION 3/16' 2-s10*x B-DN-W VLV 2E51-F031 7/B*
2R25-S021 1/8. 28 TEST LINE TD CST 3/t 6* 2-5/B'x B-ON-W 2E51-F022 7/B' 2R24-S021 110* ( ACAD XA2172602 ) 0 7 /26/9( BAS RLB APPROVED. ISSUED PER ASK WTB "">< >< ~ ABN 90-296 (NO OCR) 1 ~- 5-'1lJJ CRP I~ APPROVED. ISSUED PER ~47,,I. '"':><:' "">< >< ~ ABN 92-093-00 2 Rev. Dote By Checked Description Appr. 1 Appr. 2 Appr. 3 Appr. 4 Appr. 5 Southern Compan y Services, Inc. rar Georgia Power Company EDWIN I. HATCH NUCLEAR POWER PLANT - UNIT No. 2 NAMEPLATE ENGRAVING LIST FOR PROJECT 1.0. DRAWING NUMBER SHEET REV. PANEL 2C82-P001 Drown: B Snow !Typed: JDM IChecked: 10-502 A-2172 6 02 1
LET- PLATE COMP TER DI MEN- COLOR NO. LABEL CONTENTS SIZE SIONS CODING NOTES
<LxW) 29A STM TO TURB VL V 2E51 2R24-S021 1/4' 118' 3-l/2'x
- 1. B-ON~W A 29B DELETED
- _)
~
~---------.-. ..... - ..-. ..... ------
- - ~-- - - ~
29C VLV F045 3/16' 2-5/8'x B-ON-Y 7/6' 30 CST SUCTION 3/16' 2-5/8'x B-ON-W VLV 2E51-F010 7/8' 2R24-S021 1/8' 31 RCIC 1/2' 5' x 1* B-ON-W 32 2E51-F012 3/16' 2-5/8'x B-ON-W 2R24-S021 1/8' 7/8' 33 PUMP 3/8' 2* x B-ON-W 1-1/4' 34 XFER SW 3/16' 2-5/8'x B-DN-W 2C82-S4 7/8' 35 TRIP 8c THROTTLE 3/16' 2-5/8'x B-ON-W VLV 2E51-F524 7/8' 2R24-S021 1/8' 36 TURBINE 3/8' 2' x B-ON-W 1-1/4' 37 XFER SW 3/16' 2-5/8'x B-ON-W 2C82-S5 7/8' 38 MIN FLOW VLV 3/16' 2-5/8'x B-ON-W 2E51-F019 7/8' 2R24-S021 1/8' 39 XFER SW 3/16' 2-5/8'x B-ON-W 2C82-S3 7/8' 1 I - 5*ql o TJS khJ1) REVISED PER ABN 94-0034-0 12. ~ti?><><><>< 0 7-26-90 BAS RLE APPROVED ISSUED PER ABN 90-296 (NO OCR) . REV. DATE BY CHK'!J ABC WTB >< >< >< Description Af'. 1 AP. 2 Af'. 3 AP. 4 Af'. 5 Southern Compan y Services , Inc. for Georgia Power Compan y EDWIN I. HATCH NUCLEAR PLANT UNIT No. 2 1--"-C=on= ti=nu=ed=-- --=-on"'--T- sh""""e-'-'et '-------.-----. -- NAMEPLATE ENGRAVING LIST FOR PROJECT 1.0. DRAWING NUMBER SHEET REV. _______ PA_N_E_L_2C_,....8_2_-P_0_0_1 -----1 10-5 02 A-217 26 - Drawn: B. Snow !Checked: 03 1
LET- PLATE COMP TER DI MEN- COLOR NO. LABEL CONTENTS SIZE SIONS CODI NG NOTES CLxW) 40 2C82-K002 3/16' 4' x 1* B-ON-\i 41 DISCH VLV 1/4' 3-112* x B-ON-W 5/8' 41 A LEVEL 3/16' 1-3/4' B-DN-\i 2C82-R005 1* 42 2E51-F013 3/16' 2-5/B'x B-ON-W 2R24-S021 1/8' 7/8' 42A PRESS 3/16' 1-3/4' B-DN-W 2C82-R006 1' 43 TURB CLG WTR VLV 3/16' 2-5/B'x B-DN-W 2E51-F046 719* 2R24-S021 1/8' 44 TORUS DUTBD SUCTION 3/16' 2-5/B'x B-DN-W VLV 2E51-F029 7/8' 2R24-S021 1/8' 44A NUC BLR 112* 5' x l' B-ON-W 45 2C82-Kl0 3/16' 1-3/4' B-ON-W 1. 46 I NSTM 3/16' 2-5/B'x B-DN-W XFER SW 1-1/4' 2C82-S18 47 LLS/MANUAL 3/16' 2-5/B'x B-DN-W RELi EF VLV 1. 2B21-F013F 12SVDC CAB 2A 1/8
~A 1
47A LLS/MANUAL
- ~ ~
3/16'
- 5/B'x
- - - B-DN-W RELi EF VLV 1.
2B21-F013B 125VDC CAB- -2A - - - 1/8' - - 48 XFER SW 3/16' 2-5/B'x B-DN-W 2C82-Sl5 7/8' 49 2E51-F008 3/16' 2-5/8'x B-ON-W 2R24-S021 1/8' 7/8'
~ REVISED PER ABN 94-004.3-006~~'"f ~ ~ ">< ~
0 7-26-90 BAS RLE APPROVED, ISSUED PER .... A~ WTB ~ .><: .><: ABN 90-296 (NO DCR) ~ .><: .><: Rev. Dote By Checked Description Appr. 1 Appr. 2 Appr . .3 Appr. 4 Appr. 5 Southern Company Services, Inc. ror Georgia Power Company EDWIN I. HATCH NUCLEAR POWER PLANT - UNIT No. 2 NAMEP!J\TE ENGRAVING LIST FOR PROJECT 1.0. DRAWING NUMBER SHEET REV. PANEL 2C82-P001 Drown: 8 Snow ITyped: JDM !Checked: 10-502 A-21726 04 1
LET- PLATE COMP TER DI MEN- COLOR NO. LABEL CONTENTS SIZE SIDNS CODI NG NOTES (LxW> so XFER SW 3/16. 2-s1s*x B-DN-W 2C82-S2 719* 51 STEAM SUPPLY 319* 5* x B-ON-W OUTBD ISOL VLV 1-114* 52 REMOTE SHUTDOWN 2CB2-P001 17-1/4*x B-DN \I
- 1. 2*
53 DEMARCATION ACCORDING TO TRANSFER SWITCH-CONTROL RELATIONSHIP 3/16* 5* x B-DN-W 719* 54 RHR 8. 112* 5* x 2* B-ON-W NUC BLR 56 RX HEAD SPRAY 3/16. 2-5/B*x B-ON-W
!SOL VLV 2Ell-F023 719*
2R24-S022 l /8' 58 2C82-R004 3/16' 1-3/4"x B-DN-W 1. 59 FLOW 3/8' 2* x B-DN-W 1-1/4" 60 XFER SW 3/t 6* 2-5/B"x B-DN-W 2CB2-SB 718" 61 2El 1-C002B 3/16' 2-5/B"x B-ON-W 2R22-S007 118" 7/8" REVISED PER ABN 94- 0043-00 0 7-26-90 RLE APPROVED, ISSUED PER ABN 90-296 NO OCR Rev. Dote By Checked Description Appr. 1 Appr. 2 Appr. 3 Appr. 4 Appr. 5 Southern Company Services, Inc. far Georgia Power Company EDWIN I. HATCH NUCLEAR POWER PLANT - UNIT No. 2 NAMEPLATE ENGRAVING LIST FOR PROJECT l.D. DRAWING NUMBER SHEET REV. PANEL 2CB2-P001 Drown: 8 Snow Typed: JDM Checked: 10-502 A-21726 05 1
LET- PLATE COMP TER DI MEN- C(J_OR NO. LABEL CONTENTS SIZE SIONS CODING NOTES
<Lx\I) 62 PUMP 3/8' 2* )( B-ON-W 1-1/4' 63 XFER SV 3/ 16' 2-5/8'x B-ON-W 2C82-S9 718' 64 SDC SUCTION VlV 3/ 16' 2-5/B'x B-DN-W 2E 11-FOOB 718' 2R24-S022 1/B' 65 XFER S\I 3/16' 2-5/8'>< B-DN-W 2C82-S1 718' 66 SUCTION VLV 3/ 16' 2-5/8'>< B-DN-W 2B31-F023B 718' 2R24-SO 18B 1/8' 67 RECIRC PUMP 112' 5' x l' B-ON-W 68 XFER SV 3/16' 2-5/B'x B-ON-W 2C82-S1G 718' 69 MIN FLOW 3/8' 2' x B-ON-\1 VLV 1-114' 70 INBD INJ VLV 3/16' 2-5/B'x B-ON-V 2E 11-FO 15B 718' 2R24-S018B 1/8' 71 TORUS SPRAY VL V 3/16' 2-S/B'x B-ON-W 2E1 l-F027B 718' 2R24-S012 1/B' 72 SERV VTR CRDSSTIE 3/16' 2-5/B'x B-DN-W VLV 2Ell-F073B 7/8' 2R24-S012 118' 73 2E 11-F007B 3116' 2-5/S'x B-ON-V 2R24-SO lBB 1/8' 7/8' 74 XFER SV 3/16' 2-5/S'x B-DN-W 2C82-S80 718' 0 7 J.. t BAS ~., APPROVED. ISSUED PER ABN 90-296 {NO OCR)
Dncrlptlo n Appr. 1 Appr. 2 Appr. J Appr. 4 Appr. 5 Rev. Date By Checked Southe rn Comp any Servic es, Inc. '" Georgi a Power Compa ny EDWIN I. HATCH NUCLEAR POWER PLANT - UNIT No. 2 PRo.JECT 1.0. DRAWING NUMBER SHEET REV. NAMEPLATE ENGRAVING UST FOR PANEL 2C82-P0 01 10-50 2 A-217 26 06 0 Drown: B Snow I Typed: JD~ lcti-ked:
UT- PL.ATE Cl)4P TER DIMEH- CCl.c:R NU. LABEL CONTENTS Sizr SIONS CODit<< 1-llHI 2E t 1-COO tD 7/8' 2R22-S007 ve* e5 SHUTDOVN CLG VL. V 311&' 2-5/B'x B-ON-V I 2E 11-ro 0f.B 7/8' 2R24-S012 1/8' 86 HX TD RCIC 31 I&' 2-S/8')( 8-0N-V 2E11-f"OZ6B 7/8' 2R24-S012 118' 1 2-07-03 RCR REVISED PER ABN 02-037 1. PWG ASK (SEE MICROFILM FOR PREVIOUS REVISION SIGNATURES) Rev. Date By Description Checked Appr. 1 A
"This document contains proprietary, confidential, and/or trade secret information of the subsidiaries of The Southern Company or of third parties.
It is intended for use only by employees of , or authorized contractors of , SOUTHERN the subsidiaries of The Southern Company. Unauthorized possession, use, [ACADOVYJ A2172607 J COMPANY distribution, copying, dissemination, or disclosure of any portion hereof is prohibited." EDWIN I. HATCH NUCLEAR PLANT UNIT No. 2 NAMEPLATE ENGRAVING LIST FOR PROJECT l.D. I DRAWING NUMBER I SHEET I REV. PANEL 2C82-P001 Drawn: B SNOW I Designed: - I Dote: - 10-so2 I A-21726 I 01 I 1
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Revised by SNC per Document No.: A-47039 ABN H02887 Version 1.0 Document Ver.: 2.0 By: PVK Checked: LCF Approved: RKF Date: 05/02/2013 DOCUMENT INSERTION SHEET E. I. Hatch Nuclear Plant - Unit No. 1 / 2 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
Description Remove Insert
- 1. This insertion sheet Existing Sheet(s) Front of Manual
- 2. Replace Review Summary Sheet 1 of 362 to correct error Existing Sheet(s) SNC Ver. 2.0 identified Per SNC460325, (pdf page 2 of 364)
- 3. Replace Review Summary Sheet 171 of 363 to correct Existing Sheet(s) SNC Ver. 2.0 error identified Per SNC460325, (pdf page 172 of 364)
Document Insertion Sheet.dot
LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
Note: This Aging Management Review Summary provides for compliance with 10 CFR 54.37(b) for E.I. Hatch Nuclear Plant (HNP) regarding inclusion of systems, structures, and components (SSCs) newly identified subsequent to issuance of the renewed operating license in the FSAR, as appropriate. This Aging Management Review Summary is incorporated by reference into the HNP FSAR. The two key aspects of this document are:
- 1. LRA System description information regarding the intended functions performed by the system.
- 2. Aging management review (AMR) results for each LRA System within the scope of license renewal.
See NMP-ES-063 and sub-tier instructions for information on how to use this document. Southern Company Services, Inc. for Georgia Power Company This document contains proprietary, confidential, and/or trade secret information of the subsidiaries of the Southern Company or of third parties. It is intended for use only by employees of, or authorized contractors of, the subsidiaries of the Southern Company. Unauthorized possession, use, distribution, copying, dissemination, or disclosure of any portion hereof is prohibited. EDWIN I. HATCH NUCLEAR PLANT UNITS 1 & 2 LICENSE RENEWAL AGING MANAGEMENT REVIEW Word 2007
SUMMARY
PROJECT I.D. DRAWING NUMBER SHEET VER. Drawn: Designed: Date:06/14/2012 A-47039 1 of 362 2.0
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 2 of 363 TABLE OF CONTENTS 1 GENERAL INFORMATION 1.1 Introduction 3 1.2 Definitions 3 1.3 Content and Use 4 1.4 Development Methodology 8 2 TECHNICAL INFORMATION 2.0 Systems and Structures Within the Scope of License Renewal 9 2.1 Reactor, Nuclear Boiler, and Reactor Recirculation Systems 14 2.2 Engineered Safety Features 32 2.3 Auxiliary Systems 78 2.4 Steam and Power Conversion Systems 166 2.5 Structures and Component Supports 174 2.6 Electrical Components 219 3 REFERENCES 3.1 Edwin I. Hatch License Renewal Docket 238 3.2 NRC References 238 3.3 Other References 238 APPENDIX A - 10 Program Elements 240 APPENDIX B - Typical Structure, Component and Commodity Groupings and Active/Passive Determinations for the Integrated Plant Assessment 245 APPENDIX C - Hatch LR Emails from Ray Baker (SNC) to William Burton (NRC) 261
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 3 of 363 1 GENERAL INFORMATION 1.1 Introduction This Aging Management Review Summary provides for compliance with 10 CFR 54.37(b) for E.I. Hatch Nuclear Plant (HNP) regarding inclusion of systems, structures, and components (SSCs) newly identified subsequent to issuance of the renewed operating license in the FSAR, as appropriate. This Aging Management Review Summary is incorporated by reference into the HNP FSAR. The License Renewal Rule, Section 10 CFR 54.37 contains the following record-keeping requirements: §54.37 Additional records and record-keeping requirements. (a) The licensee shall retain in an auditable and retrievable form for the term of the renewed operating license all information and documentation required by, or otherwise necessary to document compliance with, the provisions of this part. (b) After the renewed license is issued, the FSAR update required by 10 CFR 50.71(e) must include any systems, structures, and components newly identified that would have been subject to an aging management review or evaluation of time-limited aging analyses in accordance with §54.21. This FSAR update must describe how the effects of aging will be managed such that the intended function(s) in §54.4(b) will be effectively maintained during the period of extended operation. 1.2 Definitions For use in the SNC process, the following key definitions are provided: "New LR Scope" SSCs are those SSCs that were not included within the scope of license renewal at the time of the issuance of the renewed operating license, but which now: I. Perform one or more of the intended functions described in 10 CFR54.4:
- 1. 10 CFR 54.4(a)(1) Safety Related Components
- 2. 10 CFR 54.4(a)(2) Non-safety Related Components potentially affecting Safety-Related Components
- 3. 10 CFR 54.4(a)(3) Relied on to demonstrate compliance with regulations for:
- Fire Protection - 10 CFR 50.48
- Environmental Qualification - 10 CFR 50.49
- Pressurized Thermal Shock - 10 CFR 50.61
- Anticipated Transients without SCRAM - 10 CFR 50.62
- Station Blackout - 10 CFR 50.63 AND which are II. Passive [10 CFR 54.21(1)] and long-lived [10 CFR 54.21(2)]
AND which were III Already installed in the plant when the renewed license was issued on January 15, 2002. Page 1-1
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SHEET 4 of 363 In effect, New LR Scope SSCs are SSCs which would have been subject to aging management review if identified prior to issuance of the renewed operating license. "Newly Identified" SSCs are those SSCs which meet criteria I, II, and III above, but also are determined (by review against this Aging Management Summary) not to have a previously documented system specific aging management review. That is, for the SSC's system, an aging management review item which addresses the component type, intended function(s), material(s), and environment(s) is not included in this Aging Management Summary. These newly identified SSCs must undergo aging management review, with the results added to this Aging Management Review Summary and the FSAR Supplement. A newly identified determination may result from a CLB change, design change, Condition Report, or operating experience review. Once an SSC is determined to be newly identified through use of SNC procedures and this Aging Management Review Summary, new AMR results information must be added to this Aging Management Review Summary . Other definitions applicable to this Aging Management Review Summary are contained in the SNC License Renewal Implementation Program, NMP-ES-063. 1.3 Content and Use Sections 1.3.1 and 1.3.2 describe the general content of the two key aspects of this Aging Management Review Summary. Use information provided in this Aging Management Review Summary is not intended to specify the processes and procedures by which SNC personnel will enter information into this Aging Management Review Summary or perform 10 CFR 54.37(b) evaluations required to update this Aging Management Review Summary. See References 3.3.1, 3.3.2, 3.3.3, 3.3.5, 3.3.7, 3.3.9, and 3.3.11 for procedural guidance on the use of this Aging Management Review Summary. 1.3.1 System Identification Lists and System Description Information Content Section 2.0 of this Aging Management Review Summary identifies the systems included within the scope of license renewal (LRA Systems). For NRC review purposes, HNP systems were grouped / classified into LRA Systems that generally follow the systems outlined in NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants. Performance of aging management reviews on these higher level LRA Systems allows for less duplication of aging management reviews (AMRs). Sections 2.1 through 2.6 contain LRA System description information regarding the intended functions performed by the system. This information is predominantly extracted from the License Renewal Application and is based on FSAR information. The intent of the systems description information provided is to enable SNC personnel to make a determination as to which LRA System the New LR Scope SSC would have been grouped with in the Integrated Plant Assessment (IPA). The LRA System description information is not intended to define the extents of the license renewal boundary. It is a tool for identifying the proper LRA System bin for AMR purposes only. Scoping basis documentation and license renewal boundary drawings are available to identify the extent of the license renewal boundaries for each LRA System. Only additions of new LRA Systems to the list of systems within the scope of license renewal are required. Deletions of systems specifically excluded from the scope of license renewal are NOT required. Page 1-2
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SHEET 5 of 363 Use System listings and descriptions are used to determine if New LR Scope SSC(s) are addressed by an LRA System already within the scope of license renewal, or if inclusion of the SSC(s) will result in identification of a new LRA System within the scope of license renewal. 1.3.2 Aging Management Review Results Content Sections 2.1 through 2.6 contain aging management review (AMR) results for each LRA System within the scope of license renewal. These AMR results are presented in tabular form following the system description information for each LRA System. AMR results are presented at the same level of detail as originally contained in the LRA, as amended by docketed correspondence, which is the level of detail originally required for NRC staff acceptance. When the LRA system is within the scope of license renewal for both Units 1 and 2, no distinction is made between the Units, and an AMR originally applicable only to one Unit may be applied to the alternate Unit without the need to revise this Aging Management Review Summary. AMRs have been performed for HNP:
- As part of the original license renewal process, with the results presented in the E.I. Hatch License Renewal Application,
- As part of the NRC review process, with results presented in SNC responses to NRC requests for additional information, And,
- Subsequent to issuance of the renewed operating license in accordance with SNC procedures and processes contained in References 3.3.1, 3.3.2, 3.3.3, 3.3.5, 3.3.7, 3.3.9, and 3.3.11.
The Aging Management Review Results Tables contain the following seven columns:
- Column 1 - Component Type This column identifies the component types requiring aging management review for the system or structure. Component types are generally based on the list of component types provided in Appendix B of NEI 95-10.
Component types are in many cases "groupings" of system components (e.g. piping and fittings). For some key system components (e.g. pumps, heat exchangers, vessels), the component or assembly may be specifically identified.
- Column 2 - Intended Function This column identifies the applicable intended function(s) for each component type.
- Column 3 - Material This column identifies the material(s) of construction for each component type. Materials of construction are presented at a "material class" level (e.g. stainless steel, carbon steel) based upon similar aging effects requiring management, not at the "material grade" level (e.g. 304L, CF8, A193 B7).
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SHEET 6 of 363
- Column 4 - Environment This column identifies the environment(s) for each component type. Where applicable, environment subcategories have been utilized to clarify the specific environment for the component type. For example, raw water environment subcategories include river water, potable water, and drainage.
- Column 5 - Aging Effects Requiring Management This column identifies the aging effects requiring management for each component type, material, and environment combination. The aging effects requiring management are those effects that must be managed to maintain the intended function of the component type for the period of extended operation.
- Column 6 - Aging Management Programs This column identifies the aging management programs credited for each component type to demonstrate that the aging effects requiring management will be adequately managed such that the intended function of the component type will be maintained for the period of extended operation. An acceptable aging management program should consist of the 10 elements described in Appendix A of NUREG-1800, Revision 2.
Reference 3.3.13 contains the set of site specific aging management programs credited for license renewal.
- Column 7 - Comments This column is used to identify AMR line items that were added or altered during the NRC review process, but prior to issuance of the renewed operating license. Subsequent to issuance of the renewed operating license, this column is used to identify "newly identified" SSC AMR items and provides reference to the engineering, licensing, or material replacement process which resulted in a "newly identified" conclusion. This column may also be used to provide clarifying or amplifying information to aid in understanding the aging management review issues encompassed by the line item.
Component functions, materials, environments, aging effects, and aging management programs are specifically defined for each site and used in the LRA. Reference 3.3.9 contains the site specific lists for these parameters, except for aging management programs that are listed in Reference 3.3.13. AMR line items included within this Aging Management Review Summary are historical. As such, this Aging Management Review Summary will be updated only when new AMR line items are required. Removal of line items when SSCs are removed from the scope of license renewal is not required. Use: For all "New LR Scope" SSCs that are addressed by an LRA System within the scope of license renewal, the SSC is compared against the AMR Results tables contained in Sections 2.1 through 2.6 to determine if an applicable AMR line item already exists. An applicable AMR line item exists if the component type and material/environment combination(s) are shown in the appropriate LRA System AMR Results Table. If an applicable AMR line item exists, then the SSC is NOT "newly identified." If a Page 1-4
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SHEET 7 of 363 new AMR line item must be added to the AMR Results table to address the SSC component type/material/environment combination, then the SCC is "newly identified." Caution: When using the Plant Hatch AMR Results Tables, the user should understand that component type/material/environment combinations having no aging effects are only listed when there were no aging effects for the other environments associated with the component type. For example, stainless steel piping exposed to reactor water and the inside environment will only display the reactor water environment and associated aging effects in the AMR Results Tables, since the AMRs prepared as a part of the original IPA process concluded no aging effects for stainless steels in the inside environment. The user should consider this structure when conducting comparisons of New LR Scope SSCs against the AMR Tables. When necessary, refer to the AMRs originally prepared as a part of the Plant Hatch process. Page 1-5
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SHEET 8 of 363 1.4 Development Methodology Data contained in this Aging Management Review Summary includes a list of systems within the scope of license renewal, LRA System descriptions, and an AMR Results Table for each LRA System that is determined to be within the scope of license renewal. The LRA System description information is taken from the LRA, as amended during the NRC review process. These descriptions are based primarily upon FSAR descriptions, with additional information added as needed to address license renewal scope issues. The AMR Results Tables are adapted from the LRA as amended during the NRC review process. Comment items are provided to identify the licensing correspondence, design change, or material change which required the addition of, or change to, the line item. Effort has been made to incorporate the same level of detail into this Aging Management Review Summary that was originally required for NRC acceptance in the Safety Evaluation Report regarding E.I. Hatch License Renewal. Page 1-6
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SHEET 9 of 363 2 TECHNICAL INFORMATION 2.0 Systems and Structures Within the Scope of License Renewal Technical information is provided in the following sections to identify and describe the LRA Systems included within the scope of license renewal, identify those HNP systems specifically excluded from the scope license renewal, and to identify completed AMRs for each HNP LRA System within the scope of license renewal. Tables 2.0-1a through 2.0-1f below list the HNP systems and structures which are included within the scope of license renewal and for which AMRs have been performed. These Tables consist of 2 columns:
- LRA System Column 1 provides the LRA System name. SNC chose to identify HNP systems for license renewal at a high level consistent with an FSAR level discussion.
- Desc. & AMR Column 2 provides a reference to the ARM Summary section containing a system description and the AMR Results for each LRA System.
Table 2.0-1a Systems and Structures within the Scope of License Renewal - Reactor, Nuclear Boiler, and Reactor Recirculation Systems Description & AMR LRA System Results Reactor Assembly System [B11] 2.1.1 Includes: Reactor Pressure Vessel Reactor Internals Nuclear Boiler System [B21] 2.1.2 Reactor Recirculation System [B31] 2.1.3 2.0-1
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 10 of 363 Table 2.0-1b Systems and Structures within the Scope of License Renewal - Engineered Safety Features Description & AMR LRA System Results Standby Liquid Control System [C41] 2.2.1 Residual Heat Removal System [E11] 2.2.2 Core Spray System [E21] 2.2.3 High Pressure Coolant Injection System [E41] 2.2.4 Reactor Core Isolation Cooling System [E51] 2.2.5 Standby Gas Treatment System [T46] 2.2.6 Primary Containment Purge and Inerting Sys. [T48] 2.2.7 Post LOCA Hydrogen Recombining System [T49] 2.2.8 (Unit 2 only) 2.0-2
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 11 of 363 Table 2.0-1c Systems and Structures within the Scope of License Renewal - Auxiliary Systems Description & AMR LRA System Results Control Rod Drive System [C11] 2.3.1 Refueling Equipment System [F15] 2.3.2 Insulation System [L36] 2.3.3 Access Doors System [L48] 2.3.4 Condensate Transfer and Storage System [P11] 2.3.5 Sampling System [P33] 2.3.6 Plant Service Water System [P41] 2.3.7 Reactor Building Closed Cooling Water System [P42] 2.3.8 Instrument Air System Section [P52] 2.3.9 Primary Containment Chilled Water System [P64] 2.3.10 (Unit 2 only) Drywell Pneumatics System [P70] 2.3.11 Emergency Diesel Generators System [R43] 2.3.12 Cranes, Hoists and Elevator System [T31] 2.3.13 Tornado Vents System [T38] 2.3.14 Reactor Building HVAC System [T41] 2.3.15 Traveling Water Screens/Trash Racks System [W33] 2.3.16 Outside Structures HVAC System [X41] 2.3.17 Fire Protection System [X43] 2.3.18 Fuel Oil System [Y52] 2.3.19 Control Building HVAC System [Z41] 2.3.20 2.0-3
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SHEET 12 of 363 Table 2.0-1d Systems and Structures within the Scope of License Renewal - Steam and Power Conversion Systems Description & AMR LRA System Results Electro-Hydraulic Control System [N32] 2.4.1 Main Condenser System [N61] 2.4.2 Table 2.0-1e Systems and Structures within the Scope of License Renewal - Structures and Component Supports Description & AMR LRA System Results Piping Specialties [L35] 2.5.1 Conduits, Raceways, and Trays [R33] 2.5.2 Primary Containment [T23] 2.5.3 Fuel Storage [T24] 2.5.4 Reactor Building [T29] 2.5.5 Drywell Penetrations [T52] 2.5.6 Reactor Building Penetrations [T54] 2.5.7 Turbine Building [U29] 2.5.8 Intake Structure [W35] 2.5.9 Yard Structures [Y29] 2.5.10 Main Stack [Y32] 2.5.11 EDG Building [Y39] 2.5.12 Control Building [Z29] 2.5.13 2.0-4
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 13 of 363 Table 2.0-1f Systems and Structures within the Scope of License Renewal - Electrical Components Description & AMR LRA System Results Analog Transmitter Trip System [A70] 2.6.1(a) Nuclear Steam Supply Shutoff System [A71] 2.6.1(b) Primary Containment Isolation System [C61] 2.6.1(c) Reactor Protection System [C71] 2.6.1(d) Remote Shutdown System [C82] 2.6.1(e) Process Radiation Monitoring System [D11] 2.6.1(f) Heat Trace System [G13] 2.6.1(g) Plant AC Electrical System [R20] 2.6.1(h) DC Electrical System [R42] 2.6.1(i) Plant Communications System [R51] 2.6.1(j) Power Transformers System [S11] 2.6.1(k) Emergency Response Facilities System [X75] 2.6.1(l) Electrical Panels, Racks, & Cabinets [H11] 2.6.2 Instruments Racks, Panels, & Enclosures [H21] 2.6.3 2.0-5
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SHEET 14 of 363 2.1 REACTOR, NUCLEAR BOILER, AND REACTOR RECIRCULATION SYSTEMS The Reactor Assembly System, Nuclear Boiler System, and Reactor Recirculation Systems are addressed in the following Aging Management Summary sections:
- Reactor Assembly System, Section 2.1.1
- Nuclear Boiler System, Section 2.1.2
- Reactor Recirculation System, Section 2.1.3 2.1.1 Reactor Assembly System [B11]
System Description
The reactor vessel has three major purposes:
- Contain core, internals and moderator.
- Serve as a high integrity barrier against leakage.
- Provide a floodable volume.
The reactor assembly consists of the reactor pressure vessel (RPV) and its internal components of the core, shroud, steam separator and dryer assemblies, and jet pumps. Also included in the reactor assembly are the control rods, control rod drive (CRD) housings, and the CRD. The RPV is a vertical, cylindrical pressure vessel with hemispherical heads of welded construction. The major reactor internal components are the core (fuel, channels, control blades, and instrumentation), the core support structure (including the core shroud, shroud head, separators, top guide, and core support), the steam dryer assembly, and the jet pumps. The reactor internal structural elements are stainless steel or other corrosion-resistant alloys. The reactor vessel is located inside the primary containment building. The internal environment of the RPV is reactor water, normally at 533 °F and 1055 psia during plant operation. Water quality is maintained within the specified limits. During plant conditions that require the operation of the shutdown cooling mode of RHR, reactor water can be cooled to approximately 117 °F via the RHR heat exchangers and recirculated back to the reactor through the residual recirculating system (RRS) piping. During plant shutdown conditions, the water temperature in the RPV can be as low as 70°F. 2.1-1
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 15 of 363 Table 2.1-1 Reactor Assembly System [B11] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Program Comments Appurtenances Pressure Reactor Water Nickel Based Cracking Boiling Water Reactor Vessel Deleted Reactor Pressure Boundary Alloy and Internals Program Vessel Monitoring Program. Inspections are contained as a Fission Stainless Steel Reactor Water Chemistry part of the Boiling Water Product Control Reactor Vessel and Internals Barrier Program as described in Component Cyclic or Transient Chapter 18 of the FSAR. No Structural Limit Program changes to program criteria Support result. Attachments Pressure Reactor Water Carbon Steel Cracking Boiling Water Reactor Vessel Deleted Reactor Pressure and Boundary and Internals Program Vessel Monitoring Program. Connecting Low Alloy Inspections are contained as a Welds Fission Steel Reactor Water Chemistry part of the Boiling Water Product Control Reactor Vessel and Internals Barrier Nickel Based Program as described in Alloy Component Cyclic or Transient Chapter 18 of the FSAR. No Structural Limit Program changes to program criteria Support Stainless Steel result. Closure Studs Pressure Reactor Water Low Alloy Cracking Boiling Water Reactor Vessel Deleted Reactor Pressure Boundary Steel and Internals Program Vessel Monitoring Program. Inspections are contained as a Fission Component Cyclic or Transient part of the Boiling Water Product Limit Program Reactor Vessel and Internals Barrier Program as described in Chapter 18 of the FSAR. No changes to program criteria result. Control Rod Pressure Reactor Water Stainless Steel Cracking Inservice Inspection Program Drive Boundary Reactor Water Chemistry Structural Control Support 2.1-1
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SHEET 16 of 363 Table 2.1-1 Reactor Assembly System [B11] - Aging Management Review Results Core Spray Pressure Reactor Water Stainless Steel Cracking Boiling Water Reactor Vessel Internal Boundary and Internals Program Piping Inservice Inspection Program Reactor Water Chemistry Control Core Spray Pressure Reactor Water Stainless Steel Cracking Boiling Water Reactor Vessel Sparger Boundary and Internals Program Flow Inservice Inspection Program Distribution Reactor Water Chemistry Control CRD Housing Structural Reactor Water Stainless Steel Cracking Boiling Water Reactor Vessel and CR Support and Internals Program Guide Tubes Inservice Inspection Program Reactor Water Chemistry Control Dry Tube Pressure Reactor Water Stainless Steel Cracking Inservice Inspection Program Weld to Guide Boundary Tube Reactor Water Chemistry Control Jet Pump Pressure Reactor Water Stainless Steel Cracking Boiling Water Reactor Vessel Assemblies Boundary and Internals Program Cast Structural Austenitic Inservice Inspection Program Support Stainless Steel Reactor Water Chemistry Control 2.1-2
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SHEET 17 of 363 Table 2.1-1 Reactor Assembly System [B11] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Program Comments Nozzles Pressure Reactor Water Low Alloy Cracking Boiling Water Reactor Vessel Replaced the Reactor Boundary Steel and Internals Program Pressure Vessel Monitoring Program with the Boiling Water Fission Reactor Water Chemistry Reactor Vessel and Internals Product Control Program as described in Barrier Chapter 18 of the FSAR. No Component Cyclic or Transient changes to program criteria Structural Limit Program result. Support Penetrations Pressure Reactor Water Nickel Based Cracking Boiling Water Reactor Vessel Replaced the Reactor Boundary Alloy and Internals Program Pressure Vessel Monitoring Program with the Boiling Water Fission Stainless Steel Reactor Water Chemistry Reactor Vessel and Internals Product Control Program as described in Barrier Chapter 18 of the FSAR. No changes to program criteria Structural result. Support Safe Ends Pressure Reactor Water Stainless Steel Cracking Boiling Water Reactor Vessel Replaced the Reactor Boundary and Internals Program Pressure Vessel Monitoring Low Alloy Program with the Boiling Water Fission Steel Reactor Water Chemistry Reactor Vessel and Internals Product Control Program as described in Barrier Carbon Steel Chapter 18 of the FSAR. No Component Cyclic or Transient changes to program criteria Structural Nickel Based Limit Program result. Support Alloy 2.1-3
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SHEET 18 of 363 Table 2.1-1 Reactor Assembly System [B11] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Program Comments Shell and Pressure Reactor Water Low Alloy Loss of Reactor Pressure Vessel Replaced the Reactor Closure Boundary Steel Fracture Material Surveillance Program Pressure Vessel Monitoring Heads Toughness Program with the Reactor Fission Component Cyclic or Transient Pressure Vessel Material Product Limit Program Surveillance Program as Barrier described in Chapter 18 of the FSAR. No changes to Structural program criteria result. Support Shroud Pressure Reactor Water Stainless Steel Cracking Boiling Water Reactor Vessel Boundary and Internals Program Structural Inservice Inspection Program Support Reactor Water Chemistry Control Shroud Pressure Reactor Water Stainless Steel Cracking Boiling Water Reactor Vessel Supports Boundary and Internals Program Nickel Based Structural Alloy Inservice Inspection Program Support Low Alloy Reactor Water Chemistry Steel Control Steam Dryer Physical Reactor Water Stainless Steel Cracking Boiling Water Reactor Vessel This item is conservatively Assembly Integrity and Internals Program added in response to OE following receipt of the renewed operating license. See letter NL-05-1298. 2.1-4
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 19 of 363 Table 2.1-1 Reactor Assembly System [B11] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Program Comments Thermal Pressure Reactor Water Stainless Steel Cracking Boiling Water Reactor Vessel Replaced the Reactor Sleeves Boundary and Internals Program Pressure Vessel Monitoring Nickel Based Program with the Boiling Water Fission Alloy Reactor Water Chemistry Reactor Vessel and Internals Product Control Program as described in Barrier Chapter 18 of the FSAR. No Component Cyclic or Transient changes to program criteria Limit Program result. Top Guide Structural Reactor Water Stainless Steel Cracking Boiling Water Reactor Vessel Support and Internals Program Inservice Inspection Program Reactor Water Chemistry Control 2.1-5
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 20 of 363 2.1.2 Nuclear Boiler System [B21]
System Description
The nuclear boiler system is composed of several components and subsystems that are required to generate steam. Functions provided by the nuclear boiler system include supplying feedwater to the reactor, conducting steam from the reactor, reactor overpressure protection, and some reactor control and/or engineered safety feature functions. The nuclear boiler system is in operation any time the plant is in operation. Most of the major components in the system are part of the reactor coolant pressure boundary. The system contains the following major components:
- Main steam lines (MSLs).
- Safety relief valves (SRVs).
- Main steam isolation valves (MSIVs).
- Feedwater lines.
- Feedwater line check valves.
- Instrumentation and controls.
2.1-6
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 21 of 363 Table 2.1-2 Nuclear Boiler System [B21] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Bolting Pressure Inside Carbon Steel Loss of Torque Activities (Class 1) Boundary Preload Inservice Inspection Program Fission Product Barrier Bolting Pressure Inside Carbon Steel Loss of Torque Activities (non-Class 1) Boundary Preload Protective Coatings Program Fission Loss of Product Material Barrier Crack Growth Pressure Reactor Water Stainless Steel Loss of Reactor Water Chemistry Monitor Boundary Material Control (Class 1) Fission Cracking Inservice Inspection Program Product Barrier Component Cyclic or Transient Limit Program Treated Water Systems Piping Inspections 2.1-7
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 22 of 363 Table 2.1-2 Nuclear Boiler System [B21] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Flow Nozzle Pressure Reactor Water Carbon Steel Loss of Reactor Water Chemistry (Class 1) Boundary Material Control Fission Cracking Inservice Inspection Program Product Barrier Galvanic Susceptibility Inspections Component Cyclic or Transient Limit Program Flow Accelerated Corrosion Program Treated Water Systems Piping Inspections Main Steam Pressure Reactor Water Carbon Steel Loss of Reactor Water Chemistry This line item was added in Flow Boundary Material Control response to RAI 2.3.2 -NBS-Restrictor - 2, SNC correspondence HL-Pipe Fission Cracking Inservice Inspection Program 5979, dated August 29, 2000. (Class 1) Product Barrier Galvanic Susceptibility Inspections Component Cyclic or Transient Limit Program Flow Accelerated Corrosion Program Treated Water Systems Piping Inspections 2.1-8
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 23 of 363 Table 2.1-2 Nuclear Boiler System [B21] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Main Steam Flow Reactor Water Cast Loss of Reactor Water Chemistry This line item was added in Flow Restriction Austenitic Material Control response to RAI 2.3.2 -NBS-Restrictor - Stainless Steel 2, SNC correspondence HL-Venturi Cracking Component Cyclic or Transient 5979, dated August 29, 2000. Limit Program Piping Pressure Reactor Water Carbon Steel Loss of Reactor Water Chemistry Flow Accelerated Corrosion (non-Class 1) Boundary Material Control Program was removed in response to email from R.D. Fission Cracking Galvanic Susceptibility Baker to W.F. Burton, dated Product Inspections April 21, 2000. Barrier Treated Water Systems Piping Inspections Piping Pressure Reactor Water Stainless Steel Loss of Reactor Water Chemistry (non-Class 1) Boundary Material Control Fission Cracking Treated Water Systems Piping Product Inspections Barrier Piping Pressure Demin Water Stainless Steel Loss of Demineralized Water and (non-Class 1) Boundary Material Condensate Storage Tank Chemistry Control Fission Cracking Product Treated Water Systems Piping Barrier Inspections 2.1-9
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 24 of 363 Table 2.1-2 Nuclear Boiler System [B21] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Piping Pressure Torus Water Stainless Steel Loss of Suppression Pool Chemistry Removed line item for Piping (non-Class 1) Boundary Material Control (non-class 1) - Torus Water - Carbon Steel in response to Fission Cracking Torus Submerged email from R.D. Baker to W.F. Product Components Burton, dated April 21, 2000. Barrier Inspection Program Piping Pressure Reactor Water Carbon Steel Loss of Reactor Water Chemistry (Class 1) Boundary Material Control Fission Cracking Inservice Inspection Program Product Barrier Galvanic Susceptibility Inspections Component Cyclic or Transient Limit Program Flow Accelerated Corrosion Program Treated Water Systems Piping Inspections Piping Pressure Reactor Water Stainless Steel Loss of Reactor Water Chemistry (Class 1) Boundary Material Control Fission Cracking Inservice Inspection Program Product Barrier Component Cyclic or Transient Limit Program Treated Water Systems Piping Inspections 2.1-10
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 25 of 363 Table 2.1-2 Nuclear Boiler System [B21] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Piping Pressure Wetted Gas Carbon Steel Loss of Gas Systems Component Inservice Inspection Program (non-Class 1) Boundary Material Inspections was removed in response to email from R.D. Baker to W.F. Fission Cracking Passive Component Inspection Burton, dated April 21, 2000. Product Activities Barrier Changed Piping to (non-Class 1). June 20, 2000 email from R.D. Baker to W.F. Burton. Restricting Pressure Reactor Water Stainless Steel Loss of Reactor Water Chemistry Orifice Boundary Material Control (Class 1) Fission Cracking Component Cyclic or Transient Product Limit Program Barrier Inservice Inspection Program Treated Water Systems Piping Inspections Thermowell Pressure Wetted Gas Carbon Steel Loss of Gas Systems Component (non-Class 1) Boundary Material Inspections Fission Cracking Passive Component Inspection Product Activities Barrier 2.1-11
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 26 of 363 Table 2.1-2 Nuclear Boiler System [B21] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Thermowell Pressure Reactor Water Stainless Steel Loss of Reactor Water Chemistry (Class 1) Boundary Material Control Fission Cracking Inservice Inspection Program Product Barrier Component Cyclic or Transient Limit Program Treated Water Systems Piping Inspections Valve Bodies Pressure Reactor Water Carbon Steel Loss of Reactor Water Chemistry Flow Accelerated Corrosion (non-Class 1) Boundary Material Control Program was removed in response to email from R.D. Fission Cracking Galvanic Susceptibility Baker to W.F. Burton, dated Product Inspections April 21, 2000. Barrier Treated Water Systems Piping Inspections Valve Bodies Pressure Reactor Water Stainless Steel Loss of Reactor Water Chemistry (non-Class 1) Boundary Material Control Fission Cracking Treated Water Systems Piping Product Inspections Barrier Valve Bodies Pressure Wetted Gas Carbon Steel Loss of Gas Systems Component (non-Class 1) Boundary Material Inspections Fission Cracking Inservice Inspection Program Product Barrier Passive Component Inspection Activities 2.1-12
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 27 of 363 Table 2.1-2 Nuclear Boiler System [B21] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Valve Bodies Pressure Reactor Water Carbon Steel Loss of Reactor Water Chemistry (Class 1) Boundary Material Control Fission Cracking Inservice Inspection Program Product Barrier Galvanic Susceptibility Inspections Component Cyclic or Transient Limit Program Flow Accelerated Corrosion Program Treated Water Systems Piping Inspections Valve Bodies Pressure Reactor Water Stainless Steel Loss of Reactor Water Chemistry (Class 1) Boundary Material Control Fission Cracking Inservice Inspection Program Product Barrier Component Cyclic or Transient Limit Program Treated Water Systems Piping Inspections 2.1-13
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 28 of 363 Table 2.1-2 Nuclear Boiler System [B21] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Valve Bodies Pressure Reactor Water Cast Loss of Reactor Water Chemistry (Class 1) Boundary Austenitic Material Control Stainless Steel Fission Cracking Inservice Inspection Program Product Barrier Loss of Component Cyclic or Transient Fracture Limit Program Toughness Valve Bodies Pressure Wetted Gas Stainless Steel Loss of Gas Systems Component (non-Class 1) Boundary Material Inspections Fission Cracking Passive Component Inspection Product Activities Barrier Valve Bodies Pressure Demin Water Stainless Steel Loss of Demineralized Water and (non-Class 1) Boundary Material Condensate Storage Tank Chemistry Control Fission Cracking Product Treated Water Systems Piping Barrier Inspections Component Pressure Inside Carbon Steel Loss of Protective Coatings Program FSAR 18.3.3, Protective External Boundary Material Coatings Program Surfaces (< 200 °F) Fission HL-6002, Sect. VI. B.2.3, Product Protective Coatings Program. Barrier NUREG 1803, Sect. 3.1.20, Protective Coatings Program 2.1-14
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 29 of 363 2.1.3 Reactor Recirculation System [B31]
System Description
The reactor recirculation system (RRS) is one of two core reactivity control systems. The RRS system is part of the reactor coolant pressure boundary. Therefore, it also functions to maintain the pressure boundary during normal operation, transients, and accident scenarios to prevent the release of radioactive liquid and gas. RRS consists of two parallel loops, each consisting of a recirculation pump, suction and discharge block valves, piping, fittings, flow elements and connections supporting flow, and differential pressure instrumentation. The RRS interfaces with the residual heat removal (RHR) and reactor water cleanup (RWCU) systems to provide a flow-path in support of shutdown cooling, low pressure coolant injection (LPCI), RWCU, and reactor water level control functions. HNP FSAR References More information about this system may be found in Unit 1 FSAR Section 4.3 and Unit 2 FSAR subsection 5.5.1. 2.1-15
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 30 of 363 Table 2.1-3 Reactor Recirculation System [B31] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Bolting Fission Containment Carbon Steel Loss of Inservice Inspection Program (Class 1) Product Atmosphere Preload Torque Activities Barrier Loss of Pressure Material Boundary Cracking Flow Nozzle Fission Reactor Water Stainless Steel Loss of Reactor Water Chemistry (Class 1) Product Material Control Barrier Cracking Inservice Inspection Program Pressure Boundary Component Cyclic or Transient Limit Program Piping Fission Reactor Water Stainless Steel Loss of Reactor Water Chemistry (Class 1) Product Material Control Barrier Cracking Inservice Inspection Program Pressure Boundary Component Cyclic or Transient Limit Program Treated Water Systems Piping Inspections Pump Casings Fission Reactor Water Cast Loss of Reactor Water Chemistry and Product Austenitic Material Control Cover Barrier Stainless Steel (Class 1) Cracking Inservice Inspection Program Pressure Boundary Loss of Component Cyclic or Transient Fracture Limit Program Toughness 2.1-16
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 31 of 363 Table 2.1-3 Reactor Recirculation System [B31] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Thermowell Fission Reactor Water Stainless Steel Loss of Reactor Water Chemistry (Class 1) Product Material Control Barrier Cracking Inservice Inspection Program Pressure Boundary Component Cyclic or Transient Limit Program Treated Water Systems Piping Inspections Valve Bodies Fission Reactor Water Cast Loss of Reactor Water Chemistry (Class 1) Product Austenitic Material Control Barrier Stainless Steel Cracking Inservice Inspection Program Pressure Boundary Loss of Component Cyclic or Transient Fracture Limit Program Toughness Valve Bodies Fission Reactor Water Stainless Steel Loss of Reactor Water Chemistry (Class 1) Product Material Control Barrier Cracking Inservice Inspection Program Pressure Boundary Component Cyclic or Transient Limit Program Treated Water Systems Piping Inspections 2.1-17
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 32 of 363 2.2 Engineered Safety Features The Reactor Assembly System, Nuclear Boiler System, and Reactor Circulation Systems are addressed in the following sections:
- Standby Liquid Control System, Section 2.2.1
- Residual Heat Removal System, Section 2.2.2
- Core Spray System, Section 2.2.3
- High Pressure Coolant Injection System, Section 2.2.4
- Reactor Core Isolation Cooling System, Section 2.2.5
- Standby Gas Treatment System, Section 2.2.6
- Primary Containment Purge and Inerting System, Section 2.2.7
- Post LOCA Hydrogen Recombining System, Section 2.2.8 2.2.1 Standby Liquid Control System [C41]
System Description
The standby liquid control system assures reactor shutdown, from full power operation to cold subcritical, by mixing a neutron absorber with the primary reactor coolant. The system is designed for the condition when an insufficient number of control rods can be inserted from the full power setting. The neutron absorber is injected within the core zone in sufficient quantity to provide a sufficient margin for leakage or imperfect mixing. The system is not a scram or a backup scram system for the reactor; it is an independent backup system for the control rod drive (CRD) system. HNP FSAR References More information can be found on this system in Unit 2 FSAR subsection 4.2.3. 2.2-1
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 33 of 363 Table 2.2-1 Standby Liquid Control System [C41] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Bolting Pressure Inside Stainless Steel Loss of Torque Activities Boundary Preload Piping Pressure Borated Water Stainless Steel Loss of Demineralized Water and Boundary Material Condensate Storage Tank Chemistry Control Cracking Treated Water Systems Piping Inspections Pump Pressure Borated Water Carbon Steel Loss of Demineralized Water and Accumulators Boundary Material Condensate Storage Tank Chemistry Control Cracking Protective Coatings Program Pump Casing Pressure Borated Water Stainless Steel Loss of Demineralized Water and Boundary Material Condensate Storage Tank Cracking Chemistry Control Treated Water Systems Piping Inspections Tanks Pressure Borated Water Stainless Steel Loss of Demineralized Water and Boundary Material Condensate Storage Tank Chemistry Control Cracking Treated Water Systems Piping Inspections Thermowell Pressure Borated Water Stainless Steel Loss of Demineralized Water and Boundary Material Condensate Storage Tank Chemistry Control Cracking Treated Water Systems Piping Inspections 2.2-2
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 34 of 363 Table 2.2-1 Standby Liquid Control System [C41] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Valve Bodies Pressure Borated Water Stainless Steel Loss of Demineralized Water and Boundary Material Condensate Storage Tank Chemistry Control Cracking Treated Water Systems Piping Inspections Component Pressure Inside Carbon Steel Loss of Protective Coatings Program FSAR 18.3.3, Protective External Boundary Material Coatings Program Surfaces (< 200 °F) HL-6002, Sect. VI. B.2.3, Protective Coatings Program. NUREG 1803, Sect. 3.1.20, Protective Coatings Program & Sect. 3.3.2.1. Insulation Protect and Inside Various Loss of Equipment and Piping FSAR 18.3.4, Equipment and Insulate Insulating Material Insulation Monitoring Program Piping Insulation Program Components Materials Cracking HL-6002, Sect. VI. B.2.4, Equipment and Piping Change in Insulation Monitoring Program. Material Properties NUREG 1803, Sect. 3.1.21, Equipment and Piping Insulation Monitoring Program 2.2-3
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 35 of 363 2.2.2 Residual Heat Removal System [E11]
System Description
The residual heat removal (RHR) system is composed of several components and subsystems which are required to: Restore and maintain reactor vessel water level after a loss of coolant accident (LOCA); Limit temperature and pressure inside the containment after a LOCA; Remove heat from the suppression pool water; and Remove decay and residual heat from the reactor core to achieve and maintain a cold shutdown condition ; and Remove airborne particulates from the containment atmosphere after a LOCA. Note that the RHR service water functions are included in E11. The RHR system consists of four pumps and two heat exchangers divided into two loops of two pumps and one heat exchanger each, plus the associated instruments, valves, and piping. The RHR pumps take suction from the suppression pool or the reactor coolant recirculation loop. The pumps discharge into the recirculation loop, the suppression pool, the containment spray headers, the spent-fuel pool cooling and cleanup system, depending upon the desired mode of system operation. The RHR system interfaces with the recirculation system to provide a flow-path in support of shutdown cooling and low pressure coolant injection (LPCI). The RHR system is part of the reactor coolant pressure boundary; therefore, it also maintains the pressure boundary during normal operation, transients, and accident scenarios to prevent the release of radioactive liquid and gas. The RHR system is cooled through the heat exchangers by the residual heat removal service water (RHRSW) system. The RHRSW takes suction from the Altamaha River. There are four RHRSW pumps per unit. The RHRSW system also serves as a standby coolant supply system by providing a means of injecting makeup water from the river to the RHR system to keep the core covered during an extreme emergency. HNP FSAR References More information about the RHR system may be found in Unit 1 FSAR Section 4.8 and Unit 2 FSAR subsection 5.5.7. 2.2-4
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 36 of 363 Table 2.2-2 Residual Heat Removal System [E11] - Aging Management Review Results Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Comments Bolting Pressure Inside Carbon Steel Loss of Torque Activities Boundary Preload Protective Coatings Program Loss of Material Bolting Pressure Inside Stainless Steel Loss of Torque Activities Boundary Preload Conductivity Pressure Torus Water Stainless Steel Loss of Suppression Pool Chemistry Element Boundary Material Control Fission Cracking Treated Water Systems Piping Product Inspections Barrier Heat Pressure Raw Water Carbon Steel Loss of RHR Heat Exchanger Exchanger Boundary Material Augmented Inspection and Channel Testing Program Assembly Cracking PSW and RHRSW Chemistry Fouling Control Program Loss of Heat Structural Monitoring Program Exchanger Performance 2.2-5
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 37 of 363 Table 2.2-2 Residual Heat Removal System [E11] - Aging Management Review Results Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Comments Heat Shelter/ Torus Water Stainless Steel Loss of RHR Heat Exchanger Exchanger Protection Material Augmented Inspection and Impingement Testing Program Plate Cracking Suppression Pool Chemistry Fouling Control Loss of Heat Exchanger Performance Heat Pressure Torus Water Carbon Steel Loss of RHR Heat Exchanger Exchanger Boundary Material Augmented Inspection and Shell Testing Program Fission Cracking Product Inservice Inspection Program Barrier Fouling Suppression Pool Chemistry Loss of Heat Control Exchanger Performance Heat Pressure Torus Water Carbon Steel Loss of RHR Heat Exchanger Exchanger Boundary Material Augmented Inspection and Tube Testing Program Sheet Fission Cracking Product Suppression Pool Chemistry Barrier Fouling Control Loss of Heat Exchanger Performance 2.2-6
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 38 of 363 Table 2.2-2 Residual Heat Removal System [E11] - Aging Management Review Results Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Comments Heat Pressure Raw Water Stainless Steel Loss of RHR Heat Exchanger Exchanger Boundary Material Augmented Inspection and Tube Clad Carbon Testing Program Sheet Steel Cracking PSW and RHRSW Chemistry Fouling Control Program Loss of Heat Structural Monitoring Program Exchanger Performance Heat Pressure Torus Water Stainless Steel Loss of RHR Heat Exchanger Exchanger Boundary Material Augmented Inspection and Tubes Testing Program Fission Cracking Product Suppression Pool Chemistry Barrier Loss of Heat Control Exchanger Exchange Performance Heat Heat Pressure Raw Water Stainless Steel Loss of RHR Heat Exchanger Exchanger Boundary Material Augmented Inspection and Tubes Testing Program Fission Cracking Product PSW and RHRSW Chemistry Barrier Fouling Control Program Exchange Loss of Heat Structural Monitoring Program Heat Exchanger Performance 2.2-7
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 39 of 363 Table 2.2-2 Residual Heat Removal System [E11] - Aging Management Review Results Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Comments Piping Pressure Torus Water Carbon Steel Loss of Suppression Pool Chemistry Boundary Material Control Fission Cracking Galvanic Susceptibility Product Inspections Barrier Treated Water Systems Piping Inspections Piping Pressure Wetted Gas Carbon Steel Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Passive Component Inspection Product Activities Barrier Piping Pressure Buried Carbon Steel Loss of ISI Program (VT-2) This line item was added in Boundary with Coal Tar Material response to Open Item 3.1.13-Enamel Protective Coatings Program 1 (a), SNC correspondence Coating HL-6092, dated June 5, 2001. Piping Pressure Raw Water Carbon Steel Loss of PSW and RHRSW Inspection Boundary Material Program Flow Blockage PSW and RHRSW Chemistry Control Program Cracking Galvanic Susceptibility Loss of Heat Inspections Exchanger Performance Structural Monitoring Program 2.2-8
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 40 of 363 Table 2.2-2 Residual Heat Removal System [E11] - Aging Management Review Results Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Comments Pump Casings Pressure Torus Water Carbon Steel Loss of Suppression Pool Chemistry Boundary Material Control Fission Cracking Galvanic Susceptibility Product Inspections Barrier Treated Water Systems Piping Inspections Pump Casings Pressure Raw Water Cast Loss of PSW and RHRSW Inspection Cracking was removed as an - Bowl Boundary Austenitic Material Program AERM in response to email Assembly Stainless Steel from R.D. Baker to W.F. Flow Blockage PSW and RHRSW Chemistry Burton dated June 20, 2000. Control Program Loss of Heat Exchanger Structural Monitoring Program Performance Pump Column Pressure Raw Water Carbon Steel Loss of PSW and RHRSW Inspection Cracking was removed as an Discharge Boundary Material Program AERM in response to email Head from R.D. Baker to W.F. Flow Blockage PSW and RHRSW Chemistry Burton dated June 20, 2000. Control Program Galvanic Susceptibility Inspections Structural Monitoring Program Pump Sub Structural Inside Carbon Steel Loss of Protective Coatings Program Base Support Material 2.2-9
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 41 of 363 Table 2.2-2 Residual Heat Removal System [E11] - Aging Management Review Results Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Comments Restricting Pressure Torus Water Stainless Steel Loss of Suppression Pool Chemistry Orifices Boundary Material Control Fission Cracking Treated Water Systems Piping Product Inspection Barrier Restricting Pressure Torus Water Stainless Steel Loss of Suppression Pool Chemistry Orifices Boundary Material Control Fission Cracking Treated Water Systems Piping Product Inspection Barrier Flow Restriction Restricting Pressure Raw Water Stainless Steel Loss of PSW and RHRSW Inspection Orifices Boundary Material Program Flow Flow Blockage PSW and RHRSW Chemistry Restriction Control Program Cracking Structural Monitoring Program Strainer Debris Raw Water Carbon Steel Loss of PSW and RHRSW Inspection Bodies Protection Material Program Flow Blockage PSW and RHRSW Chemistry Control Program Cracking Galvanic Susceptibility Inspections Structural Monitoring Program 2.2-10
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 42 of 363 Table 2.2-2 Residual Heat Removal System [E11] - Aging Management Review Results Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Comments Strainer Debris Raw Water Stainless Steel Loss of PSW and RHRSW Inspection Line item added in response to Basket Protection Material Program email from R.D. Baker to W.F. Burton, dated June 20, 2000. Flow Blockage PSW and RHRSW Chemistry Control Program Structural Monitoring Program Strainers Debris Torus Water Stainless Steel Loss of Suppression Pool Chemistry Protection Material Control Cracking Torus Submerged Components Inspection Program Thermowell Pressure Torus Water Carbon Steel Loss of Suppression Pool Chemistry Boundary Material Control Fission Cracking Treated Water Systems Piping Product Inspections Barrier Tubing Pressure Raw Water Copper Alloy Loss of PSW and RHRSW Inspection Boundary Material Program Flow Blockage PSW and RHRSW Chemistry Control Program Cracking Structural Monitoring Program 2.2-11
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 43 of 363 Table 2.2-2 Residual Heat Removal System [E11] - Aging Management Review Results Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Comments Valve Bodies Pressure Torus Water Carbon Steel Loss of Suppression Pool Chemistry Boundary Material Control Fission Cracking Galvanic Susceptibility Product Inspection Barrier Treated Water Systems Piping Inspection Valve Bodies Pressure Raw Water Carbon Steel Loss of PSW and RHRSW Inspection Boundary Material Program Flow Blockage PSW and RHRSW Chemistry Control Program Cracking Galvanic Susceptibility Inspections Structural Monitoring Program Component Pressure Inside Carbon Steel Loss of Protective Coatings Program FSAR 18.3.3, Protective External Boundary Material Coatings Program Surfaces Outside (< 200 °F) Fission HL-6002, Sect. VI. B.2.3, Product Protective Coatings Program. Barrier NUREG 1803, Sect. 3.1.20, Protective Coatings Program & Sect. 3.3.2.1. 2.2-12
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 44 of 363 Table 2.2-2 Residual Heat Removal System [E11] - Aging Management Review Results Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Comments Insulation Protect and Inside Various Loss of Equipment and Piping FSAR 18.3.4, Equipment and Insulate Insulating Material Insulation Monitoring Program Piping Insulation Program Components Materials Cracking HL-6002, Sect. VI. B.2.4, Equipment and Piping Change in Insulation Monitoring Program. Material Properties NUREG 1803, Sect. 3.1.21, Equipment and Piping Insulation Monitoring Program 2.2-13
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 45 of 363 2.2.3 Core Spray System [E21]
System Description
The core spray (CS) system is one of the emergency core cooling systems (ECCSs) which protects the core from overheating in the event of a loss of coolant accident (LOCA). The CS system is a low pressure system. Actuation of the CS system results from low reactor vessel water level (level 1) or high drywell pressure or manual action. Injection valves to the reactor require a signal from the reactor low pressure permissive switches before opening to provide over-pressure protection to the system. The pumps take suction from the suppression pool and spray on the top of fuel assemblies to cool the core and limit the fuel cladding temperature. An alternate suction source for the CS system, the condensate storage tank (CST), is used primarily for providing reactor pressure vessel (RPV) makeup and an injection test supply during outages, and would not normally be used post accident. The CS system works in conjunction with low pressure coolant injection (LPCI). The CS system has two independent loops. Each loop includes a 100% capacity centrifugal pump driven by an electric motor, a sparger ring in the reactor vessel above the core, piping, valves, and associated controls and instrumentation. HNP FSAR References The Core Spray System is described in Unit 1 FSAR subsection 6.4.3 and Unit 2 FSAR paragraph 6.3.2.2.3. 2.2-14
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 46 of 363 Table 2.2-3 Core Spray System [E21] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Bolting Pressure Inside Carbon Steel Loss of Torque Activities Boundary Preload Protective Coatings Program Loss of Material Bolting Pressure Inside Stainless Steel Loss of Torque Activities Boundary Preload Piping Pressure Torus Water Carbon Steel Loss of Suppression Pool Chemistry Boundary Material Control Fission Cracking Galvanic Susceptibility Product Inspections Barrier Treated Water Systems Piping Inspections Pump Casings Pressure Torus Water Carbon Steel Loss of Suppression Pool Chemistry Boundary Material Control Fission Cracking Treated Water Systems Piping Product Inspection Barrier Restricting Pressure Torus Water Stainless Steel Loss of Suppression Pool Chemistry Orifice Boundary Material Control Fission Cracking Treated Water Systems Piping Product Inspection Barrier Flow Restriction 2.2-15
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 47 of 363 Table 2.2-3 Core Spray System [E21] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Strainers Debris Torus Water Stainless Steel Loss of Suppression Pool Chemistry Protection Material Control Cracking Torus Submerged Components Inspection Program Valve Bodies Pressure Torus Water Carbon Steel Loss of Suppression Pool Chemistry Boundary Material Control Fission Cracking Galvanic Susceptibility Product Inspections Barrier Treated Water Systems Piping Inspection Component Pressure Inside Carbon Steel Loss of Protective Coatings Program FSAR 18.3.3, Protective External Boundary Material Coatings Program Surfaces (< 200 °F) Fission HL-6002, Sect. VI. B.2.3, Product Protective Coatings Program. Barrier NUREG 1803, Sect. 3.1.20, Protective Coatings Program & Sect. 3.3.2.1. Insulation Protect and Inside Various Loss of Equipment and Piping FSAR 18.3.4, Equipment and Insulate Piping Insulating Material Insulation Monitoring Program Piping Insulation Program Materials Cracking HL-6002, Sect. VI. B.2.4, Equipment and Piping Change in Insulation Monitoring Program. Material Properties NUREG 1803, Sect. 3.1.21, Equipment and Piping Insulation Monitoring Program 2.2-16
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 48 of 363 2.2.4 High Pressure Coolant Injection System [E41]
System Description
The high pressure coolant injection (HPCI) system supplies makeup coolant into the reactor vessel from a fully pressurized to a preset depressurized condition. Demineralized makeup water is supplied from the condensate storage tank (CST) or treated water from the suppression pool. The flow rate of the system will maintain the reactor vessel coolant inventory until the reactor pressure drops sufficiently to permit the low pressure core cooling systems to automatically inject coolant into the vessel. The HPCI system consists of a turbine driven pump train, piping, valves, and controls that provide a complete and independent emergency core cooling system (ECCS). A test line permits functional testing of the system during normal plant operation. A minimum flow bypass line bypasses pump discharge flow to the suppression pool to protect the pump in the event of a stoppage in the main discharge line. Reactor vessel steam is supplied to the turbine. Turbine exhaust steam is dumped to the suppression pool. HNP FSAR References The HPCI system is further described in the Unit 1 FSAR subsection 6.4.1 and Unit 2 FSAR paragraph 6.3.2.2.1. 2.2-17
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 49 of 363 Table 2.2-4 High Pressure Coolant Injection System [E41] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Bolting Pressure Inside Carbon Steel Loss of Torque Activities Boundary Preload Protective Coatings Program Fission Loss of Product Material Barrier Bolting Pressure Inside Stainless Steel Loss of Torque Activities Boundary Preload Fission Product Barrier Flexible Pressure Wetted Gas Stainless Steel Loss of Gas Systems Component Environment changed to Connector Boundary Material Inspections Wetted Gas in response to email from R.D. Baker to W.F. Fission Cracking Burton, dated April 21, 2000. Product Barrier Piping Pressure Reactor Water Carbon Steel Loss of Reactor Water Chemistry Treated Water System Piping Boundary Material Control Inspection added in response to RAI 3.3-HPCI-1, SNC Fission Cracking Galvanic Susceptibility correspondence HL-6002 Product Inspections dated October 10, 2000; and in Barrier response to email from R.D. Flow Accelerated Corrosion Baker to W.F. Burton, dated Program April 21, 2000. Treated Water Systems Piping Inspection 2.2-18
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 50 of 363 Table 2.2-4 High Pressure Coolant Injection System [E41] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Piping Pressure Demin Water Carbon Steel Loss of Demineralized Water and Galvanic Susceptibility Boundary Material Condensate Storage Tank Inspections added in response Chemistry Control to RAI 3.3-HPCI-2, SNC Fission Cracking correspondence HL-6002 Product Treated Water Systems Piping dated October 10, 2000. Barrier Inspections Galvanic Susceptibility Inspections Piping Pressure Demin Water Stainless Steel Loss of Demineralized Water and Boundary Material Condensate Storage Tank Chemistry Control Program Fission Cracking Product Treated Water Systems Piping Barrier Inspections Piping Pressure Torus Water Carbon Steel Loss of Suppression Pool Chemistry Torus Submerged Boundary Material Control Components Inspection Program and Protective Fission Cracking Galvanic Susceptibility Coatings Program added in Product Inspections response to email from R.D. Barrier Baker to W.F. Burton, dated Treated Water Systems Piping April 21, 2000 Inspections Torus Submerged Components Inspection Program Protective Coatings Program 2.2-19
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 51 of 363 Table 2.2-4 High Pressure Coolant Injection System [E41] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Piping Pressure Torus Water Stainless Steel Loss of Suppression Pool Chemistry Boundary Material Control Fission Cracking Torus Submerged Product Components Inspection Barrier Program Piping Pressure Wetted Gas Carbon Steel Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Passive Component Inspection Product Activities Barrier Piping Pressure Wetted Gas Stainless Steel Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Product Barrier Piping Pressure Buried Stainless Steel None None Required This line item was added in Boundary response to Open Item 3.1.13-1 (a), SNC correspondence Fission HL-6092, dated June 5, 2001. Product Barrier Piping Pressure Reactor Water Stainless Steel Loss of Reactor Water Chemistry Boundary Material Control Fission Cracking Treated Water Systems Piping Product Inspections Barrier Pump Structural Inside Carbon Steel Loss of Protective Coatings Program Baseplate Support Material 2.2-20
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 52 of 363 Table 2.2-4 High Pressure Coolant Injection System [E41] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Pump Casings Pressure Demin Water Carbon Steel Loss of Demineralized Water and Boundary Material Condensate Storage Tank Chemistry Control Fission Cracking Product Treated Water Systems Piping Barrier Inspections Restricting Pressure Reactor Water Stainless Steel Loss of Reactor Water Chemistry Orifice Boundary Material Control Flow Cracking Treated Water Systems Piping Restriction Inspections Fission Product Barrier Restricting Pressure Demin Water Stainless Steel Loss of Demineralized Water and Cracking added as an AERM Orifice Boundary Material Condensate Storage Tank in response to RAI 3.3-HPCI-5, Chemistry Control Program SNC correspondence HL-6002 Flow Cracking dated October 10, 2000. Restriction Treated Water Systems Piping Inspections Fission Product Barrier 2.2-21
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 53 of 363 Table 2.2-4 High Pressure Coolant Injection System [E41] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Restricting Pressure Wetted Gas Stainless Steel Loss of Gas Systems Component Orifice Boundary Material Inspections Flow Cracking Restriction Fission Product Barrier Suction Debris Torus Water Stainless Steel Loss of Suppression Pool Chemistry Strainer Protection Material Control Cracking Torus Submerged Components Inspection Program Thermowell Pressure Torus Water Stainless Steel Loss of Suppression Pool Chemistry Boundary Material Control Cracking Treated Water Systems Piping Inspections Turbine Pressure Wetted Gas Carbon Steel Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Passive Component Inspection Product Activities Barrier Valve Bodies Pressure Reactor Water Stainless Steel Loss of Reactor Water Chemistry Boundary Material Control Fission Cracking Treated Water Systems Piping Product Inspections Barrier 2.2-22
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 54 of 363 Table 2.2-4 High Pressure Coolant Injection System [E41] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Valve Bodies Pressure Demin Water Carbon Steel Loss of Demineralized Water and Treated Water Systems Piping Boundary Material Condensate Storage Tank Inspections added in response Chemistry Control to RAI 3.3-HPCI-8, SNC Fission Cracking correspondence HL-6002 Product Galvanic Susceptibility dated October 10, 2000. Barrier Inspections Treated Water Systems Piping Inspections Valve Bodies Pressure Demin Water Stainless Steel Loss of Demineralized Water and Boundary Material Condensate Storage Tank Chemistry Control Fission Cracking Product Treated Water Systems Piping Barrier Inspections Valve Bodies Pressure Torus Water Carbon Steel Loss of Suppression Pool Chemistry Boundary Material Control Fission Cracking Galvanic Susceptibility Product Inspections Barrier Treated Water Systems Piping Inspections Valve Bodies Pressure Wetted Gas Carbon Steel Loss of Gas Systems Component Passive Component Inspection Boundary Material Inspections Activities added in response to RAI 3.3-HPCI-9, SNC Fission Cracking Passive Component Inspection correspondence HL-6002 Product Activities dated October 10, 2000. Barrier 2.2-23
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 55 of 363 Table 2.2-4 High Pressure Coolant Injection System [E41] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Valve Bodies Pressure Wetted Gas Stainless Steel Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Product Barrier Valve Bodies Pressure Torus Water Stainless Steel Loss of Suppression Pool Chemistry Boundary Material Control Fission Cracking Treated Water Systems Piping Product Inspections Barrier Component Pressure Inside Carbon Steel Loss of Protective Coatings Program FSAR 18.3.3, Protective External Boundary Material Coatings Program Surfaces Outside (< 200 °F) Fission HL-6002, Sect. VI. B.2.3, Product Protective Coatings Program. Barrier NUREG 1803, Sect. 3.1.20, Protective Coatings Program & Sect. 3.3.2.1. Insulation Protect and Inside Various Loss of Equipment and Piping FSAR 18.3.4, Equipment and Insulate Piping Insulating Material Insulation Monitoring Program Piping Insulation Program Materials Cracking HL-6002, Sect. VI. B.2.4, Equipment and Piping Change in Insulation Monitoring Program. Material Properties NUREG 1803, Sect. 3.1.21, Equipment and Piping Insulation Monitoring Program 2.2-24
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 56 of 363 2.2.5 Reactor Core Isolation Cooling System [E51]
System Description
The reactor core isolation cooling (RCIC) system is a high pressure coolant makeup system which supports reactor shutdown when the feedwater system is unavailable. The RCIC system provides the capability of maintaining the reactor in a hot standby condition for an extended period. Normally, however, the RCIC system is used until the reactor pressure is sufficiently reduced to permit use of the shutdown cooling mode of the residual heat removal (RHR) system. The RCIC system consists of a turbine driven pump, piping and valves, and the instrumentation necessary to maintain the water level in the reactor vessel above the top of the active fuel should the reactor vessel be isolated from normal feedwater flow. HNP FSAR References The system is described in the Unit 1 FSAR, Section 4.7 and Unit 2 FSAR subsection 5.5.6. 2.2-25
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 57 of 363 Table 2.2-5 Reactor Core Isolation Cooling System [E51] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Bolting Pressure Inside Carbon Steel Loss of Torque Activities Boundary Preload Protective Coatings Program Fission Loss of Product Material Barrier Bolting Pressure Inside Stainless Steel Loss of Torque Activities Boundary Preload Fission Product Barrier Flexible Pressure Wetted Gas Carbon Steel Loss of Gas Systems Component Connectors Boundary Material Inspections Fission Cracking Passive Component Inspection Product Activities Barrier Piping Pressure Reactor Water Carbon Steel Loss of Reactor Water Chemistry Boundary Material Control Fission Cracking Galvanic Susceptibility Product Inspections Barrier Flow Accelerated Corrosion Program Treated Water Systems Piping Inspections 2.2-26
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 58 of 363 Table 2.2-5 Reactor Core Isolation Cooling System [E51] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Piping Pressure Demin Water Carbon Steel Loss of Demineralized Water and Boundary Material Condensate Storage Tank Chemistry Control Fission Cracking Product Galvanic Susceptibility Barrier Inspections Treated Water Systems Piping Inspections Piping Pressure Demin Water Stainless Steel Loss of Demineralized Water and Boundary Material Condensate Storage Tank Chemistry Control Fission Cracking Product Treated Water Systems Piping Barrier Inspections Piping Pressure Torus Water Stainless Steel Loss of Suppression Pool Chemistry Boundary Material Control Fission Cracking Torus Submerged Product Components Inspection Barrier Program Piping Pressure Wetted Gas Carbon Steel Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Passive Component Inspection Product Activities Barrier 2.2-27
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 59 of 363 Table 2.2-5 Reactor Core Isolation Cooling System [E51] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Piping Pressure Wetted Gas Stainless Steel Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Product Barrier Piping Pressure Reactor Water Stainless Steel Loss of Reactor Water Chemistry Boundary Material Control Fission Cracking Treated Water Systems Piping Production Inspections Barrier Piping Pressure Torus Water Carbon Steel Loss of Suppression Pool Chemistry Boundary Material Control Fission Cracking Galvanic Susceptibility Production Inspections Barrier Treated Water Systems Piping Inspections Piping Pressure Buried Stainless Steel None None Required This line item was added in Boundary response to Open Item 3.1.13-1 (a), SNC correspondence Fission HL-6092, dated June 5, 2001. Production Barrier Pump Structural Air Carbon Steel Loss of Protective Coatings Program Baseplate Support Material 2.2-28
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 60 of 363 Table 2.2-5 Reactor Core Isolation Cooling System [E51] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Pump Casing Pressure Demin Water Carbon Steel Loss of Demineralized Water and Boundary Material Condensate Storage Tank Chemistry Control Fission Cracking Product Treated Water Systems Piping Barrier Inspections Restricting Pressure Demin Water Stainless Steel Loss of Demineralized Water and Orifices Boundary Material Condensate Storage Tank Chemistry Control Flow Restriction Treated Water Systems Piping Inspections Fission Product Barrier Restricting Pressure Wetted Gas Stainless Steel Loss of Gas Systems Component Orifices Boundary Material Inspections Flow Cracking Restriction Fission Product Barrier Steam Trap Pressure Reactor Water Carbon Steel Loss of Reactor Water Chemistry Boundary Material Control Fission Cracking Treated Water Systems Piping Product Inspections Barrier Flow Accelerated Corrosion Program 2.2-29
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 61 of 363 Table 2.2-5 Reactor Core Isolation Cooling System [E51] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Steam Trap Pressure Wetted Gas Carbon Steel Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Passive Component Inspection Product Activities Barrier Steam Trap Pressure Reactor Water Stainless Steel Loss of Reactor Water Chemistry Boundary Material Control Fission Cracking Treated Water Systems Piping Product Inspections Barrier Steam Trap Pressure Wetted Gas Stainless Steel Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Product Barrier Strainer- Pressure Wetted Gas Carbon Steel Loss of Gas Systems Component Steam Boundary Material Inspections Exhaust Fission Cracking Passive Component Inspection Product Activities Barrier Suction Debris Torus Water Stainless Steel Loss of Suppression Pool Chemistry Strainer Protection Material Control Cracking Torus Submerged Components Inspection Program 2.2-30
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 62 of 363 Table 2.2-5 Reactor Core Isolation Cooling System [E51] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Thermowell Pressure Demin Water Stainless Steel Loss of Demineralized Water and Boundary Material Condensate Storage Tank Chemistry Control Fission Cracking Product Treated Water Systems Piping Barrier Inspections Thermowell Pressure Demin Water Carbon Steel Loss of Demineralized Water and Boundary Material Condensate Storage Tank Chemistry Control Fission Cracking Product Treated Water Systems Piping Barrier Inspections Turbine Pressure Wetted Gas Carbon Steel Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Passive Component Inspection Product Activities Barrier Valve Bodies Pressure Demin Water Carbon Steel Loss of Demineralized Water and Boundary Material Condensate Storage Tank Chemistry Control Fission Cracking Product Galvanic Susceptibility Barrier Inspections Treated Water Systems Piping Inspections 2.2-31
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 63 of 363 Table 2.2-5 Reactor Core Isolation Cooling System [E51] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Valve Bodies Pressure Reactor Water Carbon Steel Loss of Reactor Water Chemistry Boundary Material Control Fission Cracking Flow Accelerated Corrosion Product Program Barrier Galvanic Susceptibility Inspections Treated Water Systems Piping Inspections Valve Bodies Pressure Reactor Water Stainless Steel Loss of Reactor Water Chemistry Boundary Material Control Fission Cracking Treated Water Systems Piping Product Inspections Barrier Valve Bodies Pressure Demin Water Stainless Steel Loss of Demineralized Water and Cracking was added as an Boundary Material Condensate Storage Tank AERM in response to RAI 3.3-Chemistry Control RCIC-7 and RAI 3.3-HPCI-5, Fission Cracking SNC correspondence HL-6002 Product Treated Water Systems Piping dated October 10, 2000. Barrier Inspections 2.2-32
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 64 of 363 Table 2.2-5 Reactor Core Isolation Cooling System [E51] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Valve Bodies Pressure Torus Water Carbon Steel Loss of Suppression Pool Chemistry Boundary Material Control Fission Cracking Galvanic Susceptibility Product Inspections Barrier Treated Water Systems Piping Inspections Valve Bodies Pressure Torus Water Cast Loss of Suppression Pool Chemistry Boundary Austenitic Material Control Stainless Steel Fission Cracking Treated Water Systems Piping Product Inspections Barrier Valve Bodies Pressure Wetted Gas Carbon Steel Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Passive Component Inspection Product Activities Barrier Valve Bodies Pressure Wetted Gas Stainless Steel Loss of Gas Systems Component Passive Component Inspection Boundary Material Inspections Activities was removed in response to email from R.D. Fission Cracking Baker to W.F. Burton, dated Product April 21, 2000. Barrier 2.2-33
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 65 of 363 Table 2.2-5 Reactor Core Isolation Cooling System [E51] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Component Pressure Inside Carbon Steel Loss of Protective Coatings Program FSAR 18.3.3, Protective External Boundary Material Coatings Program Surfaces Outside (< 200 °F) Fission HL-6002, Sect. VI. B.2.3, Product Protective Coatings Program. Barrier NUREG 1803, Sect. 3.1.20, Protective Coatings Program & Sect. 3.3.2.1. 2.2-34
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 66 of 363 2.2.6 Standby Gas Treatment System [T46]
System Description
The standby gas treatment system (SGTS) is an engineered safety feature (ESF) system for ventilation and cleanup of the primary and secondary containment during certain postulated design basis accidents (DBAs), and meets the design, quality assurance, redundancy, energy source, and instrumentation requirements for ESF systems. The SGTS is also used as a normal means of venting the drywell. The major components of the SGTS include redundant filter trains, control valves, backdraft dampers, fans, and control instrumentation. Each of the filtration assemblies and their respective components are designed for 100-percent-capacity operation. HNP FSAR References Additional information may be found for this system in Unit 1 FSAR paragraph 5.3.3.3 and Unit 2 FSAR subsection 6.2.3. 2.2-35
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 67 of 363 Table 2.2-6 Standby Gas Treatment System [T46] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Damper Pressure Air Carbon Steel Loss of Gas Systems Component This line item is added in (frame only) Boundary Material Inspections response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC Fission Cracking Passive Component Inspection correspondence HL-6092, Product Activities dated June 5, 2001. Barrier Fan Housing Pressure Air Carbon Steel Loss of Gas Systems Component This line item is added in Boundary Material Inspections response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC Fission Cracking Passive Component Inspection correspondence HL-6092, Product Activities dated June 5, 2001. Barrier Filter Housing Pressure Air Galvanized Cracking None Required Boundary Steel Fission Product Barrier Piping Pressure Air Carbon Steel Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Passive Component Inspection Product Activities Barrier Piping Pressure Air Stainless Steel Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Product Barrier 2.2-36
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 68 of 363 Table 2.2-6 Standby Gas Treatment System [T46] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Piping Pressure Air Copper Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Product Barrier Piping Pressure Air Galvanized Cracking None Required Boundary Steel Fission Product Barrier Piping Pressure Buried Carbon Steel Loss of Protective Coatings Program This line item was added in Boundary with Coal Tar Material response to Open Item 3.1.13-Enamel 1 (a), SNC correspondence Fission Coating HL-6092, dated June 5, 2001. Product Barrier Rupture Disc Pressure Air Stainless Steel Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Product Barrier Thermowell Pressure Air Stainless Steel Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Product Barrier 2.2-37
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 69 of 363 Table 2.2-6 Standby Gas Treatment System [T46] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Valve Bodies Pressure Air Carbon Steel Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Passive Component Inspection Product Activities Barrier Valve Bodies Pressure Air Gray Cast Iron Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Passive Component Inspection Product Activities Barrier Valve Bodies Pressure Air Stainless Steel Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Product Barrier Valve Bodies Pressure Air Copper Alloy Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Product Barrier 2.2-38
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 70 of 363 2.2.7 Primary Containment Purge and Inerting System [T48]
System Description
The primary containment purge and inerting system primarily provides and maintains an inert atmosphere in the primary containment for combustible gas control and fire protection. Plant Technical Specifications require that within 24 hours of reactor operation, the inerting system injects a sufficient amount of gaseous nitrogen into the drywell and torus so that the oxygen concentration falls below 4% by volume. Major equipment for the purge and inerting system includes a purge air supply fan, liquid nitrogen storage tank, ambient vaporizer, steam vaporizer, vacuum breaker, valves, piping, controls, and instrumentation. The purge and inerting system provides containment vent paths to the standby gas treatment system which provides a vent path to the main stack for containment vent and purge operations. HNP FSAR References More information may be found in Unit 1 FSAR paragraph 5.2.3.8 and 9 and Unit 2 FSAR Section 6.2. 2.2-39
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 71 of 363 Table 2.2-7 Primary Containment Purge and Inerting System [T48]- Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Bolting Pressure Inside Carbon Steel Loss of Torque Activities Boundary Preload Protective Coatings Program Loss of Material Bolting Pressure Inside Stainless Steel Loss of Torque Activities Boundary Preload Flex Hose Pressure Air Stainless Steel Cracking Gas Systems Component Boundary Inspections Nitrogen Tank Structural Air Carbon Steel Loss of Gas Systems Component Jacket Support Material Inspections Cracking Passive Component Inspection Activities Piping Pressure Torus Water Carbon Steel Loss of Suppression Pool Chemistry Galvanic Susceptibility Boundary Material Control Inspections was removed in response to RAI 3.1.29-5, SNC Cracking Torus Submerged correspondence HL-6002 Components Inspection dated October 10, 2000. Program Protective Coatings Program Protective Coatings Program was added in response to RAI 3.3-P&I-1, SNC correspondence HL-6002 dated October 10, 2000; and in response to email from R.D. Baker to W.F. Burton, dated April 21, 2000. 2.2-40
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 72 of 363 Table 2.2-7 Primary Containment Purge and Inerting System [T48]- Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Piping Pressure Torus Water Stainless Steel Loss of Suppression Pool Chemistry Boundary Material Control Cracking Treated Water Systems Piping Inspections Piping Pressure Dried Gas Stainless Steel Cracking None Required Boundary Piping Pressure Wetted Gas Carbon Steel Loss of Gas Systems Component Boundary Material Inspections Cracking Passive Component Inspection Activities Pressure Pressure Dried Gas Stainless Steel Cracking None Required Buildup Coil Boundary Exchange Heat Rupture Disc Pressure Dried Gas Stainless Steel Cracking None Required Boundary Storage Tank Pressure Dried Gas Stainless Steel Cracking None Required Boundary Thermowell Pressure Inside Stainless Steel Loss of Gas Systems Component Boundary Material Inspections Cracking Valve Bodies Pressure Torus Water Stainless Steel Loss of Suppression Pool Chemistry Boundary Material Control Cracking Treated Water Systems Piping Inspections 2.2-41
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 73 of 363 Table 2.2-7 Primary Containment Purge and Inerting System [T48]- Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Valve Bodies Pressure Dried Gas Carbon Steel Cracking None Required Boundary Valve Bodies Pressure Wetted Gas Carbon Steel Loss of Gas Systems Component Boundary Material Inspections Cracking Passive Component Inspection Activities Vaporizer Pressure Dried Gas Stainless Steel Cracking None Required Boundary Exchange Heat Component Pressure Inside Carbon Steel Loss of Protective Coatings Program FSAR 18.3.3, Protective External Boundary Material Coatings Program Surfaces (< 200 °F) Structural HL-6002, Sect. VI. B.2.3, Support Protective Coatings Program. NUREG 1803, Sect. 3.1.20, Protective Coatings Program & Sect. 3.3.2.1. 2.2-42
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 74 of 363 2.2.8 Post LOCA Hydrogen Recombiners System [T49] (Unit 2 only)
System Description
The post loss of coolant accident (LOCA) hydrogen recombiner system ensures that hydrogen does not accumulate within the primary containment in combustible concentrations following a LOCA. This is accomplished by drawing primary containment atmosphere from the drywell and passing it through the recombiner where the hydrogen reacts with available oxygen to form water vapor. The recombiner discharge is to the suppression pool (torus). The hydrogen recombiner system is part of the combustible gas control system and consists of two independent 100% capacity identical trains. Each train consists of three packages: the recombiner skid, the control console, and the power panel. HNP FSAR References More information can be found about this system in Unit 2 FSAR subsection 6.2.5. 2.2-43
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 75 of 363 Table 2.2-8 Post LOCA Hydrogen Recombiners System [T49] (Unit 2 only) - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Bolting Pressure Inside Carbon Steel Loss of Torque Activities Boundary Preload Protective Coatings Program Fission Loss of Product Material Barrier Blower Casing Pressure Wetted Gas Carbon Steel Loss of Gas Systems Component This line item is added as a Boundary Material Inspections result of Open Item 2.3.3.2-1 (a), SNC correspondence HL-Fission Cracking Passive Component Inspection 6092, dated June 5, 2001. Product Activities Barrier Instrumentation Pressure Wetted Gas Carbon Steel Loss of Gas Systems Component This line item is added as a Boundary Material Inspections result of Open Item 2.3.3.2-1 (a), SNC correspondence HL-Fission Cracking 6092, dated June 5, 2001. Product Barrier Instrumentation Pressure Wetted Gas Stainless Steel Loss of Gas Systems Component This line item is added as a Boundary Material Inspections result of Open Item 2.3.3.2-1 (a), SNC correspondence HL-Fission Cracking 6092, dated June 5, 2001. Product Barrier Piping Pressure Wetted Gas Stainless Steel Loss of Gas Systems Component This line item is added as a Boundary Material Inspections result of Open Item 2.3.3.2-1 (a), SNC correspondence HL-Fission Cracking 6092, dated June 5, 2001. Product Barrier 2.2-44
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 76 of 363 Table 2.2-8 Post LOCA Hydrogen Recombiners System [T49] (Unit 2 only) - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Piping Pressure Wetted Gas Carbon Steel Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Passive Component Inspection Product Activities Barrier Reaction Pressure Wetted Gas Stainless Steel Loss of Gas Systems Component This line item is added as a Chamber Boundary Material Inspections result of Open Item 2.3.3.2-1 (a), SNC correspondence HL-Fission Cracking 6092, dated June 5, 2001. Product Barrier Valve Bodies Pressure Wetted Gas Carbon Steel Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Passive Component Inspection Product Activities Barrier Valve Bodies Pressure Wetted Gas Stainless Steel Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Product Barrier Water Separator Pressure Wetted Gas Carbon Steel Loss of Gas Systems Component This line item is added as a Boundary Material Inspections result of Open Item 2.3.3.2-1 (a), SNC correspondence HL-Fission Cracking Passive Component Inspection 6092, dated June 5, 2001. Product Activities Barrier 2.2-45
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 77 of 363 Table 2.2-8 Post LOCA Hydrogen Recombiners System [T49] (Unit 2 only) - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Water Spray Pressure Wetted Gas Stainless Steel Loss of Gas Systems Component This line item is added as a Cooler Boundary Material Inspections result of Open Item 2.3.3.2-1 (a), SNC correspondence HL-Fission Cracking 6092, dated June 5, 2001. Product Barrier Component Pressure Inside Carbon Steel Loss of Protective Coatings Program FSAR 18.3.3, Protective External Boundary Material Coatings Program Surfaces (< 200 °F) HL-6002, Sect. VI. B.2.3, Protective Coatings Program. NUREG 1803, Sect. 3.1.20, Protective Coatings Program & Sect. 3.3.2.1. 2.2-46
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 78 of 363 2.3 Auxiliary Systems The Auxiliary Systems are addressed in the following sections:
- Control Rod Drive System, Section 2.3.1
- Refueling Equipment System, Section 2.3.2
- Insulation System, Section 2.3.3
- Access Doors System, Section 2.3.4
- Condensate Transfer and Storage System, Section 2.3.5
- Sampling System, Section 2.3.6
- Plant Service Water System, Section 2.3.7
- Reactor Building Closed Cooling Water System, Section 2.3.8
- Instrument Air System Section 2.3.9
- Primary Containment Chilled Water System, Section 2.3.10
- Drywell Pneumatics System, Section 2.3.11
- Emergency Diesel Generators System, Section 2.3.12
- Cranes, Hoists and Elevator System, Section 2.3.13
- Tornado Vents System, Section 2.3.14
- Reactor Building HVAC System, Section 2.3.15
- Traveling Water Screens/Trash Racks System, Section 2.3.16
- Outside Structures HVAC System, Section 2.3.17
- Fire Protection System, Section 2.3.18
- Fuel Oil System, Section 2.3.19
- Control Building HVAC System, Section 2.3.20
- Turbine Building HVAC System, Section 2.3.21 2.3.1 Control Rod Drive (CRD) System [C11]
System Description
The CRD hydraulic system provides pressurized, demineralized water for the cooling and manipulation of the CRD mechanisms. In addition, the CRD system provides purge water for the reactor water cleanup (RWCU) pump and reactor recirculation pump seals. The alternate rod insertion system is a subsystem of the CRD system. It is a backup means of scramming the reactor by venting the scram air header. It is completely independent of the reactor protection system (RPS) and was installed for the purpose of reducing the probability of an anticipated transient without scram (ATWS) event. Water enters the CRD system from the condensate header downstream of the condensate demineralizers (normal suction) or from the condensate storage tank (CST) (alternate suction). The condensate header is the preferred suction source because the water contains less oxygen (deaerated) than water from the CST. HNP FSAR References More information about this system may be found in Unit 2 FSAR subsections 4.1.3 and 4.2.3. 2.3-1
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 79 of 363 Table 2.3-1 Control Rod Drive (CRD) System [C11] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Accumulator Pressure Demin Water Carbon Steel Loss of Demineralized Water and Boundary Material Condensate Storage Tank Chemistry Control Fission Cracking Product Galvanic Susceptibility Barrier Inspections Treated Water Systems Piping Inspections Accumulator Pressure Dried Gas Carbon Steel Cracking None Required Boundary Fission Product Barrier Bolting Pressure Inside Carbon Steel Loss of Torque Activities (Non-Class 1) Boundary Preload Protective Coatings Program Fission Loss of Product Material Barrier Piping Pressure Demin Water Carbon Steel Loss of Demineralized Water and Boundary Material Condensate Storage Tank Chemistry Control Fission Cracking Product Galvanic Susceptibility Barrier Inspections Treated Water Systems Piping Inspections 2.3-2
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 80 of 363 Table 2.3-1 Control Rod Drive (CRD) System [C11] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Piping Pressure Demin Water Stainless Steel Loss of Demineralized Water and Boundary Material Condensate Storage Tank Chemistry Control Fission Cracking Product Treated Water Systems Piping Barrier Inspections Piping Pressure Dried Gas Stainless Steel Cracking None Required Boundary Fission Product Barrier Piping Pressure Wetted Gas Carbon Steel Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Passive Component Inspection Product Activities Barrier Rupture Disc Pressure Dried Gas Stainless Steel Cracking None Required Boundary Fission Product Barrier 2.3-3
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 81 of 363 Table 2.3-1 Control Rod Drive (CRD) System [C11] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Valve Bodies Pressure Demin Water Carbon Steel Loss of Demineralized Water and Boundary Material Condensate Storage Tank Chemistry Control Fission Cracking Product Galvanic Susceptibility Barrier Inspections Treated Water Systems Piping Inspections Valve Bodies Pressure Demin Water Stainless Steel Loss of Demineralized Water and Boundary Material Condensate Storage Tank Chemistry Control Fission Cracking Product Treated Water Systems Piping Barrier Inspections Valve Bodies Pressure Dried Gas Copper Alloy Cracking None Required Boundary Fission Product Barrier Valve Bodies Pressure Wetted Gas Carbon Steel Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Passive Component Inspection Product Activities Barrier 2.3-4
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 82 of 363 Table 2.3-1 Control Rod Drive (CRD) System [C11] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Valve Bodies Pressure Air Copper Alloy Cracking None Required Boundary Fission Product Barrier Component Pressure Inside Carbon Steel Loss of Protective Coatings Program FSAR 18.3.3, Protective External Boundary Material Coatings Program Surfaces (< 200 °F) Fission HL-6002, Sect. VI. B.2.3, Product Protective Coatings Program. Barrier NUREG 1803, Sect. 3.1.20, Protective Coatings Program 2.3-5
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 83 of 363 2.3.2 Refueling Equipment System [F15]
System Description
The refueling platform equipment assembly is used for handling and transporting reactor core internals and service and handling equipment associated with the refueling operation. The refueling platform equipment assembly consists of the refueling platform, fuel grapple, grapple headlight, and the hardware required to assemble these components into a workable unit. The refueling platform is a bridge structure that spans the refueling pool and the reactor well and travels on rails which extend the length of the fuel storage pool and the reactor well. A working platform extends the width of the bridge structure, providing working access to the entire width of the pools and reactor well area. The combination of the bridge movement for the length of the pool and the trolley movement for the width of the pool provides complete access to the open pool and reactor well. The movements of the bridge and trolley are displayed so that positions above known locations, such as the location of in-core fuel assemblies, can be repeatedly reproduced from dials on the trolley cab. The fuel grapple extends downward, below the underside of the refueling platform, into the pool or reactor well. The telescoping grapple is extended or lowered by a fuel hoist. The position of the air-operated grapple is indicated in the control station. HNP FSAR References More information on refueling may be found in Unit 1 FSAR Section 7.6 and Unit 2 FSAR Section 9.1. 2.3-6
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 84 of 363 Table 2.3-2 Refueling Equipment System [F15] - Aging Management Review Results Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Anchors and Structural Inside Carbon steel Loss of Protective Coatings Program Structural Monitoring Program Bolts support Material was added in response to Overhead Crane and email from R.D. Baker to W.F. Nonsafety Refueling Platform Burton, dated April 21, 2000. Related Inspection Structural Support Structural Monitoring Program Miscellaneous Structural Inside Carbon steel Loss of Protective Coatings Program Structural Monitoring Program Steel support Material was added in response to Overhead Crane and email from R.D. Baker to W.F. Nonsafety Refueling Platform Burton, dated April 21, 2000. Related Inspection Structural Support Structural Monitoring Program Rivets Structural Inside Aluminum None None Required Support Structural Structural Inside Carbon steel Loss of Protective Coatings Program Structural Monitoring Program Steel support Material was added in response to Overhead Crane and email from R.D. Baker to W.F. Refueling Platform Burton, dated April 21, 2000. Inspection Structural Monitoring Program 2.3-7
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 85 of 363 2.3.3 Insulation System [L36]
System Description
The purpose of insulation is to help retain heat in the process piping and equipment, to prevent moisture from condensing on cold surfaces, to protect equipment and personnel from high temperatures, to prevent piping from freezing in cold areas of the plant, and to protect heat tracing from damage. Insulation is required in conjunction with heat tracing. Insulation is also credited in heat load calculations for safety related rooms. Failure of this insulation could allow the heat load of the room to exceed the capability of the HVAC system, thus exceeding the design temperature of the room. 2.3-8
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 86 of 363 Table 2.3-3 Insulation System [L36] - Summary of Aging Management Review Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Aluminum Environmental Outside Aluminum Loss of Equipment and Piping Jacket Control Material Insulation Monitoring Program Cracking Insulation Environmental Outside Asbestos Loss of Equipment and Piping Control Material Insulation Monitoring Program Calcium Cracking Silicate Change in Fiberglass Material Properties Insulation Environmental Inside Ceramics Loss of Equipment and Piping Control Material Insulation Monitoring Program Outside Mineral Fiber Cracking Change in Material Properties Insulation Environmental Outside Galvanized Loss of Equipment and Piping Bolting Control Steel Material Insulation Monitoring Program Cracking Insulation Environmental Outside Stainless Steel Loss of Equipment and Piping Bolting Control Material Insulation Monitoring Program Cracking 2.3-9
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 87 of 363 Table 2.3-3 Insulation System [L36] - Summary of Aging Management Review Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Stainless Steel Environmental Inside Stainless Steel Loss of Equipment and Piping Change in Material Jacket Control Material Insulation Monitoring Program Properties was removed in response to RAI 3.4-IN-1, SNC Cracking correspondence HL-6002 dated October 10, 2000. Wire for Environmental Outside Carbon Steel Loss of Equipment and Piping Insulation Control Material Insulation Monitoring Program Cracking 2.3-10
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 88 of 363 2.3.4 Access Doors System [L48]
System Description
The purpose of the secondary containment access doors is to provide access for personnel and equipment. The secondary containment provides, in conjunction with the primary containment and other engineering safeguards, the capability to limit the release to the environs of radioactive materials so that offsite dose from a postulated design basis accident will be below the guideline values of 10 CFR 100. 2.3-11
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 89 of 363 Table 2.3-4 Access Doors System [L48] - Summary of Aging Management Review Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Structural Missile Barrier Inside Carbon Steel Loss of Structural Monitoring Program Steel Material Fission Outside Protective Coatings Program Product Barrier 2.3-12
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 90 of 363 2.3.5 Condensate Transfer and Storage System [P11]
System Description
The condensate transfer and storage system provides the plant system makeup, receives reject flow, and provides condensate for any continuous service needs and intermittent batch-type services. The total stored design quantity is based on the demand requirements during refueling for filling the dryer separator pool and the reactor well. A 500,000 gallon condensate storage tank (CST) supplies the various unit requirements. The system includes two condensate transfer pumps and associated piping and valves. The CST provides the preferred supply to the high pressure coolant injection (H PCI) and reactor core isolation cooling (RCIC) systems. All other suctions are located above suction lines for these systems to provide a 100,000 gallon reserve. HNP FSAR References The condensate transfer and storage system is described in Unit 1 FSAR Section 11.9 and Unit 2 FSAR subsection 9.2.6. 2.3-13
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 91 of 363 Table 2.3-5 Condensate Transfer and Storage System [P11] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Bolting Pressure Outside Stainless Steel Loss of Torque Activities Boundary Preload Piping Pressure Demin Water Stainless Steel Loss of Demineralized Water and Boundary Material Condensate Storage Tank Chemistry Control Cracking Treated Water Systems Piping Inspections Tanks Pressure Demin Water Aluminum Loss of Demineralized Water and Boundary Material Condensate Storage Tank Chemistry Control Condensate Storage Tank Inspection Tanks Pressure Demin Water Galvanized Loss of Demineralized Water and Boundary Steel Material Condensate Storage Tank Chemistry Control Condensate Storage Tank Inspection Tanks Pressure Demin Water Stainless Steel Loss of Demineralized Water and Boundary Material Condensate Storage Tank Chemistry Control Condensate Storage Tank Inspection 2.3-14
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 92 of 363 Table 2.3-5 Condensate Transfer and Storage System [P11] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Valve Bodies Pressure Demin Water Cast Loss of Demineralized Water and Boundary Austenitic Material Condensate Storage Tank Stainless Steel Chemistry Control Cracking Treated Water Systems Piping Inspection Valve Bodies Pressure Demin Water Stainless Steel Loss of Demineralized Water and Boundary Material Condensate Storage Tank Chemistry Control Cracking Treated Water Systems Piping Inspection Insulation Protect and Outside Various Loss of Equipment and Piping FSAR 18.3.4, Equipment and Insulate Piping Insulating Material Insulation Monitoring Program Piping Insulation Program Materials and Jacketing Cracking HL-6002, Sect. VI. B.2.4, Equipment and Piping Change in Insulation Monitoring Program. Material Properties NUREG 1803, Sect. 3.1.21, Equipment and Piping Insulation Monitoring Program 2.3-15
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 93 of 363 2.3.6 Sampling System [P33]
System Description
The purpose of the primary containment hydrogen and oxygen analyzing system is to provide a means of monitoring hydrogen and oxygen in the primary containment (drywell and torus). The primary containment hydrogen and oxygen analyzing system consists of two separate, redundant systems, each capable of analyzing the hydrogen and oxygen content from the drywell or torus. Each analyzer channel is operated in parallel from separate penetrations in the drywell and torus. The sample is drawn through a sample cooler by the sample system inlet pump, then pumped to the hydrogen and oxygen analyzer cells. The sample is then returned to the primary containment by the sample system outlet pump. HNP FSAR References Additional information may be found in Unit 2 FSAR paragraph 6.2.4.3.3.2. 2.3-16
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 94 of 363 Table 2.3-6 Sampling System [P33] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Piping Pressure Wetted Gas Stainless Steel Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Product Barrier Valve Bodies Pressure Wetted Gas Stainless Steel Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Product Barrier 2.3-17
A-47039 ]\ LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 95 of 363 2.3.7 Plant Service Water System [P41]
System Description
The plant service water (PSW) system removes the heat generated by the operation of various systems (both safety related and nonsafety related). The PSW also provides makeup water to the plant circulating water system by supplying screened Altamaha river water to system heat exchangers. After traveling through the heat exchangers, the water is routed to the circulating water flume for use as flume makeup. The heat picked up by the water is rejected to the atmosphere via the plant cooling towers or to the river via the circulating water flume overflow. The PSW system water is also available for fire-fighting, radwaste dilution, and emergency spent fuel pool makeup. The PSW system consists of four main pumps divided into two divisions of two pumps each. Each of the two divisions supplies one redundant train of safety-related equipment. After passing through isolation valves, the two safety-related headers merge into one header supplying nonsafety-related equipment. After servicing the various systems, the service water is discharged to a potential radioactive contaminant release path, and the discharge header is constantly monitored for activity. HNP FSAR References The PSW system is described in the Unit 1 FSAR Section 10.7 and Unit 2 FSAR subsection 9.2.1. 2.3-18
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 96 of 363 Table 2.3-7 Plant Service Water System [P41] - Summary of Aging Management Review Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Bolting Pressure Inside Carbon Steel Loss of Torque Activities Boundary Preload Outside Protective Coatings Program Loss of Material Cooling Coil Pressure Raw Water Copper Alloy Loss of PSW and RHRSW Inspection This line item is added in Tubing Boundary Material Program response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC Flow Blockage PSW and RHRSW Chemistry correspondence HL-6092, Control Program dated June 5, 2001. Cracking Flexible Pressure Raw Water Stainless Steel Loss of PSW and RHRSW Inspection Connector Boundary Material Program Flow Blockage PSW and RHRSW Chemistry Control Program Cracking Structural Monitoring Program Piping Pressure Buried Carbon Steel Loss of ISI Program (VT-2) This line item was added in Boundary with Coal Tar Material response to Open Item 3.1.13-Enamel Protective Coatings Program 1 (a), SNC correspondence Coating HL-6092, dated June 5, 2001. 2.3-19
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 97 of 363 Table 2.3-7 Plant Service Water System [P41] - Summary of Aging Management Review Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Piping Pressure Raw Water Carbon Steel Loss of PSW and RHRSW Inspection Boundary Material Program Flow Blockage PSW and RHRSW Chemistry Control Program Cracking Structural Monitoring Program Galvanic Susceptibility Inspections Piping Pressure Raw Water Stainless Steel Loss of PSW and RHRSW Inspection Boundary Material Program Flow Blockage PSW and RHRSW Chemistry Control Program Cracking Structural Monitoring Program Pump Bowl Pressure Raw Water Cast Loss of PSW and RHRSW Inspection Cracking was removed as an Assembly Boundary Austenitic Material Program AERM in response to email Stainless Steel from R.D. Baker to W.F. Flow Blockage PSW and RHRSW Chemistry Burton, dated June 20, 2000. Control Program Structural Monitoring Program Pump Pressure Raw Water Carbon Steel Loss of PSW and RHRSW Inspection Cracking was removed as an Discharge Boundary Material Program AERM in response to email Column from R.D. Baker to W.F. Flow Blockage PSW and RHRSW Chemistry Burton, dated June 20, 2000. Control Program Structural Monitoring Program 2.3-20
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 98 of 363 Table 2.3-7 Plant Service Water System [P41] - Summary of Aging Management Review Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Pump Pressure Raw Water Carbon Steel Loss of PSW and RHRSW Inspection Cracking was removed as an Discharge Boundary Material Program AERM in response to email Head from R.D. Baker to W.F. Flow Blockage PSW and RHRSW Chemistry Burton, dated June 20, 2000. Control Program Structural Monitoring Program Pump Sub Structural Inside Carbon Steel Loss of Protective Coatings Program Base Support Material Restricting Pressure Raw Water Stainless Steel Loss of PSW and RHRSW Inspection Orifices Boundary Material Program Flow Flow Blockage PSW and RHRSW Chemistry Restriction Control Program Cracking Structural Monitoring Program Sight Glass Pressure Raw Water Carbon Steel Loss of PSW and RHRSW Inspection Body Boundary Material Program Flow Blockage PSW and RHRSW Chemistry Control Program Galvanic Corrosion Structural Monitoring Program Cracking Sight Glass Pressure Raw Water Stainless Steel Loss of PSW and RHRSW Inspection Body Boundary Material Program Flow Blockage PSW and RHRSW Chemistry Control Program Cracking Structural Monitoring Program 2.3-21
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 99 of 363 Table 2.3-7 Plant Service Water System [P41] - Summary of Aging Management Review Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Strainer Pressure Raw Water Carbon Steel Loss of PSW and RHRSW Inspection Boundary Material Program Flow Blockage PSW and RHRSW Chemistry Control Program Cracking Structural Monitoring Program Strainer Pressure Raw Water Gray Cast Iron Loss of PSW and RHRSW Inspection Boundary Material Program Flow Blockage PSW and RHRSW Chemistry Control Program Cracking Structural Monitoring Program Strainer Debris Raw Water Stainless Steel Loss of PSW and RHRSW Inspection Cracking was removed as an Basket Protection Material Program AERM in response to email from R.D. Baker to W.F. Flow Blockage PSW and RHRSW Chemistry Burton, dated June 20, 2000. Control Program Structural Monitoring Program Strainer Debris Raw Water Gray Cast Iron Loss of PSW and RHRSW Inspection Cracking was removed as an Basket Protection Material Program AERM in response to email from R.D. Baker to W.F. Flow Blockage PSW and RHRSW Chemistry Burton, dated June 20, 2000. Control Program Structural Monitoring Program 2.3-22
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 100 of 363 Table 2.3-7 Plant Service Water System [P41] - Summary of Aging Management Review Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Thermowell Pressure Raw Water Carbon Steel Loss of PSW and RHRSW Inspection Structural Monitoring Program Boundary Material Program was added in response to RAI 3.4-PSW-6, SNC Cracking PSW and RHRSW Chemistry correspondence HL-6002 Control Program dated October 10, 2000. Structural Monitoring Program Thermowell Pressure Raw Water Stainless Steel Loss of PSW and RHRSW Inspection Structural Monitoring Program Boundary Material Program was added in response to RAI 3.4-PSW-6, SNC Cracking PSW and RHRSW Chemistry correspondence HL-6002 Control Program dated October 10, 2000. Structural Monitoring Program Valve Bodies Pressure Raw Water Carbon Steel Loss of PSW and RHRSW Inspection Boundary Material Program Flow Blockage PSW and RHRSW Chemistry Control Program Cracking Structural Monitoring Program Galvanic Susceptibility Inspections Valve Bodies Pressure Raw Water Stainless Steel Loss of PSW and RHRSW Inspection Boundary Material Program Flow Blockage PSW and RHRSW Chemistry Control Program Cracking Structural Monitoring Program 2.3-23
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 101 of 363 Table 2.3-7 Plant Service Water System [P41] - Summary of Aging Management Review Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Valve Bodies Pressure Raw Water Copper Alloy Loss of PSW and RHRSW Inspection PSW and RHRSW Inspection Boundary Material Program Program was added in response to RAI 3.4-PSW-2, Flow Blockage PSW and RHRSW Chemistry SNC correspondence HL-6002 Control Program dated October 10, 2000; and in Cracking response to email from R.D. Structural Monitoring Program Baker to W.F. Burton, dated April 21, 2000. Venturi Pressure Raw Water Carbon Steel Loss of PSW and RHRSW Inspection Boundary Material Program Flow Blockage PSW and RHRSW Chemistry Control Program Cracking Structural Monitoring Program Galvanic Susceptibility Inspections Component Pressure Inside Carbon Steel Loss of Protective Coatings Program FSAR 18.3.3, Protective External Boundary Material Coatings Program Surfaces Outside (< 200 °F) Structural HL-6002, Sect. VI. B.2.3, Support Protective Coatings Program. NUREG 1803, Sect. 3.1.20, Protective Coatings Program 2.3-24
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 102 of 363 Table 2.3-7 Plant Service Water System [P41] - Summary of Aging Management Review Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Insulation Protect and Outside Various Loss of Equipment and Piping FSAR 18.3.4, Equipment and Insulate Piping Insulating Material Insulation Monitoring Program Piping Insulation Program Materials and Jacketing Cracking HL-6002, Sect. VI. B.2.4, Equipment and Piping Change in Insulation Monitoring Program. Material Properties NUREG 1803, Sect. 3.1.21, Equipment and Piping Insulation Monitoring Program 2.3-25
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 103 of 363 2.3.8 Reactor Building Closed Cooling Water System [P42]
System Description
The purpose of the reactor building closed cooling water (RBCCW) system is to provide cooling water to certain auxiliary equipment located in the reactor building. The RBCCW system is a closed-loop cooling system consisting of three one-half capacity pumps, two full-capacity heat exchangers, a surge tank, and a chemical addition system. The cooling water is conveyed by the pumps to the various system coolers and returned to the pumps by way of the RBCCW heat exchanger. The heat rejected by the RBCCW system to the heat exchanger is removed by the plant service water (PSW) system. HNP FSAR References The RBCCW system is described in the Unit 1 FSAR Section 10.5 and Unit 2 FSAR subsection 9.2.2. 2.3-26
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 104 of 363 Table 2.3-8 Reactor Building Closed Cooling Water System [P42] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Bolting Pressure Inside Carbon Steel Loss of Torque Activities Boundary Preload Protective Coatings Program Loss of Material Flexible Pressure Closed Stainless Steel Loss of Closed Cooling Water Connectors Boundary Cooling Water Material Chemistry Control Cracking Treated Water Systems Piping Inspections Flow Element Pressure Closed Stainless Steel Loss of Closed Cooling Water Boundary Cooling Water Material Chemistry Control Cracking Treated Water Systems Piping Inspection Heat Pressure Closed Carbon Steel Loss of Closed Cooling Water Exchanger Boundary Cooling Water Material Chemistry Control Shells Cracking Treated Water Systems Piping Inspection Piping Pressure Closed Carbon Steel Loss of Closed Cooling Water Boundary Cooling Water Material Chemistry Control Cracking Treated Water Systems Piping Inspection Piping Pressure Closed Stainless Steel Loss of Closed Cooling Water Boundary Cooling Water Material Chemistry Control Cracking Treated Water Systems Piping Inspection 2.3-27
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 105 of 363 Table 2.3-8 Reactor Building Closed Cooling Water System [P42] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Piping Pressure Closed Copper Alloy Loss of Closed Cooling Water Boundary Cooling Water Material Chemistry Control Cracking Treated Water Systems Piping Inspection Relief Valve Pressure Closed Copper Alloy Loss of Closed Cooling Water Base Boundary Cooling Water Material Chemistry Control Cracking Treated Water Systems Piping Inspection Temperature Pressure Closed Copper Alloy Loss of Closed Cooling Water Probe Boundary Cooling Water Material Chemistry Control Cracking Treated Water Systems Piping Inspection Thermowell Pressure Closed Stainless Steel Loss of Closed Cooling Water Boundary Cooling Water Material Chemistry Control Cracking Treated Water Systems Piping Inspection Valve Bodies Pressure Closed Carbon Steel Loss of Closed Cooling Water Boundary Cooling Water Material Chemistry Control Cracking Treated Water Systems Piping Inspection Valve Bodies Pressure Closed Stainless Steel Loss of Closed Cooling Water Boundary Cooling Water Material Chemistry Control Cracking Treated Water Systems Piping Inspection 2.3-28
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 106 of 363 Table 2.3-8 Reactor Building Closed Cooling Water System [P42] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Component Pressure Inside Carbon Steel Loss of Protective Coatings Program FSAR 18.3.3, Protective External Boundary Material Coatings Program Surfaces (< 200 °F) HL-6002, Sect. VI. B.2.3, Protective Coatings Program. NUREG 1803, Sect. 3.1.20, Protective Coatings Program 2.3-29
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 107 of 363 2.3.9 Instrument Air System [P52]
System Description
The purpose of the instrument air system is to provide dried and filtered air to all of the air operated instruments and valves throughout the entire plant (with the exception of equipment inside the drywell). The instrument air system is divided into the following two subsystems: Noninterruptible system provides instrument air for the operation of certain emergency system components. Interruptible system provides instrument air to all other components not supplied by the noninterruptible system. The drywell pneumatic system supplies the motive gas for components within the drywell. The requirements for the remainder of the compressed air systems are supplied by three oil-free screw-type compressors. Each compressor discharges into an air receiver which in turn discharges into a common manifold that feeds the instrument and service air systems. HNP FSAR References Additional information may be found in Unit 1 FSAR Section 10.11 and Unit 2 FSAR subsection 9.3.1. 2.3-30
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 108 of 363 Table 2.3-9 Instrument Air System [P52] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Air Receiver Pressure Dried Gas Stainless Steel Cracking None Required Boundary Bolting Pressure Inside Carbon Steel Loss of Torque Activities Boundary Preload Protective Coatings Program Loss of Material Bolting Pressure Inside Stainless Steel Loss of Torque Activities Boundary Preload Hose Pressure Dried Gas Stainless Steel Cracking None Required Boundary Piping Pressure Dried Gas Carbon Steel Cracking None Required Boundary Piping Pressure Dried Gas Stainless Steel Cracking None Required Boundary Regulator Pressure Dried Gas Carbon Steel Cracking None Required Pressure Boundary Restricting Pressure Dried Gas Stainless Steel Cracking None Required This line added for AST Orifice Boundary licensing amendments 256 (U1) and 200 (U2) Tubing Pressure Dried Gas Copper Cracking None Required Boundary Valve Bodies Pressure Dried Gas Stainless Steel Cracking None Required Boundary Valve Bodies Pressure Dried Gas Carbon Steel Cracking None Required Boundary Valve Bodies Pressure Dried Gas Copper Alloy Cracking None Required Boundary 2.3-31
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 109 of 363 Table 2.3-10 Primary Containment Chilled Water System [P64] (Unit 2 Only) - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Component Pressure Inside Carbon Steel Loss of Protective Coatings Program FSAR 18.3.3, Protective External Boundary Material Coatings Program Surfaces (< 200 °F) HL-6002, Sect. VI. B.2.3, Protective Coatings Program. NUREG 1803, Sect. 3.1.20, Protective Coatings Program 2.3-32
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 110 of 363 2.3.10 Primary Containment Chilled Water System [P64] (Unit 2 Only)
System Description
The primary containment chilled water system is designed to maintain the drywell area below a maximum volumetric average temperature of 150 °F dry bulb during normal operation by providing chilled water to the drywell fan coil units. The primary containment chilled water system consists of two chilled water recirculation pumps, two centrifugal chillers, a chemical addition tank, a chemical feed pump, and an expansion tank. Each chiller consists of a refrigerant compressor, condenser, cooler, accessories, and controls. Each chilled water recirculation pump circulates chilled water through the respective chiller to the fan coil units. Service water from the reactor building service water system is circulated through the chiller condensers for cooling. Demineralized water provides a source of makeup water for the chilled water system. The expansion tank, chemical addition tank, and associated makeup water supply are shared with the reactor and radwaste building chilled water system. HNP FSAR References More information may be found in Unit 2 FSAR subsection 9.4.6 2.3-33
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 111 of 363 Table 2.3-10 Primary Containment Chilled Water System [P64] (Unit 2 Only) - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Bolting Pressure Inside Carbon Steel Loss of Torque Activities Boundary Preload Protective Coatings Program Loss of Material Cap Pressure Closed Copper Alloy Loss of Closed Cooling Water Boundary Cooling Water Material Chemistry Control Cracking Treated Water Systems Piping Inspections Piping Pressure Closed Carbon Steel Loss of Closed Cooling Water Boundary Cooling Water Material Chemistry Control Cracking Treated Water Systems Piping Inspections Thermowell Pressure Closed Stainless Steel Loss of Closed Cooling Water Boundary Cooling Water Material Chemistry Control Cracking Treated Water Systems Piping Inspections Valve Bodies Pressure Closed Carbon Steel Loss of Closed Cooling Water Boundary Cooling Water Material Chemistry Control Cracking Treated Water Systems Piping Inspections 2.3-34
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 112 of 363 Table 2.3-10 Primary Containment Chilled Water System [P64] (Unit 2 Only) - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Component Pressure Inside Carbon Steel Loss of Protective Coatings Program FSAR 18.3.3, Protective External Boundary Material Coatings Program Surfaces (< 200 °F) HL-6002, Sect. VI. B.2.3, Protective Coatings Program. NUREG 1803, Sect. 3.1.20, Protective Coatings Program 2.3-35
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 113 of 363 2.3.11 Drywell Pneumatics System [P70]
System Description
The drywell pneumatic system supplies motive gas to the following equipment inside the drywell: reactor recirculation system sample line isolation valve, reactor pressure vessel (RPV) head vent valve, core spray (CS) system injection testable check valves and bypass valves, primary containment chilled water system control valves, residual heat removal (RHR) system low pressure coolant injection (LPCI) check valves and bypass valves, and nuclear boiler system safety relief valves (SRVs), and main steam isolation valves (MSIVs). A major portion of the drywell pneumatic system is primarily obsolete and not currently used. The control air is supplied from the nitrogen makeup system or instrument air. The system components still exist in the plant but are isolated by valve alignment or the lines are physically cut and capped. The drywell pneumatic system receives motive gas from the Unit 1 or Unit 2 nitrogen storage tanks, the instrument air system, or the emergency nitrogen hookup stations. The system includes an air receiver, particulate filters, flow sensing elements, and various process piping, valves, and regulators. Normally all system equipment upstream of the receiver tank is isolated, and system pressure is maintained by the nitrogen back-up supply with alternate supply through the instrument air supply system. Under emergency condition specific components in the drywell will be supplied control air from emergency nitrogen bottles. 2.3-36
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 114 of 363 Table 2.3-11 Drywell Pneumatics System [P70] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Bolting Pressure Inside Carbon Steel Loss of Torque Activities Boundary Preload Protective Coatings Program Loss of Material Bolting Pressure Inside Stainless Steel Loss of Torque Activities Boundary Preload Filter Pressure Dried Gas Carbon Steel Cracking None Required Housings Boundary Filter Pressure Dried Gas Stainless Steel Cracking None Required Housings Boundary Flanges Pressure Dried Gas Carbon Steel Cracking None Required Boundary Flexible Hoses Pressure Dried Gas Stainless Steel Cracking None Required Boundary Piping Pressure Dried Gas Carbon Steel Cracking None Required Boundary Piping Pressure Dried Gas Stainless Steel Cracking None Required Boundary Tubing Pressure Dried Gas Copper Cracking None Required Boundary Valve Bodies Pressure Dried Gas Carbon Steel Cracking None Required Boundary Valve Bodies Pressure Dried Gas Stainless Steel Cracking None Required Boundary Valve Bodies Pressure Dried Gas Copper Alloy Cracking None Required Boundary 2.3-37
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 115 of 363 Table 2.3-11 Drywell Pneumatics System [P70] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Component Pressure Inside Carbon Steel Loss of Protective Coatings Program FSAR 18.3.3, Protective External Boundary Material Coatings Program Surfaces (< 200 °F) HL-6002, Sect. VI. B.2.3, Protective Coatings Program. NUREG 1803, Sect. 3.1.20, Protective Coatings Program 2.3-38
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 116 of 363 2.3.12 Emergency Diesel Generator System [R43]
System Description
The purpose of the diesel generators is to provide emergency backup power to 4160 VAC emergency buses E, F, and G in the event of a loss of loss of offsite power. The diesel generators are designed to reach rated speed and voltage within 12 seconds after receiving a start signal. This allows operation of emergency equipment powered from these buses to perform their required function to safely shutdown the plant within the required time. The emergency diesel generator (EDG) provides a highly reliable source of standby, onsite, ac power. There are five diesel generators supplying standby power to 4.16 kV essential buses: 1E, 1F, 1G of Unit 1; and 2E, 2F, and 2G of Unit 2. Diesel generators 2A and 2C supply buses 2E and 2G respectively. Diesel generator 1B is shared between Units 1 and 2 and can supply power to either 1F or 2F. Diesel generator 1B has a selector switch with Unit 1 control and Unit 2 control positions, depending on whether it is supplying bus 1F or 2F. Diesel generators 1A and 1C supply buses 1E and 1G, respectively. The generator field is supplied dc power by a static exciter. The exciter-regulator provides a controlled current to the generator field winding to maintain and control the generator output voltage. In the automatic mode of voltage control, the generator output voltage is compared to a reference voltage to produce an error signal. Current transformers measure generator load and produce a proportional output. The load signal and voltage error signal are vectorally summed to produce an output which determines the generator field current and, thereby, the generator output voltage. In the manual mode, the operator controls generator output voltage by adjusting the voltage control lever on the remote control panel. When the voltage balance relay is energized, the output voltage control is transferred from automatic to manual. HNP FSAR References Additional information may be found in Unit 1 FSAR Section 8.4 and Unit 2 FSAR Section 8.3. 2.3-39
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 117 of 363 Table 2.3-12 Emergency Diesel Generator System [R43] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Expansion Pressure Demin Water Carbon Steel Loss of Demineralized Water and Tank Boundary Material Condensate Storage Tank Chemistry Control Cracking Treated Water Systems Piping Inspections Galvanic Susceptibility Inspections Filter housing Pressure Wetted Gas Carbon Steel Loss of Gas Systems Component Boundary Material Inspections Cracking Passive Component Inspection Activities Flex Hose Pressure Demin Water Stainless Steel Loss of Demineralized Water and Boundary Material Condensate Storage Tank Chemistry Control Cracking Treated Water Systems Piping Inspections Flexible Pressure Wetted Gas Stainless Steel Loss of Gas Systems Component Connector Boundary Material Inspections Cracking 2.3-40
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 118 of 363 Table 2.3-12 Emergency Diesel Generator System [R43] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Piping Pressure Demin Water Carbon Steel Loss of Demineralized Water and Boundary Material Condensate Storage Tank Chemistry Control Cracking Treated Water Systems Piping Inspections Galvanic Susceptibility Inspections Piping Pressure Wetted Gas Carbon Steel Loss of Gas Systems Component Boundary Material Inspections Cracking Passive Component Inspection Activities Piping Pressure Wetted Gas Stainless Steel Loss of Gas Systems Component Boundary Material Inspections Cracking Piping Pressure Air Galvanized Loss of Gas Systems Component Boundary Steel Material Inspections Cracking Passive Component Inspection Activities Restricting Pressure Wetted Gas Stainless Steel Loss of Gas Systems Component Orifice Boundary Material Inspections Cracking 2.3-41
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 119 of 363 Table 2.3-12 Emergency Diesel Generator System [R43] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Tanks Pressure Wetted Gas Carbon Steel Loss of Gas Systems Component Boundary Material Inspections Cracking Passive Component Inspection Activities Valve Bodies Pressure Demin Water Carbon Steel Loss of Demineralized Water and Boundary Material Condensate Storage Tank Chemistry Control Cracking Treated Water Systems Piping Inspections Galvanic Susceptibility Inspections Valve Bodies Pressure Wetted Gas Carbon Steel Loss of Gas Systems Component Boundary Material Inspections Cracking Passive Component Inspection Activities Valve Bodies Pressure Wetted Gas Stainless Steel Loss of Gas Systems Component Boundary Material Inspections Cracking 2.3-42
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 120 of 363 Table 2.3-12 Emergency Diesel Generator System [R43] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Valve Bodies Pressure Wetted Gas Copper Alloy Loss of Gas Systems Component Boundary Material Inspections Cracking Jacket Water Cooling Subsystem The Jacket Water Cooling Subsystem table is added in response to Open Item 2.3.3.2-1 (b), SNC correspondence HL-6092, dated June 5, 2001. Heater Pressure Demin Water Carbon Steel Loss of Diesel Generator Maintenance Housing Boundary and Antifreeze Material Activities Cracking Heat Pressure Demin Water Carbon Steel Loss of Diesel Generator Maintenance Exchanger Boundary and Antifreeze Material Activities Shell Heat Transfer Cracking Piping/Tubing Pressure Demin Water Carbon Steel Loss of Diesel Generator Maintenance Boundary and Antifreeze Material Activities Cracking 2.3-43
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 121 of 363 Table 2.3-12 Emergency Diesel Generator System [R43] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Piping/Tubing Pressure Demin Water Copper Loss of Diesel Generator Maintenance Boundary and Antifreeze Material Activities Cracking Piping/Tubing Pressure Demin Water Stainless Steel Loss of Diesel Generator Maintenance Boundary and Antifreeze Material Activities Cracking Pump Casing Pressure Demin Water Carbon Steel Loss of Diesel Generator Maintenance Boundary and Antifreeze Material Activities Cracking Restricting Flow Demin Water Carbon Steel Loss of Diesel Generator Maintenance Orifice Restriction and Antifreeze Material Activities Cracking Valve Bodies Pressure Demin Water Brass Loss of Diesel Generator Maintenance Boundary and Antifreeze Material Activities Cracking Valve Bodies Pressure Demin Water Bronze Loss of Diesel Generator Maintenance Boundary and Antifreeze Material Activities Cracking Valve Bodies Pressure Demin Water Carbon Steel Loss of Diesel Generator Maintenance Boundary and Antifreeze Material Activities Cracking 2.3-44
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 122 of 363 Table 2.3-12 Emergency Diesel Generator System [R43] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Valve Bodies Pressure Demin Water Cast Iron Loss of Diesel Generator Maintenance Boundary and Antifreeze Material Activities Cracking Valve Bodies Pressure Demin Water Stainless Steel Loss of Diesel Generator Maintenance Boundary and Antifreeze Material Activities Cracking Lubricating Oil Subsystem The Lubricating Oil Subsystem table is added in response to Open Item 2.3.3.2-1 (b), SNC correspondence HL-6092, dated June 5, 2001. Filter Housing Pressure Lube Oil Carbon Steel Loss of Diesel Generator Maintenance Boundary Material Activities Cracking Heater Pressure Lube Oil Carbon Steel Loss of Diesel Generator Maintenance Housing Boundary Material Activities Cracking 2.3-45
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 123 of 363 Table 2.3-12 Emergency Diesel Generator System [R43] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Heat Pressure Lube Oil Carbon Steel Loss of Diesel Generator Maintenance Exchanger Boundary Material Activities Shells Cracking Heat Transfer Piping/Tubing Pressure Lube Oil Carbon Steel Loss of Diesel Generator Maintenance Boundary Material Activities Cracking Piping/Tubing Pressure Lube Oil Copper Loss of Diesel Generator Maintenance Boundary Material Activities Cracking Pump Casing Pressure Lube Oil Carbon Steel Loss of Diesel Generator Maintenance Boundary Material Activities Cracking Strainer Pressure Lube Oil Carbon Steel Loss of Diesel Generator Maintenance Casing Boundary Material Activities Cracking Strainer Component Lube Oil Carbon Steel Loss of Diesel Generator Maintenance Element Protection Material Activities Valve Bodies Pressure Lube Oil Brass Loss of Diesel Generator Maintenance Boundary Material Activities Cracking Valve Bodies Pressure Lube Oil Bronze Loss of Diesel Generator Maintenance Boundary Material Activities Cracking 2.3-46
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 124 of 363 Table 2.3-12 Emergency Diesel Generator System [R43] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Valve Bodies Pressure Lube Oil Carbon Steel Loss of Diesel Generator Maintenance Boundary Material Activities Cracking Valve Bodies Pressure Lube Oil Cast Iron Loss of Diesel Generator Maintenance Boundary Material Activities Cracking Heat Exchanger Components Containing Service Water or Air Subsystem The Heat Exchanger Components Containing Service Water or Air subsystem table is added in response to Open Item 2.3.3.2-1 (b), SNC correspondence HL-6092, dated June 5, 2001. Bolting Pressure Moist Air Alloy Steel Loss of Torque Activities (applies to all Boundary Material Plant Coatings Program three EDG Loss of subsystems) Preload Bolting Pressure Moist Air Carbon Steel Loss of Torque Activities (applies to all Boundary Material Plant Coatings Program three EDG Loss of subsystems) Preload 2.3-47
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 125 of 363 Table 2.3-12 Emergency Diesel Generator System [R43] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Heat Pressure Moist Air Carbon Steel Loss of Diesel Generator Maintenance Exchanger Boundary Material Activities Shell Cracking Heat Transfer Piping/Tubing Pressure Raw Water Admiralty Loss of Diesel Generator Maintenance Boundary Brass Material Activities Heat Transfer Cracking Loss of Heat Exchanger Performance Piping/Tubing Pressure Raw Water Copper-Nickel Loss of Diesel Generator Maintenance Boundary Alloy Material Activities Heat Transfer Cracking Loss of Heat Exchanger Performance Piping/Tubing Pressure Raw Water Carbon Steel Loss of Diesel Generator Maintenance Boundary Material Activities Cracking Piping/Tubing Pressure Raw Water Stainless Steel Loss of Diesel Generator Maintenance Boundary Material Activities Cracking 2.3-48
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 126 of 363 Table 2.3-12 Emergency Diesel Generator System [R43] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Pump Casing Pressure Raw Water Carbon Steel Loss of Diesel Generator Maintenance Boundary Material Activities Cracking Valve Bodies Pressure Raw Water Carbon Steel Loss of Diesel Generator Maintenance Boundary Material Activities Cracking Valve Bodies Pressure Raw Water Copper Loss of Diesel Generator Maintenance Boundary Material Activities Cracking Valve Bodies Pressure Raw Water Stainless Steel Loss of Diesel Generator Maintenance Boundary Material Activities Cracking 2.3-49
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 127 of 363 2.3.13 Cranes, Hoists and Elevators System [T31]
System Description
The reactor building crane is the only inscope component for this system. The purpose of the reactor building crane is to provide the capability for moving major components for refueling operations and maintenance. The Unit 1 reactor building crane provides service to both Unit 1 and Unit 2. Capability includes the handling of shield plugs, reactor vessel heads, drywell heads, steam dryers, steam separators, and the spent-fuel shipping cask. The reactor building crane main and auxiliary hooks have an electrical interlock system to prevent their potential movement over spent fuel. HNP FSAR References Additional information may be found in Unit 1 FSAR Section 10.20 and Unit 2 FSAR Section 9.1. 2.3-50
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 128 of 363 Table 2.3-13 Cranes, Hoists and Elevators System [T31] - Aging Management Review Results Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Structural Structural Inside Carbon Steel Loss of Overhead Crane and Structural Monitoring Program Steel Support Material Refueling Platform was added in response to Inspection email from R.D. Baker to W.F. Burton, dated April 21, 2000. Structural Monitoring Program Protective Coatings Program 2.3-51
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 129 of 363 2.3.14 Tornado Vents System [T38]
System Description
The purpose of the tornado vents is to act as blowout panels for venting the reactor and control building roofs under the following conditions: Against a wind velocity of 300 mph. When the internal static pressure in the building is increased to 55 lb/ft2. When the temperature reaches approximately 212 °F. A rapid depressurization of air surrounding site structures can occur if a tornado funnel suddenly engulfs a structure. Venting is accomplished by placing blowout panels, designed to fail at a pressure lower than the safe building capability for internal pressure, to relieve excess pressure in all essential parts of such structures. HNP FSAR References Additional information may be found in Unit 2 FSAR paragraph 3.3.2.3. 2.3-52
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 130 of 363 Table 2.3-14 Tornado Vents System [T38] - Aging Management Review Results Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Screws Structural Inside Stainless None None Required Support Steel Outside Support Structural Inside Aluminum None None Required Frame Support Outside Tornado Relief Fission Inside Acrylic Cracking Structural Monitoring Program Vent Product (Plexiglas G Dome Barrier Outside Cellcast Acrylic Polymer) 2.3-53
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 131 of 363 2.3.15 Reactor Building HVAC System [T41]
System Description
The purposes of the reactor building HVAC system are to: Provide an environment with controlled temperature and airflow to ensure the comfort and safety of operating personnel and to optimize equipment performance by the removal of the heat dissipated from the plant equipment. Promote air movement from operating areas and areas of lower airborne radioactivity potential to areas of greater airborne radioactivity potential prior to final filtration and exhaust. Minimize the release of potential airborne radioactivity to the environment during normal plant operation by exhausting air, through a filtration system, from the areas in which a significant potential for radioactive particulates and/or radioiodine contamination exists. Provide a source of cooling to support the operation of the emergency core cooling systems (ECCS). Provide isolation capability to maintain secondary containment integrity and support operation of the standby gas treatment system (SGTS). The reactor building HVAC system utilizes a combination of air conditioning, heating, and once-through ventilation. Heat removal is provided by the ventilation air and by the chilled-water (Unit 2 only) and service-water cooling coils served by the reactor and radwaste building chilled water system and the plant service water (PSW) system, respectively. Hot water heating coils, served by the plant heating system, are provided for heating. HNP FSAR References Additional information may be found in Unit 1 FSAR Section 10.9 and Unit 2 FSAR subsection 9.4.2. 2.3-54
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 132 of 363 Table 2.3-15 Reactor Building HVAC System [T41] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Bolting Pressure Inside Carbon Steel Loss of Torque Activities Boundary Preload Protective Coatings Program Fission Loss of Product Material Barrier Cooling Coil Pressure Raw Water Copper Alloy Loss of PSW and RHRSW Inspection This line item is added in Tubing Boundary Material Program response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC Cracking PSW and RHRSW Chemistry correspondence HL-6092, Control Program dated June 5, 2001. Loss of Heat Exchanger Performance Damper Pressure Air Carbon Steel Loss of Gas Systems Component This line item is added in (frame only) Boundary Material Inspections response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC Cracking Passive Component Inspection correspondence HL-6092, Activities dated June 5, 2001. Ductwork Pressure Air Galvanized Cracking None Required Boundary Steel Fission Product Barrier 2.3-55
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 133 of 363 Table 2.3-15 Reactor Building HVAC System [T41] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Fan Housing Pressure Wetted Gas Carbon Steel Loss of Gas Systems Component This line item is added in Boundary Material Inspections response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC Cracking Passive Component Inspection correspondence HL-6092, Activities dated June 5, 2001. Fan Inlet Pressure Air Aluminum Loss of Gas Systems Component This line item is added in Housing Boundary Material Inspections response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC Cracking Passive Component Inspection correspondence HL-6092, Activities dated June 5, 2001. Fan Inlet Protection Inside Aluminum Loss of Gas Systems Component This line item is added in Screen from Debris Material Inspections response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC Passive Component Inspection correspondence HL-6092, Activities dated June 5, 2001. Flow Element Pressure Air Stainless Steel Cracking Gas Systems Component Boundary Inspections Tubing Pressure Air Copper Alloy Loss of Gas Systems Component Boundary Material Inspections Cracking 2.3-56
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 134 of 363 Table 2.3-15 Reactor Building HVAC System [T41] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Component Pressure Inside Carbon Steel Loss of Protective Coatings Program FSAR 18.3.3, Protective External Boundary Material Coatings Program Surfaces (< 200 °F) HL-6002, Sect. VI. B.2.3, Protective Coatings Program. NUREG 1803, Sect. 3.1.20, Protective Coatings Program 2.3-57
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 135 of 363 2.3.16 Traveling Water Screens/Trash Racks System [W33]
System Description
The purpose of the traveling water screens is to prevent debris from entering the portion of the intake structure from which the pumps take suction. Larger debris are prevented from reaching the screens by the trash racks. The screen system is composed of two traveling screens, two motors, and two screen wash lines which operate in parallel to serve the common bay from which both the Unit 1 and Unit 2 pumps take suction. The specifications for both the trash racks and traveling screens require that they maintain their structural integrity following a design basis earthquake (DBE). Therefore, the pumps would continue to be protected from river debris by both the trash racks and the screens. The normal environment for the traveling screens and trash racks is submerged in river water. 2.3-58
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 136 of 363 Table 2.3-16 Traveling Water Screens/Trash Racks System [W33] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Bolting Pressure Outside Carbon Steel Loss of Torque Activities This line item added in Boundary Material response to email from R.D. Protective Coatings Program Baker to W.F. Burton, dated Loss of April 21, 2000. Preload Trash Rack Debris Submerged Carbon Steel Loss of Structural Monitoring Program Protection Material Protective Coatings Program Traveling Debris Submerged Carbon Steel Loss of Structural Monitoring Program Screen Protection Material Stainless Steel Traveling Debris Submerged Copper Alloy None None Required Screen Protection Valve Bodies Pressure Raw Water Carbon Steel Loss of PSW and RHRSW Inspection Boundary Material Program Flow Blockage PSW and RHRSW Chemistry Control Program Cracking Galvanic Susceptibility Inspections Component Pressure Outside Carbon Steel Loss of Protective Coatings Program FSAR 18.3.3, Protective External Boundary Material Coatings Program Surfaces (< 200 °F) HL-6002, Sect. VI. B.2.3, Protective Coatings Program. NUREG 1803, Sect. 3.1.20, Protective Coatings Program 2.3-59
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 137 of 363 Table 2.3-16 Hydrogen Control System - Aging Management Review Results 2.3-60
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 138 of 363 2.3.17 Outside Structures HVAC System [X41]
System Description
The purpose of the intake structure HVAC system is to protect the intake structure equipment from adverse temperature conditions that could affect the reliability of the equipment. The diesel generator building HVAC system protects diesel generator building equipment from adverse temperature conditions that could affect the reliability of the equipment. The river intake structure HVAC system consists of roof-mounted exhaust ventilators, gravity-operated louvers, and wall-mounted unit heaters. The ventilators are powered from separate power sources. Each ventilator has a separate control station and is operated by an individual thermostat. The independent controls are powered from the motor control center (MCC) control transformer for the associated fan. Since selected plant service water (PSW) pumps operate during normal and accident conditions in the plant, the thermostats and the individual fan control stations are located in the Unit 1 and Unit 2 PSW pump bay areas. The locations of the thermostats ensure the ventilation system is always activated when operation of the PSW pumps causes a heat buildup in the area. The unit heaters and their associated thermostats are strategically located at different areas of the building to provide adequate area coverage for maintaining the building above freezing temperatures. The diesel generator rooms' heating and ventilating systems consist of a power roof exhaust ventilator in each room for exhausting heat from the rooms when the generator is shut down and two 100% capacity power roof exhaust ventilators in each room for exhausting heat from the rooms during generator actuation. Two motor-operated wall air intake louvers, with fire dampers in each room, replenish the air removed by the exhaust ventilation. One louver serves as the air intake to the generator area; the other serves as the air intake to the battery rooms through the generator area. HNP FSAR References Additional information about the system may be found in Unit 2 FSAR subsections 9.4.5 and 9.4.10. 2.3-61
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 139 of 363 Table 2.3-17 Outside Structures HVAC System [X41] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Bolting Pressure Inside Carbon Steel Loss of Torque Activities Boundary Preload Protective Coatings Program Loss of Material Bolting Pressure Outside Stainless Steel Loss of Torque Activities Boundary Preload Damper Pressure Air Carbon Steel Loss of Gas Systems Component This line item is added in (frame only) Boundary Material Inspections response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC Cracking Passive Component Inspection correspondence HL-6092, Activities dated June 5, 2001. Duct Sleeve Pressure Air Carbon Steel Loss of Gas Systems Component Boundary Material Inspections Cracking Passive Component Inspection Activities Fan Housing Pressure Air Carbon Steel Loss of Gas Systems Component This line item is added in Boundary Material Inspections response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC Cracking Passive Component Inspection correspondence HL-6092, Activities dated June 5, 2001. Restricting Pressure Air Stainless Steel Loss of Gas Systems Component Orifices Boundary Material Inspections Cracking Tubing Pressure Air Copper Loss of Gas Systems Component Boundary Material Inspections Cracking 2.3-62
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 140 of 363 Table 2.3-17 Outside Structures HVAC System [X41] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Unit Heater Flow Direction Inside Carbon Steel Loss of Gas Systems Component This line item is added in Housing Material Inspections response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC Cracking Passive Component Inspection correspondence HL-6092, Activities dated June 5, 2001. Component Pressure Inside Carbon Steel Loss of Protective Coatings Program FSAR 18.3.3, Protective External Boundary Material Coatings Program Surfaces Outside (< 200 °F) HL-6002, Sect. VI. B.2.3, Protective Coatings Program. NUREG 1803, Sect. 3.1.20, Protective Coatings Program 2.3-63
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 141 of 363 2.3.18 Fire Protection System [X43]
System Description
The fire protection program assures, through a defense-in-depth design, that a fire will not prevent the necessary safe plant shutdown functions from occurring. Increases in the risk of radioactive releases to the environment could occur without the fire protection program. The program consists of detection and extinguishing systems, administrative controls and procedures, and trained personnel. The defense-in-depth principle is aimed at achieving an adequate balance in these areas along with: Preventing fires from starting, Detecting fires quickly, rapidly suppressing fires that occur and limiting their damage, and Designing plant safety systems so that a fire which starts in spite of the fire protection program and burns for a significant period of time will not prevent essential plant safety functions from being performed. Primary design consideration is given to locating redundant safe shutdown circuits and components in distinct areas separated by fire barriers which prevent the propagation of fire to adjacent areas. The barriers are designed to contain a design basis fire which totally involves the combustibles in the given area. A state-of-the-art, early warning fire detection multiplex system is utilized. The system is configured around master/slave concept linked to a common command center. All devices (e.g., detectors, tamper switches, pressure switches, etc.) are wired to their respective slave panels. Signals from each of these devices are grouped according to their originating detection zone. There are approximately 260 detection zones throughout both units. Water supply for the fire protection system inside the protected area is provided by two 300,000 gallon dedicated storage tanks. The tanks are supplied by two deep wells, each with a 700 gpm makeup pump, capable of refilling either tank within 8 hours. These water supplies are strained and filtered for normal makeup. There are three fire pumps, two diesel engine driven and one electric motor driven. Each pump is rated for 2500 gpm capacity at 125 psi. A single 70 gpm, 125 psig pressure maintaining pump (jockey pump) is provided to keep the system filled and pressurized during low flow draw offs and in the event of system leakage. Additional information may be found in the Hatch Fire Hazards Analysis (FHA). 2.3-64
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 142 of 363 Table 2.3-18 Fire Protection System [X43] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Bolting Pressure Inside Carbon Steel Loss of Torque Activities Boundary Preload Outside Protective Coatings Program Loss of Material Fire Damper Pressure Air Carbon Steel Loss of Fire Protection Activities This line item is added in Boundary Material response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC Fire Barrier Cracking correspondence HL-6092, dated June 5, 2001. Fire Doors Fire Barrier Inside Carbon Steel Loss of Fire Protection Activities Material Fire Doors Fire Barrier Inside Galvanized None None Required Steel Copper Alloy Stainless Steel Aluminum Nonmetallic, Inorganic Gypsum Fibers, Nonasbestos Synthetic Nonmetallic, Organic 2.3-65
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 143 of 363 Table 2.3-18 Fire Protection System [X43] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Fire Hydrants Pressure Raw Water Cast Iron Loss of Fire Protection Activities Boundary Material Cracking Flow Blockage Fittings Pressure Raw Water Cast Iron Loss of Fire Protection Activities Boundary Material Air Cracking Flow Blockage Fittings Pressure Air Copper Alloy Loss of Fire Protection Activities Boundary Material Cast Iron Cracking Fusible Pressure Inside Nonferrous Loss of Fire Protection Activities Material Boundary Metal Material Cracking 2.3-66
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 144 of 363 Table 2.3-18 Fire Protection System [X43] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Kaowool and Fire Barrier Inside Galvanized Loss of Fire Protection Activities Loss of Material was added as Hold-Down Steel Material an AERM in response to RAI Straps 3.4-FPS-9, SNC Insulation Change in correspondence HL-6002 Material Material dated October 10, 2000. Properties Insulation Material was added and Cracking removed as an AERM in response to email from R.D. Baker to W.F. Burton, dated April 21, 2000. Nozzles Flow Air Copper Alloy Loss of Fire Protection Activities Flow blockage was removed Restriction Material as an AERM in response to RAI 3.4-FPS-8, SNC Cracking correspondence HL-6002 dated October 10, 2000. Nozzles Flow Air Aluminum Loss of Fire Protection Activities Restriction Material Copper Alloy Cracking Penetration Fire Barrier Inside; Ceramics Loss of Fire Protection Activities Seals Embedded Material Carbon Steel Cracking Synthetic Fiber Change in Elastomers Material Properties Concrete 2.3-67
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 145 of 363 Table 2.3-18 Fire Protection System [X43] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Pilot Valves Pressure Raw Water Aluminum Loss of Fire Protection Activities Boundary Material Cracking Flow Blockage Pipe Line Pressure Air Cast Iron Loss of Fire Protection Activities Strainers Boundary Material Cracking Flow Blockage Piping Pressure Raw Water Carbon Steel Loss of Fire Protection Activities Boundary Material Air Aluminum Cracking Galvanized Steel Flow Blockage Copper Alloy Cast Iron Piping Pressure Fuel Oil Carbon Steel Loss of Diesel Fuel Oil Testing Boundary Material Stainless Steel Fire Protection Activities Cracking Piping Pressure Air Carbon Steel Loss of Fire Protection Activities Boundary Material Carbon Galvanized Dioxide Steel Cracking Dried Gas 2.3-68
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 146 of 363 Table 2.3-18 Fire Protection System [X43] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Piping Pressure Buried Cast Iron None None Required This line item was added in Boundary response to Open Item 3.1.13-1 (a), SNC correspondence HL-6092, dated June 5, 2001. Pump Casings Pressure Raw Water Cast Iron Loss of Fire Protection Activities Boundary Material Cracking Flow Blockage Restricting Pressure Raw Water Stainless Steel Loss of Fire Protection Activities Orifices Boundary Material Air Flow Cracking Restriction Flow Blockage Sprinkler Head Pressure Inside Ceramics Cracking Fire Protection Activities Bulbs Boundary Sprinkler Head Pressure Inside Copper Cracking Fire Protection Activities Loss of Material was removed Links Boundary as an AERM in response to RAI 3.4-FPS-9, SNC correspondence HL-6002 dated October 10, 2000. 2.3-69
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 147 of 363 Table 2.3-18 Fire Protection System [X43] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Sprinkler Flow Direction Raw Water Stainless Steel Loss of Fire Protection Activities Heads Material Pressure Air Copper Alloy Boundary Cracking Carbon Steel Flow Flow Blockage Restriction Strainer Pressure Raw Water Stainless Steel Loss of Fire Protection Activities Basket Boundary Material Air Cracking Flow Blockage Strainers Pressure Air Cast Iron Loss of Fire Protection Activities Flow blockage was removed Boundary Material as an AERM in response to Raw Water RAI 3.4-FPS-8, SNC Cracking correspondence HL-6002 dated October 10, 2000. Tank Pressure Air Carbon Steel Loss of Fire Protection Activities Flow blockage was removed Boundary Material as an AERM in response to RAI 3.4-FPS-8, SNC Cracking correspondence HL-6002 dated October 10, 2000. Tank Pressure Raw Water Carbon Steel Loss of Fire Protection Activities Boundary Material Protective Coatings Program Cracking Flow Blockage 2.3-70
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 148 of 363 Table 2.3-18 Fire Protection System [X43] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Tank Pressure Fuel Oil Carbon Steel Loss of Diesel Fuel Oil Testing Boundary Material Fire Protection Activities Cracking Tank Pressure Carbon Carbon Steel Loss of Fire Protection Activities Boundary Dioxide Material Dried Cracking Gas Tank Environmental Inside Organic Loss of Fire Protection Activities Loss of Material was added as Insulation Control Material an AERM and Outside was Outside added as an Environment in Cracking response to RAI 3.4-FPS-9, SNC correspondence HL-6002 Change in dated October 10, 2000. Material Properties Tubing Pressure Fuel Oil Copper Alloy Loss of Diesel Fuel Oil Testing Boundary Material Fire Protection Activities Cracking Tubing Fittings Pressure Fuel Oil Copper Alloy Loss of Diesel Fuel Oil Testing Diesel Fuel Oil Testing was Boundary Material added in response to RAI 3.4-Raw Water Cast Iron Fire Protection Activities FPS-11, SNC correspondence Cracking HL-6002 dated October 10, Copper 2000. 2.3-71
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 149 of 363 Table 2.3-18 Fire Protection System [X43] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Valve Bodies Pressure Raw Water Carbon Steel Loss of Fire Protection Activities Boundary Material Air Cast Iron Cracking Copper Alloy Flow Blockage Valves Bodies Pressure Fuel Oil Copper Alloy Loss of Diesel Fuel Oil Testing Boundary Material Cast Iron Fire Protection Activities Cracking Valves Bodies Pressure Carbon Carbon Steel Loss of Fire Protection Activities Boundary Dioxide Material Copper Alloy Dried Gas Cracking Air Component Pressure Inside Carbon Steel Loss of Protective Coatings Program FSAR 18.3.3, Protective External Boundary Material Coatings Program Surfaces Outside (< 200 °F) HL-6002, Sect. VI. B.2.3, Protective Coatings Program. NUREG 1803, Sect. 3.1.20, Protective Coatings Program 2.3-72
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 150 of 363 Table 2.3-18 Fire Protection System [X43] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Insulation Protect and Outside Various Loss of Equipment and Piping FSAR 18.3.4, Equipment and Insulate Piping Insulating Material Insulation Monitoring Program Piping Insulation Program Materials and Jacketing Cracking HL-6002, Sect. VI. B.2.4, Equipment and Piping Change in Insulation Monitoring Program. Material Properties NUREG 1803, Sect. 3.1.21, Equipment and Piping Insulation Monitoring Program 2.3-73
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 151 of 363 2.3.19 Fuel Oil System [Y52]
System Description
The purpose of the fuel oil system is to receive, store, and supply fuel oil to other systems. Fuel oil is provided to the diesel generator system. Diesel engine fuel for Units 1 and 2 is stored in five interconnected buried tanks. Diesel fuel is transferred to the engine day tanks using dedicated, redundant transfer pumps and piping. The diesel fuel storage tanks are filled by gravity from a truck connection through a common header. Two of the buried tanks are dedicated to each of the Unit 1 and Unit 2 diesel generators. The remaining tank is used to supply the swing diesel (1B) to serve either Unit 1 or Unit 2. The fuel oil system transfer pumps operate continuously on demand from the day tank level controllers. Storage tank levels are monitored and alarmed (low level) in the main control room (MCR). HNP FSAR References Additional information may be found in Unit 1 FSAR Section 8.4 and Unit 2 FSAR subsection 9.5.4. 2.3-74
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 152 of 363 Table 2.3-19 Fuel Oil System [Y52] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Bolting Pressure Inside Carbon Steel Loss of Torque Activities Boundary Preload Protective Coatings Program Loss of Material Discharge Pressure Fuel Oil Carbon Steel Loss of Diesel Fuel Oil Testing Head Boundary Material Cracking Flex Hose Pressure Fuel Oil Stainless Steel Loss of Diesel Fuel Oil Testing Boundary Material Cracking Manway Shell Shelter/ Air Carbon Steel Loss of Gas Systems Component Protection Material Inspections Cracking Passive Component Inspection Activities Piping Pressure Fuel Oil Carbon Steel Loss of Diesel Fuel Oil Testing Boundary Material Cracking Piping Pressure Fuel Oil Stainless Steel Loss of Diesel Fuel Oil Testing Boundary Material Cracking 2.3-75
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 153 of 363 Table 2.3-19 Fuel Oil System [Y52] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Piping Pressure Air Carbon Steel Loss of Gas Systems Component Boundary Material Inspection Cracking Passive Component Inspection Activities Piping Pressure Air Stainless Steel Loss of Gas Systems Component Boundary Material Inspections Cracking Piping Pressure Buried Carbon Steel Loss of Protective Coatings Program This line item was added in Boundary with Coal Tar Material response to Open Item 3.1.13-Enamel 1 (a), SNC correspondence Coating HL-6092, dated June 5, 2001. Pump Pressure Fuel Oil Carbon Steel Loss of Diesel Fuel Oil Testing Boundary Material Cracking Strainer Shelter/ Fuel Oil Stainless Steel Loss of Diesel Fuel Oil Testing Cracking was removed as an Basket Protection Material AERM in response to email from R.D. Baker to W.F. Burton, dated June 20, 2000. Tank Pressure Fuel Oil Carbon Steel Loss of Diesel Fuel Oil Testing Cracking was removed as an Boundary Material AERM in response to email from R.D. Baker to W.F. Burton, dated June 20, 2000. 2.3-76
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 154 of 363 Table 2.3-19 Fuel Oil System [Y52] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Valve Bodies Pressure Fuel Oil Carbon Steel Loss of Diesel Fuel Oil Testing Boundary Material Cracking Valve Bodies Pressure Fuel Oil Stainless Steel Loss of Diesel Fuel Oil Testing Boundary Material Cracking Valve Bodies Pressure Air Carbon Steel Loss of Gas Systems Component Boundary Material Inspections Cracking Passive Component Inspection Activities Valve Bodies Pressure Air Stainless Steel Loss of Gas Systems Component Boundary Material Inspections Cracking Component Pressure Inside Carbon Steel Loss of Protective Coatings Program FSAR 18.3.3, Protective External Boundary Material Coatings Program Surfaces Shelter / (< 200 °F) Protection HL-6002, Sect. VI. B.2.3, Protective Coatings Program. NUREG 1803, Sect. 3.1.20, Protective Coatings Program 2.3-77
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 155 of 363 2.3.20 Control Building HVAC System [Z41]
System Description
The control building HVAC system performs the following functions under normal and post accident conditions of the plant: Provides temperature control and air movement control, including a filtered fresh-air supply, for personnel comfort. Optimizes equipment performance by the removal of the heat dissipated from the plant equipment. Minimizes the potential of exhaust air entering into the supply air intake by exhausting at an elevated point via the reactor building vent plenum. Detects and limits the introduction of radioactive material into the main control room (MCR). The control building is served by both heating and air-conditioning (A/C) subsystems and a once-through ventilation subsystem. The A/C subsystems use direct expansion of chilled water cooling coils. Heating is provided by electric or hot water heating coils. The control room, computer room, water analysis room, chemistry laboratory and health physics area, and cold laboratory are the areas served by the heating and A/C subsystems. The low pressure coolant injection (LPCI) inverter room and Unit 2 vital A/C room are served by separate coolers. All other areas of the control building are served by a once-through ventilation subsystem. HNP FSAR References For additional information see Unit 2 FSAR subsection 9.4.7. 2.3-78
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 156 of 363 Table 2.3-20 Control Building HVAC System [Z41] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Accumulator Pressure Air Carbon Steel Loss of Gas Systems Component Air Valve Boundary Material Inspections Cracking Accumulator Pressure Dried Gas Carbon Steel Cracking None Required Piping Boundary Accumulator Pressure Dried Gas Stainless Steel Cracking None Required Boundary Bolting Pressure Inside Carbon Steel Loss of Torque Activities Boundary Preload Protective Coatings Program Loss of Material Condensing Pressure Inside Carbon Steel Loss of Protective Coatings Program This line item is added in Unit Shell Boundary Material response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC Cracking correspondence HL-6092, dated June 5, 2001. Condensing Pressure Raw Water Gray Cast Iron Loss of PSW and RHRSW Inspection This line item is added in Unit Shell Boundary Material Program response to Open Item Dried Gas 2.3.3.2-2 (a), (c), and (d), SNC Cracking PSW and RHRSW Chemistry correspondence HL-6092, Control Program dated June 5, 2001. 2.3-79
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 157 of 363 Table 2.3-20 Control Building HVAC System [Z41] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Condensing Pressure Raw Water Copper Alloy Loss of PSW and RHRSW Inspection This line item is added in Unit Tubing Boundary Material Program response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC Cracking PSW and RHRSW Chemistry correspondence HL-6092, Control Program dated June 5, 2001. Loss of Heat Exchanger Performance Damper Pressure Air Carbon Steel Loss of Gas Systems Component This line item is added in (frame only) Boundary Material Inspections response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC Cracking Passive Component Inspection correspondence HL-6092, Activities dated June 5, 2001. Damper Pressure Air Gray Cast Iron Loss of Gas Systems Component This line item is added in (frame only) Boundary Material Inspections response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC Cracking Passive Component Inspection correspondence HL-6092, Activities dated June 5, 2001. Duct Gasket Pressure Air Fibers, Material Gas Systems Component Boundary Nonasbestos Property Inspections Inside Synthetic Changes Passive Component Inspection Elastomers, Cracking Activities Other Duct Heater Pressure Air Aluminum Loss of Gas Systems Component Boundary Material Inspections Duct Silencer Pressure Air Galvanized Cracking None Required Boundary Steel 2.3-80
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 158 of 363 Table 2.3-20 Control Building HVAC System [Z41] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Ductwork Pressure Air Carbon Steel Loss of Gas Systems Component Boundary Material Inspections Cracking Passive Component Inspection Activities Ductwork Pressure Outside Galvanized Loss of Gas Systems Component Boundary Steel Material Inspections Cracking Passive Component Inspection Activities Ductwork Flex Pressure Air Fibers, Non- Material Gas Systems Component Connector Boundary Asbestos Property Inspections Inside Synthetic Changes Passive Component Inspection Elastomers, Cracking Activities Other Fan Housing Pressure Air Aluminum Loss of Gas Systems Component This line item is added in Boundary Material Inspections response to Open Item Wetted 2.3.3.2-2 (a), (c), and (d), SNC Cracking Passive Component Inspection correspondence HL-6092, Activities dated June 5, 2001. Fan Housing Pressure Air Carbon Steel Loss of Gas Systems Component This line item is added in Boundary Material Inspections response to Open Item Wetted 2.3.3.2-2 (a), (c), and (d), SNC Cracking Passive Component Inspection correspondence HL-6092, Activities dated June 5, 2001. 2.3-81
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 159 of 363 Table 2.3-20 Control Building HVAC System [Z41] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Fan Housing Pressure Air Galvanized Loss of Gas Systems Component This line item is added in Boundary Steel Material Inspections response to Open Item Wetted 2.3.3.2-2 (a), (c), and (d), SNC Cracking Passive Component Inspection correspondence HL-6092, Activities dated June 5, 2001. Filter Housing Pressure Air Galvanized Cracking None Required Boundary Steel Fan Screen Protection Air Carbon Steel Loss of Gas Systems Component This line item is added in from Debris Material Inspections response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC Cracking Passive Component Inspection correspondence HL-6092, Activities dated June 5, 2001. Flow Element Pressure Air Stainless Steel Cracking None Required This line item is added in Boundary response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC correspondence HL-6092, dated June 5, 2001. Instrument Pressure Air Stainless Steel Loss of Gas Systems Component Piping Boundary Material Inspections Cracking Instrument Pressure Air Copper Alloy Loss of Gas Systems Component Piping Boundary Material Inspections Cracking 2.3-82
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 160 of 363 Table 2.3-20 Control Building HVAC System [Z41] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Louver Pressure Outside Carbon Steel Loss of Gas Systems Component Boundary Material Inspections Cracking Passive Component Inspection Activities Piping Pressure Air Stainless Steel Loss of Gas Systems Component Boundary Material Inspections Cracking Radiation Pressure Air Stainless Steel Loss of Gas Systems Component Element Boundary Material Inspections Cracking Restricting Pressure Air Stainless Steel Loss of Gas Systems Component Orifice Boundary Material Inspections Cracking Thermowell Pressure Inside Stainless Steel Cracking None Required Boundary Tubing Pressure Dried Gas Copper Cracking None Required Boundary Valve Bodies Pressure Dried Gas Carbon Steel Cracking None Required Boundary Valve Bodies Pressure Dried Gas Copper Alloy Cracking None Required Boundary Valve Bodies Pressure Air Stainless Steel Loss of Gas Systems Component Boundary Material Inspections Cracking 2.3-83
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 161 of 363 Table 2.3-20 Control Building HVAC System [Z41] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Component Pressure Inside Carbon Steel Loss of Protective Coatings Program FSAR 18.3.3, Protective External Boundary Material Coatings Program Surfaces (< 200 °F) HL-6002, Sect. VI. B.2.3, Protective Coatings Program. NUREG 1803, Sect. 3.1.20, Protective Coatings Program 2.3-84
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 162 of 363 2.3.21 Turbine Building HVAC System [U41]
System Description
The Turbine Building HVAC System performs the following functions under normal and post accident conditions of the plant: Provides temperature control and air movement control, including a filtered fresh-air supply, for personnel comfort. Optimizes equipment performance by the removal of heat dissipated from plant equipment. Provides for air movement from areas of lesser potential airborne radioactivity to areas of greater potential airborne radioactivity prior to final exhaust. Minimizes the possibility of exhaust air recirculation into the air intake. Minimizes the escape of potential airborne radioactivity to the outside atmosphere during normal operation by exhausting air through a suitable filtration system from the areas in which a significant potential for radioactive particulates and radioactive iodine contamination exists. Purges the Turbine Building area around the main control room to remove airborne radioactivity following a design basis loss of coolant accident, control rod drop accident, or main steam line break. Fresh air from outside is supplied to the Turbine Building by a duct system with two supply fans. Normally, one fan is in operation while the other is on standby. If the operating supply fan fails, the standby fan starts automatically. The normal outside air supply is filtered and tempered through a hot water heating coil. Air is exhausted from the Turbine Building by a duct system to the Reactor Building vent plenum by two exhaust fans. The Turbine Building exhaust is filtered by two 50% capacity filter trains. Each filter train consists of a bank of prefilters, carbon adsorbers, and HEPA filters. Only one of the two 100% capacity exhaust fans is normally in operation. If the operating exhaust fan fails, the standby fan starts automatically. Following a design basis loss of coolant accident, control rod drop accident, or main steam line break, leakage past the MSIVs is contained in the main steam piping downstream of the MSIVs and in the main condenser. One Turbine Building exhaust fan is manually placed in operation to purge the Turbine Building area around the main control room of any airborne radioactivity which might leak out of the main steam piping or main condenser in order to reduce the dose received by personnel in the main control room. HNP FSAR References More information about this system may be found in Unit 1 FSAR Section 10.9.3.4 and Unit 2 FSAR Section 9.4.4. 2.3-85
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 163 of 363 Table 2.3-21 Turbine Building HVAC System [U41] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Bolting Pressure Inside Carbon Steel Loss of Torque Activities This line added for AST Boundary Preload licensing amendments 256 Protective Coatings Program (U1) and 200 (U2) Loss of Material Damper Pressure Air Carbon Steel Loss of Gas Systems Component This line added for AST (frame only) Boundary Material Inspections licensing amendments 256 (U1) and 200 (U2) Cracking Passive Component Inspection Activities Duct Gasket Pressure Air Elastomers, Material Gas Systems Component This line added for AST Boundary Other Property Inspections licensing amendments 256 Inside Changes (U1) and 200 (U2) Passive Component Inspection Cracking Activities Ductwork Pressure Air Galvanized Cracking None Required This line added for AST Boundary Steel licensing amendments 256 (U1) and 200 (U2) Ductwork Flex Pressure Air Elastomers, Material Gas Systems Component This line added for AST Connector Boundary Other Property Inspections licensing amendments 256 Inside Changes (U1) and 200 (U2) Passive Component Inspection Cracking Activities Fan Housing Pressure Air Carbon Steel Loss of Gas Systems Component This line added for AST Boundary Material Inspections licensing amendments 256 (U1) and 200 (U2) Cracking Passive Component Inspection Activities 2.3-86
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 164 of 363 Table 2.3-21 Turbine Building HVAC System [U41] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Filter Housing Pressure Air Carbon Steel Loss of Gas Systems Component This line added for AST Boundary Material Inspections licensing amendments 256 (U1) and 200 (U2) Cracking Passive Component Inspection Activities Flow Element Pressure Air Stainless Steel Cracking None Required This line added for AST Boundary licensing amendments 256 (U1) and 200 (U2) Instrument Pressure Air Stainless Steel Loss of Gas Systems Component This line added for AST Piping Boundary Material Inspections licensing amendments 256 (U1) and 200 (U2) Cracking Piping Pressure Air Carbon Steel Loss of Gas Systems Component This line added for AST Boundary Material Inspections licensing amendments 256 (U1) and 200 (U2) Cracking Passive Component Inspection Activities Radiation Pressure Air Stainless Steel Loss of Gas Systems Component This line added for AST Element Boundary Material Inspections licensing amendments 256 (U1) and 200 (U2) Cracking Tubing Pressure Air Copper Cracking None Required This line added for AST Boundary licensing amendments 256 (U1) and 200 (U2) Valve Bodies Pressure Air Cast Iron Loss of Gas Systems Component This line added for AST Boundary Material Inspections licensing amendments 256 (U1) and 200 (U2) Cracking Passive Component Inspection Activities 2.3-87
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 165 of 363 Table 2.3-21 Turbine Building HVAC System [U41] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Valve Bodies Pressure Air Copper Alloy Cracking None Required This line added for AST Boundary licensing amendments 256 (U1) and 200 (U2) Component Pressure Inside Carbon Steel Loss of Protective Coatings Program This line added for AST External Boundary Material licensing amendments 256 Surfaces (U1) and 200 (U2) (< 200 °F) 2.3-88
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 166 of 363 2.4 Steam And Power Conversion Systems The Steam and Power Conversion Systems are addressed in the following sections:
- Electro-Hydraulic Control System, Section 2.4.1
- Main Condenser System, Section 2.4.2 2.4.1 Electro-Hydraulic Control System [N32]
System Description
The purpose of the electro-hydraulic control (EHC) system is to provide control of reactor pressure during reactor startup, power operation, and shutdown. EHC also provides a means of controlling main turbine speed and acceleration during turbine startup and protect the main turbine from undesirable operating conditions by initiating alarms, trips, and runbacks. HNP FSAR References Additional information about this system may be found in Unit 1 FSAR Section 11.2 and Unit 2 FSAR subsection 10.2A.1. 2.4-1
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 167 of 363 Table 2.4-1 Electro-Hydraulic Control System [N32] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Piping Pressure Reactor Water Stainless Loss of Reactor Water Chemistry Boundary Steel Material Control Cracking Treated Water Systems Piping Inspections Valve Bodies Pressure Reactor Water Stainless Loss of Reactor Water Chemistry Boundary Steel Material Control Cracking Treated Water Systems Piping Inspections 2.4-2
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 168 of 363 2.4.2 Main Condenser System [N61]
System Description
The main condenser provides a heat sink for turbine exhaust steam, turbine bypass steam, and other flows such as cascading heater drains, air ejector condenser drains, exhaust from the feed pump turbines, gland seal condenser, feedwater heater shell operating vents, and condensate pump suction vents. The main condenser also deaerates and provides storage capacity for the condensate water to be reused. During plant operation, steam from the last-stage, low-pressure turbine is exhausted directly downward into the condenser shells through exhaust openings in the bottom of the turbine casings. The condenser serves as a heat sink for several others flows, such as exhaust steam from the feed pump turbines, cascading heater drains, air ejector condenser drain, gland-seal condenser drain, feedwater heater shell operating vents, and condensate pump suction vents. Other flows occur periodically. These originate from condensate and reactor feed pump startup vents, reactor feed pump minimum recirculation flow, feedwater lines startup flushing, turbine equipment clean drains, low-point drains, extraction steam spills, makeup, and condensate. During abnormal conditions, the condenser is designed to receive (not simultaneously) turbine bypass steam, feedwater heater high-level dumps, and relief valve discharge from feedwater heater shells, steam-seal regulator, and various steam supply lines. During a design basis loss of coolant accident, control rod drop accident, or main steam line break, the main condenser and main steam piping downstream of the MSIVs are credited for a reduction in the offsite dose associated with leakage past the MSIVs. Retention of MSIV leakage within these components provides for holdup and deposition of radionuclides. Also credited is an alternate leakage treatment path from the main steam lines downstream of the MSIVs to the condenser. HNP FSAR References Additional information may be found in Unit 2 FSAR subsection 10.4.1. 2.4-3
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 169 of 363 Table 2.4-2 Main Condenser System [N61] - Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Bolting Pressure Inside Carbon Steel Loss of Torque Activities Revised to include Unit 1 Boundary Preload components following Protective Coatings Program implementation of Alternate Fission Loss of Source Term License Product Material Amendment 256. Barrier Condenser Pressure Reactor Water Carbon Steel Loss of Reactor Water Chemistry Revised to include Unit 1 Shell Boundary Material Control components following implementation of Alternate Fission Cracking Treated Water Systems Piping Source Term License Product Inspections Amendment 256. Barrier Galvanic Susceptibility Inspections Piping Pressure Reactor Water Carbon Steel Loss of Reactor Water Chemistry Revised to include Unit 1 Boundary Material Control components following implementation of Alternate Fission Cracking Flow Accelerated Corrosion Source Term License Product Program Amendment 256. Barrier Galvanic Susceptibility Inspections Treated Water Systems Piping Inspections 2.4-4
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 170 of 363 Table 2.4-2 Main Condenser System [N61]- Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Piping Pressure Reactor Water Stainless Steel Loss of Reactor Water Chemistry This row appears twice in the Boundary Material Control LRA and the duplicate was removed in response to RAI Fission Cracking Treated Water Systems Piping 3.5-MC-1, SNC Product Inspections correspondence HL-6002 Barrier dated October 10, 2000. Revised to include Unit 1 components following implementation of Alternate Source Term License Amendment 256. Preheater Pressure Reactor Water Carbon Steel Loss of Reactor Water Chemistry Not applicable to Unit 1 Boundary Material Control Fission Cracking Treated Water Systems Piping Product Inspections Barrier Preheater Pressure Reactor Water Stainless Steel Loss of Reactor Water Chemistry Not applicable to Unit 1 Boundary Material Control Fission Cracking Treated Water Systems Piping Product Inspections Barrier Restricting Pressure Reactor Water Stainless Steel Loss of Reactor Water Chemistry Revised to include Unit 1 Orifices Boundary Material Control components following implementation of Alternate Fission Cracking Treated Water Systems Piping Source Term License Product Inspections Amendment 256. Barrier 2.4-5
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 171 of 363 Table 2.4-2 Main Condenser System [N61]- Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Steam Traps Pressure Reactor Water Carbon Steel Loss of Reactor Water Chemistry Unit 2 Only Boundary Material Control Fission Cracking Flow Accelerated Corrosion Revised to remove Unit 1 Product Program components incorrectly added Barrier following implementation of Galvanic Susceptibility Alternate Source Term License Inspections Amendment 256. See RER SNC460325. Treated Water Systems Piping Inspections Strainer Pressure Reactor Water Carbon Steel Loss of Reactor Water Chemistry Revised to include Unit 1 Boundary Material Control components following implementation of Alternate Fission Cracking Flow Accelerated Corrosion Source Term License Product Program Amendment 256. Barrier Galvanic Susceptibility Inspections Treated Water Systems Piping Inspections Thermowell Pressure Reactor Water Stainless Loss of Reactor Water Chemistry Revised to include Unit 1 Boundary Steel Material Control components following implementation of Alternate Fission Cracking Treated Water Systems Piping Source Term License Product Inspections Amendment 256. Barrier VER 2.0 2.4-6
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 172 of 363 Table 2.4-2 Main Condenser System [N61]- Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Valve Bodies Pressure Reactor Water Carbon Steel Loss of Reactor Water Chemistry Boundary Material Control Revised to include Unit 1 components following Fission Cracking Flow Accelerated Corrosion implementation of Alternate Product Program Source Term License Barrier Amendment 256. Galvanic Susceptibility Inspections Component function of Fission Product Barrier added Treated Water Systems Piping following implementation of Inspections Alternate Source Term license amendments 256 (U1) and 200 (U2) Valve Bodies Pressure Reactor Water Stainless Loss of Reactor Water Chemistry Revised to include Unit 1 Boundary Steel Material Control components following implementation of Alternate Fission Cracking Treated Water Systems Piping Source Term License Product Inspections Amendment 256. Barrier Component function of Fission Product Barrier added following implementation of Alternate Source Term license amendments 256 (U1) and 200 (U2) 2.4-7
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 173 of 363 Table 2.4-2 Main Condenser System [N61]- Aging Management Review Results Mechanical Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Component Pressure Inside Carbon Steel Loss of Protective Coatings Program FSAR 18.3.3, Protective External Boundary Material Coatings Program Surfaces (< 200 °F) Fission HL-6002, Sect. VI. B.2.3, Product Protective Coatings Program. Barrier NUREG 1803, Sect. 3.1.20, Protective Coatings Program Revised to include Unit 1 components following implementation of Alternate Source Term License Amendment 256. 2.4-8
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 174 of 363 2.5 Structures and Component Supports The Structures and Component Supports are addressed in the following sections:
- Piping Specialties, Section 2.5.1
- Conduits, Raceways, and Trays, Section 2.5.2
- Primary Containment, Section 2.5.3
- Fuel Storage, Section 2.5.4
- Reactor Building, Section 2.5.5
- Drywell Penetrations, Section 2.5.6
- Reactor Building Penetrations, Section 2.5.7
- Turbine Building, Section 2.5.8
- Intake Structure, Section 2.5.9
- Yard Structures, Section 2.5.10
- Main Stack, Section 2.5.11
- EDG Building, Section 2.5.12
- Control Building, Section 2.5.13
- Switchyard Structures, Section 2.5.14 2.5.1 Piping Specialties [L35]
System Description
Piping specialties provide support for essential piping systems. Essential piping systems are required to maintain the integrity of safety-related and nonsafety-related systems during normal operations and transient/accident mitigation. These specialties include snubbers and pipe restraints regardless of system affiliation and also include non-ASME HVAC duct supports and tube trays. 2.5-1
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 175 of 363 Table 2.5-1 Piping Specialties [L35] - Aging Management Review Results Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Hangers and Structural Containment Carbon Steel Loss of Structural Monitoring Program Supports Support Atmosphere Material for ASME Galvanized Protective Coatings Program Class I Inside Steel Piping Hangers and Structural Containment Stainless Steel None None Required Supports Support Atmosphere for ASME Class I Inside Piping Hangers and Structural Containment Carbon Steel Loss of Structural Monitoring Program Supports Support Atmosphere Material for Non ASME Galvanized Protective Coatings Program Class I Nonsafety Inside Steel Piping, Related Tubing, and Structural Outside Stainless Steel Ducts Support Submerged Tube Trays Structural Inside Stainless Steel None None Required and Support Covers Outside Nonsafety Related Structural Support 2.5-2
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 176 of 363 2.5.2 Conduits, Raceways, and Trays [R33]
System Description
The purpose of the conduits, raceways, and trays system is to provide support for a cable system with cables and penetrations selected, routed, and located to survive the design basis events established for this plant and prevent a loss of function of any system due to a cable failure. HNP FSAR References Additional information may be found in Unit 1 FSAR Section 8.8 and Unit 2 FSAR Section 8.3. 2.5-3
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 177 of 363 Table 2.5-2 Conduits, Raceways, and Trays [R33] - Aging Management Review Results Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Cable Trays Structural Containment Carbon Steel Loss of Structural Monitoring Program and Support Atmosphere Material supports Galvanized Protective Coatings Program Nonsafety Inside Steel Related Structural Support Cable Trays Structural Containment Aluminum None None Required and Support Atmosphere supports Nonsafety Inside Related Structural Support 2.5-4
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 178 of 363 2.5.3 Primary Containment [T23]
System Description
The purpose of the primary containment is to isolate and contain fission products released from the reactor primary system following a design basis accident (DBA) and to confine the postulated release of radioactive material. The primary containment design employs a pressure suppression containment system which houses the reactor vessel, the reactor coolant recirculating loops, and other branch connections of the reactor primary system. The pressure suppression system consists of a drywell, a pressure suppression chamber (torus) which stores a large volume of water, a connecting vent system between the drywell and the pressure suppression pool, isolation valves, vacuum relief system, containment cooling systems, and other service equipment. The pressure suppression chamber is a steel pressure vessel in the shape of a torus located below and encircling the drywell, with a major diameter of approximately 107 ft and a cross-sectional diameter of approximately 28 ft. The pressure suppression chamber contains the suppression pool and the air space above the pool. The suppression chamber transmits seismic loading to the reinforced concrete foundation slab of the reactor building. Space is provided outside of the chamber for inspection. HNP FSAR References Additional information about this system may be found in Unit 1 FSAR subsection 5.1.2 and Unit 2 FSAR subsection 6.2.1. 2.5-5
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 179 of 363 Table 2.5-3 Primary Containment [T23] - Summary of Aging Management Review Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Anchors and Structural Containment Carbon Steel Loss of Protective Coatings Program Bolts Support Atmosphere Material Galvanized Inservice Inspection Program Nonsafety Embedded Steel Related Suppression Pool Chemistry Structural Inside Stainless Steel Control Support Torus Water Bolting Pressure Containment Carbon Steel Loss of Protective Coatings Program Line item added in response to Boundary Atmosphere Material email from R.D. Baker to W.F. Torque Activities Burton, dated April 21, 2000. Inside Loss of Preload Blind Flange* Fission Torus Water Carbon Steel Loss of Suppression Pool Chemistry Treated Water Systems Piping Product Material Control Inspections was added in Barrier response to email from R.D. Cracking Treated Water Systems Piping Baker to W.F. Burton, dated Inspections April 21, 2000. Containment Fission Demin Water Stainless Steel Loss of Demineralized Water and Isolation Product Material Condensate Storage Tank Valves* Barrier Chemistry Control Cracking Treated Water Systems Piping Inspections Containment Fission Demin Water Carbon Steel Loss of Demineralized Water and Isolation Product Material Condensate Storage Tank Valves* Barrier Chemistry Control Cracking Treated Water Systems Piping Inspections 2.5-6
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 180 of 363 Table 2.5-3 Primary Containment [T23] - Summary of Aging Management Review Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Containment Fission Torus Water Carbon Steel Loss of Suppression Pool Chemistry Isolation Product Material Control Valves* Barrier Treated Water Systems Piping Inspections Containment Fission Raw Water Carbon Steel Loss of Passive Component Inspection Isolation Product Material Activities Valves* Barrier Cracking Containment Fission Wetted Gas Carbon Steel Loss of Gas Systems Component Isolation Product Material Inspections Valves* Barrier Passive Component Inspection Activities Containment Fission Wetted Gas Stainless Steel Loss of Gas Systems Component Isolation Product Material Inspection Valves* Barrier Cracking Containment Fission Containment Carbon Steel Loss of Protective Coatings Program Penetrations Product Atmosphere Material (Mechanical Barrier Stainless Steel Inservice Inspection Program only) Embedded Primary Containment Leakage Inside Rate Testing Program 2.5-7
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 181 of 363 Table 2.5-3 Primary Containment [T23] - Summary of Aging Management Review Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Miscellaneous Structural Containment Carbon Steel Loss of Protective Coatings Program Steel Support Atmosphere Material Galvanized Inservice Inspection Program Radiation Embedded Steel Shielding Suppression Pool Chemistry Inside Control Nonsafety Related High Humidity Structural Support Torus Water Pipe Whip Restraint Piping* Fission Demin Water Stainless Steel Loss of Demineralized Water and Product Material Condensate Storage Tank Barrier Chemistry Control Cracking Treated Water Systems Piping Inspections Piping* Fission Torus Water Carbon Steel Loss of Suppression Pool Chemistry Product Material Control Barrier Cracking Treated Water Systems Piping Inspections Piping* Fission Raw Water Carbon Steel Loss of Passive Component Inspection Product Material Activities Barrier Cracking 2.5-8
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 182 of 363 Table 2.5-3 Primary Containment [T23] - Summary of Aging Management Review Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Piping* Fission Wetted Gas Carbon Steel Loss of Gas Systems Component Product Material Inspections Barrier Cracking Passive Component Inspection Activities Piping* Fission Wetted Gas Stainless Steel Loss of Gas Systems Component Product Material Inspection Barrier Reinforced Structural Containment Concrete Loss of Structural Monitoring Program Concrete Support Atmosphere Material Carbon Steel Protective Coatings Program Shelter/Protect Inside ion Radiation Shielding HE/ME Shielding Missile Barrier Fission Product Barrier Flood Barrier 2.5-9
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 183 of 363 Table 2.5-3 Primary Containment [T23] - Summary of Aging Management Review Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Steel Bellows Pressure Containment Carbon Steel Loss of Protective Coatings Program (Inside Boundary Atmosphere Material Vent Pipe) Stainless Steel Inservice Inspection Program Fission Inside Product Primary Containment Leakage Barrier Rate Testing Program 2.5-10
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 184 of 363 Table 2.5-3 Primary Containment [T23] - Summary of Aging Management Review Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Structural Structural Containment Carbon Steel Loss of Protective Coatings Program Steel Support Atmosphere Material Stainless Steel Primary Containment Leakage Shelter/Protect Embedded Cracking Rate Testing Program ion Inside Inservice Inspection Program Pressure Suppression Pool Chemistry Boundary Torus Water Control Radiation Component Cyclic or Transient Shielding Limit Program Nonsafety Related Structural Support HE/ME Shielding Missile Barrier Pipe Whip Restraint Fission Product Barrier Exchange Heat 2.5-11
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 185 of 363 Table 2.5-3 Primary Containment [T23] - Summary of Aging Management Review Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Tubing* Pressure Wetted Gas Stainless Steel Loss of Gas Systems Component Boundary Material Inspections Fission Cracking Product Barrier Vent Pipe, Pressure Containment Carbon Steel Loss of Protective Coatings Program Vent Boundary Atmosphere Material Header, Inservice Inspection Program Downcomers Fission Inside Cracking Product Primary Containment Leakage Barrier High Humidity Rate Testing Program Torus Water Component Cyclic or Transient Limit Program Suppression Pool Chemistry Control Component Pressure Inside Carbon Steel Loss of Protective Coatings Program FSAR 18.3.3, Protective External Boundary Material Coatings Program Surfaces (< 200 °F) Fission HL-6002, Sect. VI. B.2.3, Product Protective Coatings Program. Barrier NUREG 1803, Sect. 3.1.20, Protective Coatings Program
- Piping and valve bodies include components from systems P51, P21, T23, G51, G11, D11, and C51. These are all included in function T23-01, Torus/Drywell.
2.5-12
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 186 of 363 2.5.4 Fuel Storage [T24]
System Description
The purpose of the fuel storage system is to provide specially designed underwater storage space for the spent-fuel assemblies which require shielding during storage and handling. The fuel storage facility is located inside the secondary containment on the refueling floor. HNP FSAR References Additional information may be found in Unit 1 FSAR Section 10.2, 10.3 and Unit 2 FSAR Section 9.1. 2.5-13
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 187 of 363 Table 2.5-4 Fuel Storage [T24] - Summary of Aging Management Review Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Anchors and Structural Inside Carbon Steel Loss of Structural Monitoring Program Bolts Support Material Protective Coatings Program Nonsafety Related Structural Support Anchors and Structural Inside Stainless Steel Loss of Fuel Pool Chemistry Control The original line item was Bolts Support Material modified, creating two line Demin Water items, in response to RAI 3.6-24, SNC correspondence HL-Anchors and Structural Embedded Stainless Steel Loss of Structural Monitoring Program 6002 dated October 10, 2000. Bolts Support Material Inside Miscellaneous Structural Inside Carbon Steel Loss of Structural Monitoring Program Steel Support Material Protective Coatings Program Nonsafety Related Structural Support Miscellaneous Fission Inside Stainless Steel Loss of Fuel Pool Chemistry Control The original line item was Steel Product Material modified, creating two line Barrier Demin Water items, in response to RAI 3.6-Miscellaneous Fission Embedded Stainless Steel Loss of Structural Monitoring Program 24, SNC correspondence HL-Steel Product Material 6002 dated October 10, 2000. Barrier Inside 2.5-14
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 188 of 363 Table 2.5-4 Fuel Storage [T24] - Summary of Aging Management Review Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Reinforced Structural Inside Concrete Loss of Structural Monitoring Program Concrete Support Material Carbon Steel Protective Coatings Program Shelter/Protect ion Reinforced Structural Inside Concrete Loss of Structural Monitoring Program Concrete Support Material Carbon Steel Protective Coatings Program Nonsafety Related Structural Support Seismic Structural Inside Aluminum Loss of Fuel Pool Chemistry Control restraints for Support Material spent fuel Demin Water storage racks Storage Racks Structural Inside Aluminum None None Required This line item was added in - New Fuel Support response to RAIs 3.6-20 & 24, SNC correspondence HL-6002 Nonsafety dated October 10, 2000. Related Structural Support Storage Racks Structural Inside Aluminum None None Required Support Nonsafety Related Structural Support 2.5-15
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 189 of 363 Table 2.5-4 Fuel Storage [T24] - Summary of Aging Management Review Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Structural Structural Inside Stainless Steel Loss of Fuel Pool Chemistry Control Steel Support Material Demin Water Shelter/ Protection Fission Product Barrier 2.5-16
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 190 of 363 2.5.5 Reactor Building [T29]
System Description
The purpose of the reactor building is to shelter and support the refueling and reactor servicing equipment, new and spent fuel storage facilities, and other reactor auxiliary and service equipment. The building is a reinforced concrete structure with a steel superstructure. The building consists of the following major structural components: Reinforced concrete foundation mat. Reinforced concrete exterior walls and prestressed exterior wall panels. Reinforced concrete floors with reinforced concrete beams and girders framing. Reinforced concrete interior walls with some blockouts filled with concrete masonry. Reinforced concrete roof slab on metal roof deck system supported by steel superstructure. The reactor building completely encloses the reactor and its pressure suppression primary containment system. Also housed within the reactor building are the core standby cooling systems, reactor water cleanup demineralizer system, standby liquid control system, control rod drive system, reactor protection system, and electrical equipment components. The building is designed for minimum leakage so that the standby gas treatment system (SGTS) has the necessary capacity to reduce and hold the building at a subatmospheric pressure under normal wind conditions. HNP FSAR References Additional information may be found in Unit 1 FSAR subsection 12.2.1 and Unit 2 FSAR Section 3.0. 2.5-17
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 191 of 363 Table 2.5-5 Reactor Building [T29] - Aging Management Review Results Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Anchors and Structural Inside Carbon Steel Loss of Structural Monitoring Program Bolts Support Material Outside Protective Coatings Program Nonsafety Related Structural Support Blowout Structural Inside Aluminum None None Required Panels Support Fission Product Barrier Miscellaneous Structural Inside Carbon Steel Loss of Structural Monitoring Program Steel Support Material Outside Galvanized Protective Coatings Program Nonsafety Steel Related Structural Support HE/ME Shielding 2.5-18
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 192 of 363 Table 2.5-5 Reactor Building [T29] - Aging Management Review Results Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Miscellaneous Structural Inside Stainless Steel None None Required Steel Support Outside Nonsafety Related Structural Support HE/ME Shielding Panel Joint Shelter/ Inside Elastomers; Material Structural Monitoring Program Protective Coatings Program Seals and Protection Nonmetallic, Property was removed in response to Sealants Outside Inorganic Changes RAI 3.6-27, SNC Fission correspondence HL-6002 Product Cracking dated October 10, 2000; and in Barrier response to email from R.D. Loss of Baker to W.F. Burton, dated Adhesion April 21, 2000. 2.5-19
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 193 of 363 Table 2.5-5 Reactor Building [T29] - Aging Management Review Results Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Reinforced Structural Inside Concrete Loss of Structural Monitoring Program Concrete Support Material Outside Masonry Block Protective Coatings Program Shelter/Protect Cracking ion Carbon Steel Radiation Shielding Nonsafety Related Structural Support HE/ME Shielding Missile Barrier Fission Product Barrier Flood Barrier Fire Barrier 2.5-20
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 194 of 363 Table 2.5-5 Reactor Building [T29] - Aging Management Review Results Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Structural Structural Inside Carbon Steel Loss of Structural Monitoring Program Overhead Crane and Steel Support Material Refueling Platform Inspections Outside Galvanized Protective Coatings Program added in response to email Nonsafety Steel from R.D. Baker to W.F. Related Submerged Overhead Crane and Burton, dated April 21, 2000. Structural Stainless Steel Refueling Platform Inspections Support Missile Barrier 2.5-21
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 195 of 363 2.5.6 Drywell Penetrations [T52]
System Description
The purpose of the drywell penetrations is to provide a path for cable currents/signals to pass through primary containment to support the various modes of operation of their associated systems while maintaining primary containment integrity. Mechanical penetrations are discussed in Section 2.5.3 (Primary Containment [T23]). Containment penetrations include electrical penetration assemblies in addition to the mechanical penetrations referenced above. Electrical penetrations are hermetically sealed penetrations which are welded to the primary containment shell plate. They must maintain their primary containment pressure integrity function during all postulated operating and accident conditions. They are designed for the same pressure and temperature conditions as the drywell and pressure suppression chamber. HNP FSAR References For additional information see Unit 1 FSAR Section 5.2 and Unit 2 FSAR subsection 6.2.1. 2.5-22
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 196 of 363 Table 2.5-6 Drywell Penetrations [T52] - Aging Management Review Results Structural Component Aging Management Comments Component Functions Environment Material Aging Effects Programs Structural Fission Containment Carbon Steel Loss of Protective Coatings Program Steel Product Atmosphere Material Barrier Primary Containment Leakage Embedded Rate Testing Program Inside Inservice Inspection Program 2.5-23
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 197 of 363 2.5.7 Reactor Building Penetrations [T54]
System Description
The purpose of the reactor building penetrations is to allow mechanical and electrical equipment and personnel to pass through secondary containment to support the various modes of operation of their associated systems while maintaining secondary containment integrity. Penetrations for piping and ducts are designed for leakage characteristics consistent with containment requirements for the entire building. Electrical cables and instrument leads pass through ducts sealed into the building wall. HNP FSAR References Additional information may be found in Unit 1 FSAR paragraph 5.3.3.2 and Unit 2 FSAR figure 8.3-11. 2.5-24
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 198 of 363 Table 2.5-7 Reactor Building Penetrations [T54] - Summary of Aging Management Review Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Structural Fission Embedded Carbon Steel Loss of Structural Monitoring Program Steel Product Material Barrier Inside Galvanized Protective Coatings Program Steel Outside 2.5-25
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 199 of 363 2.5.8 Turbine Building [U29]
System Description
The purpose of the turbine building is to house the turbine-generator and associated auxiliaries including the condensate and feedwater systems. The turbine building is a steel and concrete structure consisting of the following major structural components: Reinforced concrete foundation mat. Reinforced concrete floors self-supporting or supported by structural steel framing. Reinforced concrete or concrete block interior walls. Reinforced concrete turbine pedestal resting on concrete mat foundation. Reinforced concrete exterior walls. Reinforced concrete slab on metal roof deck system supported by steel framing. HNP FSAR References Additional information may be found in Unit 1 FSAR subsection 12.2.2 and Unit 2 FSAR Section 3.2. 2.5-26
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 200 of 363 Table 2.5-8 Turbine Building [U29] - Aging Management Review Results Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Anchors and Structural Embedded Carbon Steel Loss of Structural Monitoring Program Bolts Support Material Inside Galvanized Protective Coatings Program Nonsafety Steel Related Outside Structural Support Wetting Other Than Humidity Miscellaneous Structural Inside Carbon Steel Loss of Structural Monitoring Program Steel Support Galvanized Material Steel Protective Coatings Program Nonsafety Related Structural Support Reinforced Structural Buried Concrete Loss of Structural Monitoring Program Concrete Support Masonry Material Inside Carbon Steel Protective Coatings Program Shelter/Protect ion Outside Radiation Shielding Nonsafety Related Structural Support 2.5-27
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 201 of 363 Table 2.5-8 Turbine Building [U29] - Aging Management Review Results Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Structural Structural Inside Carbon Steel Loss of Structural Monitoring Program Steel Support Material Protective Coatings Program Shelter/Protect ion Nonsafety Related Structural Support 2.5-28
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 202 of 363 2.5.9 Intake Structure [W35]
System Description
The purpose of the intake structure is to protect residual heat removal service water and plant service water equipment from the influence of environmental conditions such as flooding, earthquakes, and tornadoes. The intake structure is a concrete and steel structure consisting of the following major structural components: Reinforced concrete foundation mat. Reinforced concrete exterior walls and internal walls. Reinforced concrete floors and roof. Structural steel framing and grating, steel water spray and internal missile shield barriers, stairs, and platforms. Unit 1 shares the intake structure with Unit 2. The intake structure has labyrinth access openings for protection against tornado missiles. HNP FSAR References Additional information may be found in Unit 1 FSAR subsection 12.2.7 and Unit 2 FSAR subsection 3.8.4. 2.5-29
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 203 of 363 Table 2.5-9 Intake Structure [W35] - Aging Management Review Results Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Anchors and Structural Embedded Carbon Steel Loss of Structural Monitoring Program Bolts Support Material Inside Protective Coatings Program Nonsafety Related Outside Structural Support High Humidity Wetting Other Than Humidity Miscellaneous Structural Embedded Carbon Steel Loss of Structural Monitoring Program Steel Support Material Inside Galvanized Protective Coatings Program Nonsafety Steel Related Outside Structural Support High Humidity Missile Barrier Wetting Other Than Humidity Submerged 2.5-30
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 204 of 363 Table 2.5-10 Yard Structures [Y29] - Aging Management Review Results Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Reinforced Structural Buried Concrete Loss of Structural Monitoring Program Concrete Support Material Inside Carbon Steel Protective Coatings Program Shelter/Protect ion Outside Nonsafety High Related Humidity Structural Support Wetting Other Than Missile Barrier Humidity Flood Barrier Submerged Structural Structural Embedded Carbon Steel Loss of Structural Monitoring Program Steel Support Material Inside Galvanized Protective Coatings Program Shelter/Protect Steel ion Outside Nonsafety High Related Humidity Structural Support Wetting Other Than Missile Barrier Humidity Flow Direction 2.5-31
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 205 of 363 2.5.10 Yard Structures [Y29]
System Description
The purpose of the yard structures is to provide equipment integrity and personnel habitability for various structures on the plant site. Some of the structures included in Y29 are: The concrete wall and foundation accommodating the condensate storage tank. The foundation of the nitrogen storage tank. The service water valve pit boxes. The foundation for the fire pump house. The foundations for the two fire protection water storage tanks. The foundations for the two fire protection diesel pump fuel tanks. Underground concrete duct runs and pull boxes between Class I structures. HNP FSAR References Additional information may be found in Unit 1 FSAR paragraph 5.2.3.9 and Unit 2 FSAR paragraph 3.8.5.1. 2.5-32
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 206 of 363 Table 2.5-10 Yard Structures [Y29] - Aging Management Review Results Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Anchors and Structural Inside Carbon Steel Loss of Structural Monitoring Program Bolts Support Material Outside Galvanized Protective Coatings Program Nonsafety Steel Related Structural Support Cover Plates - Shelter/Protect Inside Aluminum None None Required Pull ion Boxes Outside Flood Barrier Miscellaneous Structural Inside Carbon Steel Loss of Structural Monitoring Program Steel Support Material Outside Galvanized Protective Coatings Program Nonsafety Steel Related Structural Support Reinforced Structural Inside Concrete Loss of Structural Monitoring Program Concrete Support Material Outside Carbon Steel Protective Coatings Program Nonsafety Related Structural Support 2.5-33
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 207 of 363 Table 2.5-10 Yard Structures [Y29] - Aging Management Review Results Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Structural Structural Inside Carbon Steel Loss of Structural Monitoring Program Steel Support Material Outside Protective Coatings Program Shelter/Protect ion Nonsafety Related Structural Support 2.5-34
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 208 of 363 2.5.11 Main Stack [Y32]
System Description
The purpose of the main stack is to support and protect monitoring equipment and provide for the monitoring and elevated release of gaseous effluents from the main stack system. The main stack is a concrete cylindrical shape which consists of the following major components: Reinforced concrete foundation mat supported on steel H piles. Reinforced concrete truncated conical cylinder. Reinforced concrete internal floors. Reinforced concrete loading bay consisting of concrete base slab, external and internal walls, and roof. Unit 1 shares a single main stack used to discharge gaseous waste with Unit 2. The main stack extends 120 meters above ground level. HNP FSAR References Additional information may be found in Unit 1 FSAR subsection 5.3.4 and Unit 2 FSAR Section 11.3. 2.5-35
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 209 of 363 Table 2.5-11 Main Stack [Y32] - Aging Management Review Results Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Anchors and Structural Embedded Galvanized Loss of Structural Monitoring Program Bolts Support Steel Material Outside Protective Coatings Program Nonsafety Related Structural Support Anchors and Structural Embedded Stainless Steel None None Required Bolts Support Inside Copper Alloy Nonsafety (Bronze) Related Outside Structural Support Miscellaneous Structural Outside Galvanized Loss of Structural Monitoring Program Steel Support Steel Material Protective Coatings Program Nonsafety Related Structural Support Miscellaneous Structural Inside Galvanized None None Required Steel Support Steel Nonsafety Related Structural Support 2.5-36
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 210 of 363 Table 2.5-11 Main Stack [Y32] - Aging Management Review Results Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Reinforced Structural Inside Concrete Loss of Structural Monitoring Program Fire Barrier was added as an Concrete Support Material intended function and Masonry Outside Carbon Steel Protective Coatings Program Block added as a Material in Shelter/ Cracking response to RAI 3.4-FPS-13, Protection Masonry Block SNC correspondence HL-6002 dated October 10, 2000. Radiation Shielding Nonsafety Related Structural Support Fission Product Barrier Fire Barrier Structural Structural Inside Galvanized None None Required Steel Support Steel Nonsafety Related Structural Support 2.5-37
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 211 of 363 2.5.12 EDG Building [Y39]
System Description
The purpose of the diesel generator building is to house the emergency diesel generators (EDG) and their accessories for safe plant shutdown for both Unit 1 and Unit 2. The diesel generator building is a reinforced concrete structure consisting of the following major structural components: Reinforced concrete foundation mat. Reinforced concrete exterior walls and interior walls. Reinforced concrete roof and parapet wall. The diesel generator building houses EDGs and their accessories. The diesel generator building has labyrinth access openings for protection against tornado missiles. The diesel generator building is designed as a Seismic Category I structure to protect vital equipment and systems both during and following the most severe natural phenomena. HNP FSAR References Additional information may be found in Unit 1 FSAR subsection 12.2.6 and Unit 2 FSAR subsection 9.4.5. 2.5-38
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 212 of 363 Table 2.5-12 EDG Building [Y39] - Aging Management Review Results Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Anchors and Structural Inside Carbon Steel Loss of Structural Monitoring Program Bolts Support Material Protective Coatings Program Nonsafety Related Structural Support Miscellaneous Structural Embedded Carbon Steel Loss of Structural Monitoring Program Steel Support Material Inside Galvanized Protective Coatings Program Nonsafety Steel Related Structural Support Reinforced Structural Inside Concrete Loss of Structural Monitoring Program Concrete Support Material Outside Carbon Steel Protective Coatings Program Shelter/Protect ion Nonsafety Related Structural Support Missile Barrier 2.5-39
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 213 of 363 Table 2.5-12 EDG Building [Y39] - Aging Management Review Results Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Structural Structural Inside Carbon Steel Loss of Structural Monitoring Program Steel Support Material Protective Coatings Program Nonsafety Related Structural Support 2.5-40
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 214 of 363 2.5.13 Control Building [Z29]
System Description
The purpose of the control building is to house the common control room for Units 1 and 2 and associated auxiliaries. The building is a reinforced concrete structure with steel framing. The building consists of the following major structural components. Reinforced concrete foundation mat. Reinforced concrete floors with reinforced concrete beam and girder framing. Reinforced concrete or concrete block interior walls and reinforced concrete columns. Reinforced concrete exterior walls and prestressed exterior wall panels. Reinforced concrete slab on metal roof deck system supported by steel framing. HNP FSAR References Additional information may be found in Unit 1 FSAR paragraph 12.3.3.1.1 and Unit 2 FSAR subsection 3.2.1. 2.5-41
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 215 of 363 Table 2.5-13 Control Building [Z29] - Aging Management Review Results Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Anchors and Structural Embedded Carbon Steel Loss of Structural Monitoring Program Bolts Support Material Inside Galvanized Protective Coatings Program Nonsafety Steel Related Structural Support Blowout Structural Inside Aluminum None None Required Panels Support Fission Product Barrier Miscellaneous Structural Embedded Carbon Steel Loss of Structural Monitoring Program Steel Support Material Inside Galvanized Protective Coatings Program Nonsafety Steel Related Structural Support 2.5-42
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 216 of 363 Table 2.5-13 Control Building [Z29] - Aging Management Review Results Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Reinforced Structural Inside Concrete Loss of Structural Monitoring Program Fire Barrier was added as an Concrete Support Material intended function and Masonry Outside Carbon Steel Protective Coatings Program Block added as a Material in Shelter/ Cracking response to RAI 3.4-FPS-13, Protection Masonry Block SNC correspondence HL-6002 dated October 10, 2000. Nonsafety Related Structural Support Missile Barrier Fire Barrier Structural Structural Inside Carbon Steel Loss of Structural Monitoring Program Steel Support Material Protective Coatings Program Shelter/Protect ion Nonsafety Related Structural Support 2.5-43
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 217 of 363 2.5.14 Switchyard Structures [S48]
System Description
The purpose of the switchyard structures is to provide equipment integrity and personnel habitability for structures in the low voltage and high voltage switchyards which are required to attach the onsite AC power distribution system to the offsite power system and energize the safety-related AC buses. Some of the structures included in S48 are: The foundations of station service transformers 1C, 1D, 2C, and 2D. The foundations for structures such as 230 kV line towers, breakers, switch structures, and bus support columns. The foundation and structure of the switchhouse. Underground concrete duct runs and covers. HNP FSAR References Additional information may be found in Unit 2 FSAR paragraph 8.3. 2.5-44
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 218 of 363 Table 2.5-14 Switchyard Structures [S48] - Aging Management Review Results Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Anchors and Nonsafety Inside Carbon Steel Loss of Structural Monitoring Program Added due to LR-ISG-02 per Bolts Related Material RIS 2007-16, Rev. 1 Structural Outside Galvanized Protective Coatings Program Support Steel Embedded Cable Trays Nonsafety Inside Carbon Steel Loss of Structural Monitoring Program Added due to LR-ISG-02 per and Related Material RIS 2007-16, Rev. 1 supports Structural Outside Galvanized Protective Coatings Program Support Steel Cable Trays Nonsafety Inside Aluminum None None Required Added due to LR-ISG-02 per and Related RIS 2007-16, Rev. 1 supports Structural Outside Support Miscellaneous Nonsafety Inside Carbon Steel Loss of Structural Monitoring Program Added due to LR-ISG-02 per Steel Related Material RIS 2007-16, Rev. 1 Structural Outside Galvanized Protective Coatings Program Support Steel Reinforced Nonsafety Inside Concrete Loss of Structural Monitoring Program Added due to LR-ISG-02 per Concrete Related Material RIS 2007-16, Rev. 1 Structural Outside Carbon Steel Protective Coatings Program Support Structural Shelter/Protect Inside Carbon Steel Loss of Structural Monitoring Program Added due to LR-ISG-02 per Steel ion Material RIS 2007-16, Rev. 1 Outside Galvanized Protective Coatings Program Nonsafety Steel Related Structural Support 2.5-45
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SHEET 219 of 363 2.6 Electrical Components The Electrical Components for the Plant Hatch LRA Systems are addressed in the following sections:
- Electric Power and Instrumentation and Controls (Plant Wide), Section 2.6.1 o Analog Transmitter Trip System, Section 2.6.1(a) o Nuclear Steam Supply Shutoff System, Section 2.6.1(b) o Primary Containment Isolation System, Section 2.6.1(c) o Reactor Protection System, Section 2.6.1(d) o Remote Shutdown System, Section 2.6.1(e) o Process Radiation Monitoring System, Section 2.6.1(f) o Heat Trace System, Section 2.6.1(g) o Plant AC Electrical System, Section 2.6.1(h) o DC Electrical System, Section 2.6.1(i) o Plant Communications System, Section 2.6.1(j) o Power Transformers System, Section 2.6.1(k) o Emergency Response Facilities System, Section 2.6.1(l)
- Electrical Panels, Racks, & Cabinets, Section 2.6.2
- Instruments Racks, Panels, & Enclosures, Section 2.6.3
- Switchyard, Section 2.6.4 2.6.1 Electric Power and Instrumentation and Controls (Plant Wide)
The Electric Power and Instrumentation and Controls LRA system is comprised of several plant systems as described in Sections 2.6.1(a) - 2.6.1(l) below. Table 2.6-1 presents the electrical AMR results. The list of electrical components subject to an AMR is determined on a plantwide basis by compiling a list of all electrical component types installed in the plant, then applying the scoping and screening criteria in the Rule to determine those component types subject to an AMR. The resulting list is an encompassing list of component types, not individual components. For example, cable is listed as a component type. Individual circuits are not evaluated to determine whether they are in scope. The list of component types subject to an aging management review has been further reduced by application of the scoping criteria to the component types which meet the screening criteria. These criteria are found in 10 CFR 54.4(a). Any component type which does not meet the scoping criteria in this section on a generic basis does not require an aging management review. The comprehensive list of electrical component types is included in Table 2.6-1. 2.6-1
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SHEET 220 of 363 2.6.1(a) Analog Transmitter Trip System [A70]
System Description
The purpose of the analog transmitter trip system (ATTS) is to monitor several critical plant parameters and provide actuation and trip signals to the following systems: Reactor Protection System Primary Containment Isolation System Secondary Containment Isolation System Core Spray System Residual Heat Removal System High Pressure Coolant Injection System Reactor Core Isolation Cooling Automatic Depressurization System Low-Low Set Logic Alternate Rod Insertion Logic Reactor Recirculation System Emergency Diesel Generators Safety Relief Valves The ATTS is a solid-state electronic trip system designed to provide monitoring of process parameters. The system consists of primary sensors, master trip assemblies, slave trip assemblies, calibration units, card file assemblies, and other accessories. HNP FSAR References Additional information may be found in Unit 1 FSAR Section 7.18 and Unit 2 FSAR Section 7.8. 2.6-2
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SHEET 221 of 363 2.6.1(b) Nuclear Steam Supply Shutoff System [A71]
System Description
The purpose of the nuclear steam supply shutoff system is to isolate the reactor vessel and various other systems which carry radioactive fluids within the primary containment to prevent the release of radioactive materials. Sensor elements are located in the reactor vessel, drywell, main steam lines (MSLs), MSL pipe chase, turbine building, the reactor water cleanup (RWCU) system, and areas around the RWCU system. The system functions are initiated when sensors actuate and provide input to relay control circuits, which in turn initiate the closure of containment isolation valves and initiate various other functions. The other functions include annunciation, post accident monitoring system recorder chart speed control, control room pressurization, and signal input to the primary containment isolation system. HNP FSAR References Additional information may be found in Unit 1 FSAR subsection 7.3.4 and Unit 2 FSAR subsection 7.3.2. 2.6.1(c) Primary Containment Isolation System [C61]
System Description
The purpose of the primary containment isolation system (PCIS) is to limit fission product releases by isolating fluid systems during accident/transient conditions. The PCIS functions are initiated when sensors monitoring critical parameters activate and provide input to relay control circuits which in turn initiate closure of containment isolation valves or initiate various other functions. The other functions include initiating SGTS, isolating reactor building ventilation, isolating refueling floor ventilation, and isolating the off-gas system exhaust. HNP FSAR References Additional information may be found in Unit 1 FSAR Section 7.3 and Unit 2 FSAR subsection 7.3.2. 2.6-3
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SHEET 222 of 363 2.6.1(d) Reactor Protection System [C71]
System Description
The purpose of the reactor protection system (RPS) is to provide protection against the onset and consequences of conditions that challenge the integrity of the fuel barriers and the nuclear system process barrier by the initiation of an automatic scram. The RPS is composed of two independent, dual channel monitor/trip systems, associated process system sensors, and annunciators. The RPS is designed to initiate a reactor scram to: Preserve the integrity of fuel cladding. Preserve the integrity of the reactor coolant pressure boundary (RCPB). Minimize the energy released during a loss-of-coolant accident (LOCA). HNP FSAR References Additional information may be found in Unit 1 FSAR Section 7.2 and Unit 2 FSAR Section 7.2. 2.6.1(e) Remote Shutdown System [C82]
System Description
The remote shutdown panels provide controls and indications to safely shut down the reactor for a selected number of components in a selected number of systems in the event the control room becomes uninhabitable. 2.6.1(f) Process Radiation Monitoring System [D11]
System Description
The purpose of the process radiation monitoring system is to provide input into the reactor protection system, primary containment isolation system, and others for system isolation. HNP FSAR References More information on this system can be found in Unit 1 FSAR Section 7.12 and Unit 2 FSAR Section 11.4. 2.6-4
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SHEET 223 of 363 2.6.1(g) Heat Trace System [G13]
System Description
The purpose of the heat trace system is to maintain piping, instrumentation, and equipment in working order during below freezing temperatures. A primary function is to maintain the sodium pentaborate solution in the standby liquid control system at a temperature high enough to prevent precipitation and solidification of the solution. Standby liquid control storage tank temperature is maintained by adjusting the storage tank heater-indicating controller to maintain temperature control and prevent precipitation of the sodium pentaborate from solution. Thermostat controlled heat tracing is run along the pump suction piping to maintain suction piping solution temperature. A temperature versus concentration curve is monitored to ensure that sufficient margin will be maintained above saturation temperature. HNP FSAR References Additional information may be found in Unit 2 FSAR paragraph 4.2.3.4.2. 2.6.1(h) Plant AC Electrical System [R20]
System Description
The entire auxiliary power distribution system, station service, and emergency service systems consisting of both 1E and Non-1E systems, distribute power to all ac auxiliaries required to startup, operate, and shut down the plant. The emergency service portion Class 1E distributes power to all loads essential to plant safety and normal plant operation ensuring power is available to perform a safe plant shutdown. The auxiliary power distribution system distributes power to all auxiliaries necessary for normal plant operation. The station auxiliary ac power system is divided into two portions: one for normal Non-Class 1E service and one for emergency Class 1E service. The emergency service portion distributes ac power required to shut down the reactor, maintain the shutdown condition, and operate all safety-related equipment necessary to mitigate the consequences of major accident conditions. The entire station auxiliary ac power system, both normal and emergency service portions, distributes power to all ac auxiliaries required to start up, operate, and shut down the plant. HNP FSAR References 2.6-5
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SHEET 224 of 363 Additional information may be found in Unit 1 FSAR Sections 8.3 and 8.7 and Unit 2 FSAR subsection 8.3.1. 2.6-6
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SHEET 225 of 363 2.6.1(i) DC Electrical System [R42]
System Description
The purpose of the dc distribution system is to provide reliable power from a rectified ac source (battery charger) with a battery backup to supply dc loads, control power, logic power, and inverters for all operational modes. The battery system provides an uninterruptible source of power to normal Non-Class 1E and emergency Class 1E loads such as motors, circuit breaker controls, operation of logic and control relays, emergency lighting, etc. The emergency power is required to safely shutdown the reactor, maintain the reactor in a shutdown condition, and operate all auxiliaries necessary for plant safety under all plant operational modes. The dc electrical system includes the following: 125/250 V station battery system Class 1E 125 V diesel generator battery system Class 1E 125 V cooling tower battery system Non-Class 1E 24/48 V instrumentation battery system Non-Class 1E Battery for 120/240 V vital ac system Non-Class 1E HNP FSAR References Additional information may be found in Unit 1 FSAR Section 8.5 and Unit 2 FSAR subsection 8.3.2. 2.6-7
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SHEET 226 of 363 2.6.1(j) Plant Communications System [R51]
System Description
The purpose of the plant communications system is to allow key personnel to communicate information about plant conditions and other pertinent information. The intrasite communication system consists of a public address system; a private, dial telephone system; and a two-way radio communication system provided for paging and communication. The public address system which consists of handsets, amplifiers, loudspeakers, multi-tone generator, and associated equipment provides convenient, effective paging, and private conversational service. The private, automatic exchange dial telephone system is an electronic system of modular design utilizing stored program control and time division switching. A separate, two-way radio communication is provided to permit communication with mobile units and base stations within the range of the plant. HNP FSAR References Additional information may be found in Unit 1 FSAR Section 10.15 and Unit 2 FSAR subsection 9.5.2. 2.6.1(k) Power Transformers System [S11]
System Description
The in scope components for this system are the CD transformers. The function of these transformers is to provide power to 600V busses C or D from 4160V bus F during station blackout. The transformers operate by dropping the voltage from 4160 volts to 600 volts. HNP FSAR References Additional information may be found in Unit 1 FSAR Section 8.3 and Unit 2 FSAR Section 8.3. 2.6-8
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SHEET 227 of 363 2.6.1(l) Emergency Response Facilities System [X75]
System Description
The purpose of the emergency response facilities is to help the plant operators, shift technical advisors, supervisory personnel, and the NRC in rapidly assessing the plant safety status during normal, transient, and accident conditions. The NRC-emergency response data system (NRC-ERDS) is the response to the ERDS Rule published in 10 CFR 50 in 1991. It is used during an Alert emergency classification or higher to transmit certain data to the NRC operations center in Rockville, Maryland. The X75 system includes the safety parameter display system (SPDS), the technical support center (TSC) HVAC system, and the ERDS. HNP FSAR References For additional information see Unit 1 FSAR Section 7.21 and Unit 2 FSAR Section 7.9. 2.6-9
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SHEET 228 of 363 This Page Intentionally Left Blank. 2.6-10
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SHEET 229 of 363 Table 2.6-1 Electrical Components [Plant Wide] - Aging Management Review Results Electrical Intended Aging Management Component Function Environment Material Aging Effects Programs Comments Cable Provide Inside Various Change in Wetted Cable Activities The Insulated Cables and (Outside insulation Polymers Insulation Connections Program was Containment) resistance to Outside Resistance Insulated Cables and added to this line item in preclude Tinned and Connections Program response to Draft Open Item shorts, Submerged Bare Copper 51 (3.7.2.2-2), SNC grounds, and correspondence HL-6037, unacceptable dated January 31, 2001. leakage currents Cable (Inside Provide Inside Various None Insulated Cables and The Insulated Cables and Containment) insulation Polymers Connections Program Connections Program was resistance to added to this line item in preclude Tinned and response to Draft Open Item shorts, Bare Copper 51 (3.7.2.2-2), SNC grounds, and correspondence HL-6037, unacceptable dated January 31, 2001. leakage currents Electrical Provide Inside Various None None Connectors insulation Polymers Splices, resistance to Outside Terminal preclude Galvanized Blocks shorts, and Stainless grounds, and Steel unacceptable leakage Tinned and currents Bare Copper 2.6-10
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SHEET 230 of 363 Table 2.6-1 Electrical Components [Plant Wide] - Aging Management Review Results Electrical Intended Aging Management Component Function Environment Material Aging Effects Programs Comments Electrical Provide Inside Various None None Penetration insulation Polymers Assemblies resistance to (Penetration assemblies are preclude Painted Steel covered by an EQ TLAA.) shorts, grounds, and Stainless Steel unacceptable leakage currents Phase Provide Inside Various None None Bussing insulation Polymers resistance to preclude Galvanized shorts, and Stainless grounds, and Steel unacceptable leakage Tinned and currents Bare Copper Nelson Fission Inside Various None None Frames Product Polymers Barrier Galvanized Fire Protection and Painted Steel 2.6-11
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SHEET 231 of 363 2.6.2 Electrical Panels, Racks, & Cabinets [H11]
System Description
The purpose of the main control boards is to provide display, recording, and alarm to enable plant operators to monitor and control the equipment necessary for normal operations and transient/accident mitigation. H11 as described in this Specification includes only the supporting panels, racks, and cabinets. HNP FSAR References Additional information may be found in Unit 1 FSAR Section 7.16 and Unit 2 FSAR Section 3.2. 2.6-12
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SHEET 232 of 363 Table 2.6-2 Electrical Panels, Racks, & Cabinets [H11] - Aging Management Review Results Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Electrical Structural Inside Carbon Steel Loss of Structural Monitoring Program panels, racks Support Material and cabinets Protective Coatings Program Shelter/Protect ion Nonsafety Related Structural Support 2.6-13
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SHEET 233 of 363 2.6.3 Instrument Racks, Panels, & Enclosures [H21]
System Description
The purpose of the auxiliary control panels is to provide system information and control to allow operators to operate equipment from outside the main control room (MCR) in the reactor building, turbine building, and other auxiliary buildings. The actual controls for each system are included in specific functions for the respective system. HNP FSAR References Additional information may be found in Unit 1 FSAR Section 7.16 and Unit 2 FSAR Section 3.10. 2.6-14
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SHEET 234 of 363 Table 2.6-3 Instrument Racks, Panels, & Enclosures [H21] - Aging Management Review Results Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Instrument Structural Inside Carbon Steel Loss of Structural Monitoring Program racks, Support Material panels and Protective Coatings Program enclosures Nonsafety Related Structural Support 2.6-15
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SHEET 235 of 363 2.6.4 Switchyard [S40]
System Description
The high voltage switchyard consists of two sections, a 500 kV switchyard and a 230 kV switchyard. A 500/230 kV autotransformer connects the 500 kV switchyard to the 230 kV switchyard. The transmission network interconnections at HNP consist of four 500 kV lines and four 230 kV lines. The low voltage (24 kV) switchyard contains one main transformer for each unit, unit auxiliary transformers 1A, 1B, 2A, and 2B, and startup auxiliary transformers 1C, 1D, 2C, and 2D. Offsite power is supplied from the high voltage switchyard to the startup auxiliary transformers via three physically independent 230 kV circuits. The startup auxiliary transformers then supply power to the safety related portion of the onsite distribution system. A switchhouse containing relaying and controls is provided in the high voltage switchyard. This section has been added in response to the 10 CFR 54.37(b) review of NRC Regulatory Issue Summary (RIS) 2007-16, Revision 1, relating to LR-ISG-02 concerning recovery from a station blackout (SBO) event. HNP FSAR References Additional information may be found in Unit 2 FSAR Section 8.2. 2.6-16
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SHEET 236 of 363 Table 2.6-4 Switchyard [S40] - Aging Management Review Results Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Cable Provide Various Change in Wetted Cable Activities Added in response to the Inside (Outside insulation Polymers Insulation 10 CFR 54.37(b) review of Containment) resistance to Outside Resistance Insulated Cables and NRC Regulatory Issue preclude Tinned and Connections Program Summary (RIS) 2007-16, shorts, Bare Copper Revision 1, relating to LR-ISG-grounds, and 02 concerning recovery from a unacceptable station blackout (SBO) event. leakage currents Electrical Provide Various None None Added in response to the Inside Connectors, insulation Polymers 10 CFR 54.37(b) review of Splices, resistance to Outside NRC Regulatory Issue Terminal preclude Galvanized Summary (RIS) 2007-16, Blocks shorts, and Stainless Revision 1, relating to LR-ISG-grounds, and Steel 02 concerning recovery from a unacceptable station blackout (SBO) event. leakage Tinned and currents Bare Copper High-Voltage Insulate and Outside Porcelain, None None Added in response to the Insulators support an Malleable Iron, 10 CFR 54.37(b) review of electrical Galvanized NRC Regulatory Issue conductor Steel, Cement Summary (RIS) 2007-16, Revision 1, relating to LR-ISG-02 concerning recovery from a station blackout (SBO) event. Instrument Structural Inside Carbon Steel Loss of Structural Monitoring Program Added in response to the racks, Support Material 10 CFR 54.37(b) review of panels and Protective Coatings Program NRC Regulatory Issue enclosures Nonsafety Summary (RIS) 2007-16, Related Revision 1, relating to LR-ISG-Structural 02 concerning recovery from a Support station blackout (SBO) event. 2.6-17
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SHEET 237 of 363 Structural Intended Aging Management Component Functions Environment Material Aging Effects Programs Comments Switchyard Provide Outside Aluminum, None None Added in response to the Bus and Electrical Copper, 10 CFR 54.37(b) review of Connections Connections Bronze, NRC Regulatory Issue Stainless Summary (RIS) 2007-16, Steel, Revision 1, relating to LR-ISG-Galvanized 02 concerning recovery from a Steel station blackout (SBO) event. Transmission Provide Outside Aluminum, None None Added in response to the Conductors Electrical Steel 10 CFR 54.37(b) review of and Connections NRC Regulatory Issue Connections Summary (RIS) 2007-16, Revision 1, relating to LR-ISG-02 concerning recovery from a station blackout (SBO) event. 2.6-18
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SHEET 238 of 363 3 REFERENCES 3.1 Edwin I. Hatch License Renewal Docket 3.1.1 SNC Letter HL-5853, Edwin I. Hatch Nuclear Plant Units 1 and 2, Application for License Renewal, dated February29, 2003. 3.1.2 SNC Letter HL-5979, Edwin I. Hatch Nuclear Plant Units 1 and 2, Response to License Renewal Requests for Additional Information, dated August 29, 2000. 3.1.3 SNC Letter HL-6002, Edwin I. Hatch Nuclear Plant Units 1 and 2, Response to License Renewal Requests for Additional Information, dated October 10, 2000. 3.1.4 SNC Letter HL-6024, Edwin I. Hatch Nuclear Plant Units 1 and 2, Annual Update of License Renewal Application, dated December 15, 2000. 3.1.5 SNC Letter HL-6037, Edwin I. Hatch Nuclear Plant, Transmittal of Responses to License Renewal Draft Open Items, dated January 31, 2001. 3.1.6 SNC Letter HL-6092, Edwin I. Hatch Nuclear Plant Units 1 and 2, License Renewal Draft SER Open Items, dated June 5, 2001. 3.1.7 SNC Letter HL-6123, Edwin I. Hatch Nuclear Plant Units 1 and 2, Transmittal of Additional Information for License Renewal Draft Safety Evaluation Report Open Items, dated September 5, 2001. 3.1.8 SNC Emails from R.D. Baker to W.F.Burton, dated April 21, 2000 through October 13, 2001 (Attachment C). 3.1.9 E.I. Hatch Final Safety Analysis Report, Chapter 18. 3.2 NRC References 3.2.1 10 CFR 54, The License Renewal Rule. 3.2.2 NUREG 1803, Rev. 1; Safety Evaluation Related to the License Renewal of the Edwin I. Hatch Nuclear Plant, Units 1 and 2. 3.2.3 RIS 2007-16, Revision 1: Implementation of the Requirements of 10 CFR 54.37(b) for Holders of Renewed Licenses 3.3 Other References 3.3.1 NMP-ES-063, License Renewal Program 3.3.2 NMP-ES-063-001, License Renewal Program Implementation Instructions 3.3.3 NMP-ES-063-003, 10 CFR 54.37(b) Review Instructions 3.3.4 NMP-ES-063-003-F01, 10 CFR 54.37(b) Review Form 3.3.5 NMP-ES-063-004, 10 CFR 54.37(b) Scoping Determination Instructions 3-1
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SHEET 239 of 363 3.3.6 NMP-ES-063-004-F01, 10 CFR 54.37(b) Scoping Determination Form 3.3.7 NMP-ES-063-005, 10 CFR 54.37(b) Commodity Evaluation Instructions 3.3.8 NMP-ES-063-005-F01, 10 CFR 54.37(b) Commodity Evaluation Form 3.3.9 NMP-ES-063-006, 10 CFR 54.37(b) Aging Management Review Evaluation Instructions 3.3.10 NMP-ES-063-006-F01, 10 CFR 54.37(b) AMR Evaluation Form 3.3.11 NMP-ES-063-007, 10 CFR 54.37(b) TLAA Evaluation Instructions 3.3.12 NMP-ES-063-007-F01, 10 CFR 54.37(b) TLAA Evaluation Form 3.3.13 NMP-ES-063-GL01, Hatch License Renewal Program Manual 3.3.14 NEI 95-10, Revision 6, Guidelines for Implementing the Requirements of 10 CFR Part 54 - The License Renewal Rule. 3-2
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SHEET 240 of 363 Attachment A 10 Program Elements (Excerpted from Appendix A to NUREG-1800) A.1.2.3 Aging Management Program Elements A.1.2.3.1 Scope of Program The specific program necessary for license renewal should be identified. The scope of the program should include the specific structures and components, the aging of which the program manages. A.1.2.3.2 Preventive Actions
- 1. The activities for prevention and mitigation programs should be described. These actions should mitigate or prevent aging degradation.
- 2. Some condition or performance monitoring programs do not rely on preventive actions and thus, this information need not be provided.
- 3. In some cases, condition or performance monitoring programs may also rely on preventive actions. The specific prevention activities should be specified.
A.1.2.3.3 Parameters Monitored or Inspected
- 1. This program element should identify the aging effects that the program manages and should provide a link between the parameter or parameters that will be monitored and how the monitoring of these parameters will ensure adequate aging management.
- 2. For a condition monitoring program, the parameter monitored or inspected should be capable of detecting the presence and extent of aging effects. Some examples are measurements of wall thickness and detection and sizing of cracks.
- 3. For a performance monitoring program, a link should be established between the degradation of the particular structure or component-intended function(s) and the parameter(s) being monitored. An example of linking the degradation of a passive component-intended function with the performance being monitored is linking the fouling of heat exchanger tubes with the heat transfer-intended function. This could be monitored by periodic heat balances. Since this example deals only with one intended function of the tubes (heat transfer), additional programs may be necessary to manage other intended function(s) of the tubes, such as pressure boundary. Thus, a performance monitoring program must ensure that the structure and components are capable of performing their intended functions by using a combination of performance monitoring and evaluation (if outside acceptable limits of acceptance criteria) that demonstrate that a change in performance characteristic is a result of an age-related degradation mechanism.
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- 4. For prevention or mitigation programs, the parameters monitored should be the specific parameters being controlled to achieve prevention or mitigation of aging effects. An example is the coolant oxygen level that is being controlled in a water chemistry program to mitigate pipe cracking.
A.1.2.3.4 Detection of Aging Effects
- 1. Detection of aging effects should occur before there is a loss of the structure- and component-intended function(s). The parameters to be monitored or inspected should be appropriate to ensure that the structure- and component-intended function(s) will be adequately maintained for license renewal under all CLB design conditions. Thus, the discussion for the detection of aging effects program element should address (a) how the program element would be capable of detecting or identifying the occurrence of age-related degradation or an aging effect prior to a loss of structure and component (SC)-
intended function or (b) for preventive/mitigative programs, how the program would be capable of preventing or mitigating their occurrence prior to a loss of a SC-intended function. The discussion should provide information that links the parameters to be monitored or inspected to the aging effects being managed.
- 2. Nuclear power plants are licensed based on redundancy, diversity, and defense-in-depth principles. A degraded or failed component reduces the reliability of the system, challenges safety systems, and contributes to plant risk. Thus, the effects of aging on a structure or component should be managed to ensure its availability to perform its intended function(s) as designed when called upon. In this way, all system level-intended function(s), including redundancy, diversity, and defense-in-depth consistent with the plants CLB, would be maintained for license renewal. A program based solely on detecting structure and component failure should not be considered as an effective AMP for license renewal.
- 3. This program element describes when, where, and how program data are collected (i.e., all aspects of activities to collect data as part of the program).
- 4. For condition monitoring programs, the method or technique (such as visual, volumetric, or surface inspection), frequency, and timing of new, one-time inspections may be linked to plant-specific or industry-wide operating experience. The discussion should provide justification, including codes and standards referenced, that the technique and frequency are adequate to detect the aging effects before a loss of SC-intended function. A program based solely on detecting SC failures is not considered an effective AMP.
For a condition monitoring program, when sampling is used to represent a larger population of SCs, applicants should provide the basis for the inspection population and sample size. The inspection population should be based on such aspects of the SCs as a similarity of materials of construction, fabrication, procurement, design, installation, operating environment, or aging effects. The sample size should be based on such aspects of the SCs as the specific aging effect, location, existing technical information, system and structure design, materials of construction, service environment, or previous failure history. The samples should be biased toward locations most susceptible to the specific aging effect of concern in the period of extended operation. Provisions on expanding the sample size when degradation is detected in the initial sample should also be included.
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- 5. For a performance monitoring program, the detection of aging effects program element should discuss and establish the monitoring methods that will be used for performance monitoring. In addition, the detection of aging effects program element should also establish and justify the frequency that will be used to implement these performance monitoring activities.
- 1. For a prevention or mitigation program, the detection of aging effects program element should discuss and establish the monitoring methods that the program will use to monitor for the preventive or mitigative parameters that the program controls and should justify the frequency of performing these monitoring activities.
A.1.2.3.5 Monitoring and Trending
- 1. Monitoring and trending activities should be described, and they should provide a prediction of the extent of degradation and thus effect timely corrective or mitigative actions. Plant-specific and/or industrywideoperating experience may be considered in evaluating the ppropriateness of the technique and frequency.
- 2. This program element describes how the data collected are evaluated and may also include trending for a forward look. This includes an evaluation of the results against the acceptance criteria and a prediction regarding the rate of degradation in order to confirm that timing of the next scheduled inspection will occur before a loss of SC-intended function. Although aging indicators may be quantitative or qualitative, aging indicators should be quantified, to the extent possible, to allow trending. The parameter or indicator trended should be described. The methodology for analyzing the inspection or test results against the acceptance criteria should be described. Trending is a comparison of the current monitoring results with previous monitoring results in order to make predictions for the future.
A.1.2.3.6 Acceptance Criteria
- 1. The quantitative or qualitative acceptance criteria of the program and its basis should be described. The acceptance criteria, against which the need for corrective actions are evaluated, should ensure that the structure- and component-intended function(s) are maintained consistent with all CLB design conditions during the period of extended operation. The program should include a methodology for analyzing the results against applicable acceptance criteria.
For example, carbon steel pipe wall thinning may occur under certain conditions due to FAC. An AMP for FAC may consist of periodically measuring the pipe wall thickness and comparing that to a specific minimum wall acceptance criterion. Corrective action is taken, such as piping replacement, before deadweight, seismic, and other loads, and this acceptance criterion must be appropriate to ensure that the thinned piping would be able to carry these CLB design loads. This acceptance criterion should provide for timely corrective action before loss of intended function under these CLB design loads.
- 2. Acceptance criteria could be specific numerical values, or could consist of a discussion of the process for calculating specific numerical values of conditional acceptance criteria
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SHEET 243 of 363 to ensure that the structure- and component-intended function(s) will be maintained under all CLB design conditions. Information from available references may be cited.
- 2. It is not necessary to justify any acceptance criteria taken directly from the design basis information that is included in either the final safety analysis report (FSAR), plant Technical Specifications, or other codes and standards incorporated by reference into NRC regulations; they are a part of the CLB. Nor is it necessary to justify the acceptance criteria that have been established in either NRC-accepted or NRC-endorsed methodology, such as those that may be given in NRC-approved or NRC-endorsed topical reports or NRC-endorsed codes and standards; the acceptance criteria referenced in these types of documents have been subject to an NRC review process and have been approved or endorsed for their application to an NRC-approved or NRC endorsed evaluation methodology. Also, it is not necessary to discuss CLB design loads if the acceptance criteria do not permit degradation because a structure and component without degradation should continue to function as originally designed. Acceptance criteria, which do permit degradation, are based on maintaining the intended function under all CLB design loads.
A.1.2.3.7 Corrective Actions
- 1. Actions to be taken when the acceptance criteria are not met should be described in appropriate detail or referenced to source documents. Corrective actions, including root cause determination and prevention of recurrence, should be timely.
- 3. If corrective actions permit analysis without repair or replacement, the analysis should ensure that the structure- and component-intended function(s) are maintained consistent with the CLB.
- 4. For safety-related components, an applicants 10 CFR Part 50, Appendix B, Quality Assurance Program, is an acceptable means to confirm that the corrective actions are done in a manner consistent with the condition monitoring program, preventive program, mitigative program, or performance monitoring program that is credited for aging management. For example, for a plant-specific condition monitoring program that is based on ASME Section XI requirements, the implementation of the Appendix B program should ensure that any corrective actions are performed in accordance with applicable Code requirements or NRC-approved Code cases.
A.1.2.3.8 Confirmation Process
- 1. The confirmation process should be described. The process ensures that preventive actions are adequate and that appropriate corrective actions have been completed and are effective.
- 2. The effectiveness of prevention and mitigation programs should be verified periodically.
For example, in managing internal corrosion of piping, a mitigation program (water chemistry) may be used to minimize susceptibility to corrosion. However, it also may be necessary to have a condition monitoring program (ultrasonic inspection) to verify that corrosion is indeed insignificant.
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SHEET 244 of 363
- 3. When corrective actions are necessary, there should be follow-up activities to confirm that the corrective actions have been completed, a root cause determination was performed, and recurrence will be prevented.
A.1.2.3.9 Administrative Controls
- 1. The administrative controls of the program should be described. Administrative controls provide a formal review and approval process.
- 2. Any AMPs to be relied on for license renewal should have regulatory and administrative controls. That is the basis for 10 CFR 54.21(d) to require that the FSAR supplement include a summary description of the programs and activities for managing the effects of aging for license renewal. Thus, any informal programs relied on to manage aging for license renewal must be administratively controlled and included in the FSAR supplement.
A.1.2.3.10 Operating experience
- 1. Consideration of future plant-specific and industry operating experience relating to aging management programs should be discussed. Reviews of operating experience by the applicant in the future may identify areas where aging management programs should be enhanced or new programs developed. An applicant should commit to a future review of plant-specific and industry operating experience to confirm the effectiveness of its aging management programs or indicate a need to develop new aging management programs.
This information should provide objective evidence to support the conclusion that the effects of aging will be managed adequately so that the structure and component intended function(s) will be maintained during the period of extended operation.
- 2. Operating experience with existing programs should be discussed. The operating experience of AMPs that are existing programs, including past corrective actions resulting in program enhancements or additional programs, should be considered. A past failure would not necessarily invalidate an AMP because the feedback from operating experience should have resulted in appropriate program enhancements or new programs. This information can show where an existing program has succeeded and where it has failed (if at all) in intercepting aging degradation in a timely manner.
This information should provide objective evidence to support the conclusion that the effects of aging will be managed adequately so that the structure- and component-intended function(s) will be maintained during the period of extended operation.
- 3. For new AMPs that have yet to be implemented at an applicants facility, the programs have not yet generated any operating experience (OE). However, there may be other relevant plant-specific OE at the plant or generic OE in the industry that is relevant to the AMPs program elements even though the OE was not identified as a result of the implementation of the new program. Thus, for new programs, an applicant may need to consider the impact of relevant OE that results from the past implementation of its existing AMPs that are existing programs and the impact of relevant generic OE on developing the program elements. Therefore, operating experience applicable to new programs should be discussed. Additionally, an applicant should commit to a review of future plant-specific and industry operating experience for new programs to confirm their effectiveness.
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SHEET 245 of NEI 95-10 363 Revision 6 June 2005 APPENDIX B TYPICAL STRUCTURE, COMPONENT AND COMMODITY GROUPINGS AND ACTIVE/PASSIVE DETERMINATIONS FOR THE INTEGRATED PLANT ASSESSMENT B-1
A-47039 LICENSOifYP~*~#~~~6MP~~~~cRWili>1~ ofNEI 95-10 Revision 6 AND ACTIVE/PASSIVE DETERMINATIONS FOR THE June 2005 INTEGRATED PLANT ASSESSMENT ITEM CATEGORY STRUCTURE , COMPONENT, OR STRUCTURE, COMMODITY GROUPING COMPONENT, OR COMMODITY GROUPING MEETS 10CFR54.21(a)(l)(i) (YES/NO) Category I Structures Yes 1 Structures Note: If a da m is included in this category-see Appendix C, Reference 4 for guidance on an acceptable aging management program. Primary Containment Structure Yes 2 Structures Intake Structures Yes 3 Structures Intake Canal Yes 4 Structures Other Non-Category I Structures Within the Yes 5 Structures Scope of License Renewal Note: If a dam is included in this category-see Appendix C, Reference 4 for guidance on an acceptable aging management program Equipment Supports and Foundations Yes 6 Structures Structural Bellows Yes 7 Structures Controlled Leakage Doors Yes 8 Structures Penetration Seals Yes 9 Structures B-2
A-47039 LICENSETYPICAL RENEWAL AGING MANAGEMENT STRUCTURE, COMPONENTREVIEW
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GROUPINGS AND COMMODITY SHEET 247 of NEI 363 95-10 Revision 6 AND ACTIVE/PASSIVE DETERMINATIONS FOR THE June 2005 INTEGRATED PLANT ASSESSMENT ITEM CATEGORY STRUCTURE, COMPONENT, OR STRUCTURE, COMMODITY GROUPING COMPONENT, OR COMMODITY GROUPING MEETS 10CFR54.21(a)(1)(i) (YES/NO) Compressible Joints and Seals Yes 10 Structures Fuel Pool and Sump Liners Yes 11 Structures Concrete Curbs Yes 12 Structures Offgas Stack and Flue Yes 13 Structures Fire Barriers Yes 14 Structures Pipe Whip Restraints and Jet Impingement Yes 15 Structures Shields Electrical and Instrumentation and Control Yes 16 Structures Penetration Assemblies Instrumentation Racks, Frames, Panels, and Yes 17 Structures Enclosures Electrical Panels, Racks, Cabinets, and Yes 18 Structures Other Enclosures B-3
A-47039 LICENSETYPICAL RENEWAL AGING MANAGEMENT STRUCTURE, COMPONENTREVIEW
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GROUPINGS AND COMMODITY SHEET 248 of NEI 363 95-10 Revision 6 AND ACTIVE/PASSIVE DETERMINATIONS FOR THE June 2005 INTEGRATED PLANT ASSESSMENT ITEM CATEGORY STRUCTURE, COMPONENT, OR STRUCTURE, COMMODITY GROUPING COMPONENT, OR COMMODITY GROUPING MEETS 10CFR54.21(a)(1)(i) (YES/NO) Cable Trays and Supports Yes 19 Structures Conduit Yes 20 Structures Tube Track Yes 21 Structures Reactor Vessel Internals Yes 22 Structures ASME Class 1 Hangers and Supports Yes 23 Structures Non-ASME Class 1 Hangers and Supports Yes 24 Structures Snubbers No 25 Structures Reactor Coolant ASME Class 1 Piping Yes 26 Pressure Boundary Components (Note: the components of the RCPB are defined by each plant's CLB and site specific documentation. B-4
A-47039 LICENSETYPICAL RENEWAL AGING MANAGEMENT STRUCTURE, COMPONENTREVIEW
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GROUPINGS AND COMMODITY SHEET 249 of NEI 363 95-10 Revision 6 AND ACTIVE/PASSIVE DETERMINATIONS FOR THE June 2005 INTEGRATED PLANT ASSESSMENT ITEM CATEGORY STRUCTURE, COMPONENT, OR STRUCTURE, COMMODITY GROUPING COMPONENT, OR COMMODITY GROUPING MEETS 10CFR54.21(a)(1)(i) (YES/NO) Reactor Vessel Yes 27 Reactor Coolant Pressure Boundary Components Reactor Coolant Pumps Yes (Casing) 28 Reactor Coolant Pressure Boundary Components Control Rod Drives No 29 Reactor Coolant Pressure Boundary Components Control Rod Drive Housing Yes 30 Reactor Coolant Pressure Boundary Components Steam Generators Yes 31 Reactor Coolant Pressure Boundary Components Pressurizers Yes 32 Reactor Coolant Pressure Boundary Components Underground Piping Yes 33 Non-Class I Piping Components Piping in Low Temperature Demineralized Yes 34 Non-Class I Water Service Piping Components Piping in High Temperature Single Phase Yes 35 Non-Class I Service Piping Components B-5
A-47039 LICENSOifYP~*~#~~~6MP~~~~cRWili>1~ ofNEI 95-10 Revision 6 AND ACTIVE/PASSIVE DETERMINATIONS FOR THE J une 2005 INTEGRATED PLANT ASSESSMENT ITEM CATEGORY STRUCTURE , COMPONENT, OR STRUCTURE, COMMODITY GROUPING COMPONENT, OR COMMODITY GROUPING MEETS 10CFR54.21(a)(l )(i) (YES/NO) Reactor Vessel Yes 27 Reactor Coolant Pressure Boundary Compon ents Reactor Coolan t Pumps Yes (Casing) 28 Reactor Coolant Pressure Boundary Compon en ts Control Rod Drives No 29 Reactor Coolant Pressure Boundary Compon en ts Control Rod Drive Hou sing Yes 30 Reactor Coolant Pressure Boundary Compon en ts Steam Gen erators Yes 31 Reactor Coolant Pressure Boundary Compon en ts Pressurizers Yes 32 Reactor Coolant Pressure Boundary Compon en ts Underground Piping Yes 33 Non- Class I Piping Compon ents Piping in Low Temperature Demin eralized Yes 34 Non- Class I Water Ser vice Piping Compon ents Piping in High Temperature Single Phase Yes 35 Non- Class I Service Piping Compon ents B-5
A-47039 LICENSETYPICAL RENEWAL AGING MANAGEMENT STRUCTURE, COMPONENTREVIEW
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GROUPINGS AND COMMODITY SHEET 251 of NEI 363 95-10 Revision 6 AND ACTIVE/PASSIVE DETERMINATIONS FOR THE June 2005 INTEGRATED PLANT ASSESSMENT ITEM CATEGORY STRUCTURE, COMPONENT, OR STRUCTURE, COMMODITY GROUPING COMPONENT, OR COMMODITY GROUPING MEETS 10CFR54.21(a)(1)(i) (YES/NO) ECCS Pumps Yes (Casing) 45 Pumps Service Water and Fire Pumps Yes (Casing) 46 Pumps Lube Oil and Closed Cooling Water Pumps Yes (Casing) 47 Pumps Condensate Pumps Yes (Casing) 48 Pumps Borated Water Pumps Yes (Casing) 49 Pumps Emergency Service Water Pumps Yes (Casing) 50 Pumps Submersible Pumps Yes (Casing) 51 Pumps Turbine Pump Drives (excluding pumps) Yes (Casing) 52 Turbines Gas Turbines Yes (Casing) 53 Turbines B-7
A-47039 LICENSETYPICAL RENEWAL AGING MANAGEMENT STRUCTURE, COMPONENTREVIEW
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GROUPINGS AND COMMODITY SHEET 252 of NEI 363 95-10 Revision 6 AND ACTIVE/PASSIVE DETERMINATIONS FOR THE June 2005 INTEGRATED PLANT ASSESSMENT ITEM CATEGORY STRUCTURE, COMPONENT, OR STRUCTURE, COMMODITY GROUPING COMPONENT, OR COMMODITY GROUPING MEETS 10CFR54.21(a)(1)(i) (YES/NO) Controls (Actuator and Overspeed Trip) No 54 Turbines Fire Pump Diesel Engines No 55 Engines Emergency Diesel Generators No 56 Emergency Diesel Generators Condensers Yes 57 Heat Exchangers HVAC Coolers (including housings) Yes 58 Heat Exchangers Primary Water System Heat Exchangers Yes 59 Heat Exchangers Treated Water System Heat Exchangers Yes 60 Heat Exchangers Closed Cooling Water System Heat Yes 61 Heat Exchangers Exchangers Lubricating Oil System Heat Exchangers Yes 62 Heat Exchangers B-8
A-47039 LICENSETYPICAL RENEWAL AGING MANAGEMENT STRUCTURE, COMPONENTREVIEW
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GROUPINGS AND COMMODITY SHEET 253 of NEI 363 95-10 Revision 6 AND ACTIVE/PASSIVE DETERMINATIONS FOR THE June 2005 INTEGRATED PLANT ASSESSMENT ITEM CATEGORY STRUCTURE, COMPONENT, OR STRUCTURE, COMMODITY GROUPING COMPONENT, OR COMMODITY GROUPING MEETS 10CFR54.21(a)(1)(i) (YES/NO) Raw Water System Heat Exchangers Yes 63 Heat Exchangers Containment Atmospheric System Heat Yes 64 Heat Exchangers Exchangers Gland Seal Blower No 65 Miscellaneous Process Components Recombiners The applicant shall 66 Miscellaneous identify the intended Process function and apply the Components IPA process to determine if the grouping is active or passive. Flexible Connectors Yes 67 Miscellaneous Process Components Strainers Yes 68 Miscellaneous Process Components Rupture Disks Yes 69 Miscellaneous Process Components Steam Traps Yes 70 Miscellaneous Process Components Restricting Orifices Yes 71 Miscellaneous Process Components B-9
A-47039 LICENSOifYP~*~#~~~6MP~~~~cRWili>1~ ofNEI 95-10 Revision 6 AND ACTIVE/PASSIVE DETERMINATIONS FOR THE June 2005 INTEGRATED PLANT ASSESSMENT ITEM CATEGORY STRUCTURE , COMPONENT, OR STRUCTURE, COMMODITY GROUPING COMPONENT, OR COMMODITY GROUPING MEETS 10CFR54.21(a)(l)(i) (YES/NO) Air Compressor No 72 Miscellaneous Process Components Alarm Unit No 73 Electrical and (e.g. , fire detection devices) I&C Analyzers No 74 Electrical and (e.g. , gas analyzers, conductivity analyzers) I&C Electrical and Annunciators (e.g. , lights, buzzers, alarms) No 75 I&C Batteries No 76 Electrical and I&C Cables and Connections, Bus, electrical Yes 77 Electrical and portions of Electrical and I&C Penetration I&C Assemblies, Includes fuse holders outside of cabinets of active electrical SCs (e.g. , electrical penetration assembly cables and connections, connectors, electrical splices, terminal blocks, power cables, control cables, instrument cables, insulated cables, communication cables, uninsulated ground conductors, transmission conductors, isolated-phase bus, nonsegregated-phase bus, segregated-phase bus, switchyard bus) Chargers, Converters, Inverters No 78 Electrical and (e.g. , converters-voltage/current, converters-I&C voltage/pneumatic, battery chargers/inverters, motor-generator sets) Circuit Breakers No 79 Electrical and (e.g. , air circuit breakers, molded case circuit I&C breakers, oil-filled circuit breakers) B-10
A-47039 LICENSETYPICAL RENEWAL AGING MANAGEMENT STRUCTURE, COMPONENTREVIEW
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GROUPINGS AND COMMODITY SHEET 255 of NEI 363 95-10 Revision 6 AND ACTIVE/PASSIVE DETERMINATIONS FOR THE June 2005 INTEGRATED PLANT ASSESSMENT ITEM CATEGORY STRUCTURE, COMPONENT, OR STRUCTURE, COMMODITY GROUPING COMPONENT, OR COMMODITY GROUPING MEETS 10CFR54.21(a)(1)(i) (YES/NO) Communication Equipment No 80 Electrical and (e.g., telephones, video or audio recording or I&C playback equipment, intercoms, computer terminals, electronic messaging, radios, transmission line traps and other power-line carrier equipment) Electric Heaters, No, Yes for a Pressure 81 Electrical and Boundary if applicable, I&C See Appendix C Reference 2 Heat Tracing No 82 Electrical and See Appendix C I&C Reference 2 Electrical Controls and Panel Internal No 83 Electrical and Component Assemblies (may include I&C internal devices such as, but not limited to, switches, breakers, indicating lights, fuse holders, etc.) (e.g., main control board, HVAC control board) Elements, RTDs, Sensors, Thermocouples, No 84 Electrical and Transducers I&C (e.g., conductivity elements, flow elements, Yes for a Pressure temperature sensors, radiation sensors,watt Boundary if applicable transducers, thermocouples, RTDs, vibration probes, amp transducers, frequency transducers, power factor transducers, speed transducers, var. transducers, vibration transducers, voltage transducers) Fuses No 85 Electrical and See Appendix C I&C Reference 3 Generators, Motors No 86 Electrical and (e.g., emergency diesel generators, ECCS and I&C emergency service water pump motors, small motors, motor-generator sets, steam turbine generators, combustion turbine generators, fan motors, pump motors, valve motors, air compressor motors) B-11
A-47039 LICENSETYPICAL RENEWAL AGING MANAGEMENT STRUCTURE, COMPONENTREVIEW
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GROUPINGS AND COMMODITY SHEET 256 of NEI 363 95-10 Revision 6 AND ACTIVE/PASSIVE DETERMINATIONS FOR THE June 2005 INTEGRATED PLANT ASSESSMENT ITEM CATEGORY STRUCTURE, COMPONENT, OR STRUCTURE, COMMODITY GROUPING COMPONENT, OR COMMODITY GROUPING MEETS 10CFR54.21(a)(1)(i) (YES/NO) High-voltage Insulators Yes 87 Electrical and (e.g., porcelain switchyard insulators, I&C transmission line insulators) Surge Arresters No 88 Electrical and (e.g., switchyard surge arresters, lightning I&C arresters, surge suppressers, surge capacitors, protective capacitors) Indicators No 89 Electrical and (e.g., differential pressure indicators, I&C pressure indicators, flow indicators, level indicators, speed indicators, temperature indicators, analog indicators, digital indicators, LED bar graph indicators, LCD indicators) Isolators No 90 Electrical and (e.g., transformer isolators, optical isolators, I&C isolation relays, isolating transfer diodes) Light Bulbs No 91 Electrical and (e.g., indicating lights, emergency lighting, See Appendix C I&C incandescent light bulbs, fluorescent light Reference 2 bulbs) Loop Controllers No 92 Electrical and (e.g., differential pressure indicating I&C controllers, flow indicating controllers, temperature controllers, controllers, speed controllers, programmable logic controller, single loop digital controller, process controllers, manual loader, selector station, hand/auto station, auto/manual station) Meters No 93 Electrical and (e.g., ammeters, volt meters, frequency I&C meters, var meters, watt meters, power factor meters, watt-hour meters) Power Supplies No 94 Electrical and I&C B-12
A-47039 LICENSOifYP~*~#~~~6MP~~~~cRWili>1~ ofNEI 95-10 Revision 6 AND ACTIVE/PASSIVE DETERMINATIONS FOR THE J une 2005 INTEGRATED PLANT ASSESSMENT ITEM CATEGORY STRUCTURE , COMPONENT, OR STRUCTURE, COMMODITY GROUPING COMPONENT, OR COMMODITY GROUPING MEETS 10CFR54.21(a)(l )(i) (YES/NO) Radiation Monitors No 95 Electr ical and (e.g., ar ea radiation monitors , process I&C radiation monitor s) Recorders No 96 Electrical and (e.g., char t recorders, digital recorder s, I&C events recorders) Electrical and Regulators (e.g. , voltage regulators) No 97 I&C Relays No 98 Electrical and (e.g., pr otective relays, con trol/logic relays, I&C a uxilia ry r elays) Sign al Condition ers No 99 Electrical and I&C Solenoid Operators No 100 Electrical and I&C Solid- State Devices No 101 Electrical and (e.g., transistor s, circuit boards, compu ters) I&C Switch es No 102 Electrical and (e.g., different ial pressure indicating I&C switch es, differ en tial pressu re switches, pr essure indicator switch es, pr essure switch es, flow switch es, conductivity switch es, level indicating switches, temperature indicating switches, temperature switches, moisture switches, position switch es, vibration switch es, level switch es, control switch es, au tomatic tran sfer switches, manual tr ansfer switch es, manual disconnect switches, curren t switch es, limit switch es, knife switches) B-13
A-47039 LICENSETYPICAL RENEWAL AGING MANAGEMENT STRUCTURE, COMPONENTREVIEW
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GROUPINGS AND COMMODITY SHEET 258 of NEI 363 95-10 Revision 6 AND ACTIVE/PASSIVE DETERMINATIONS FOR THE June 2005 INTEGRATED PLANT ASSESSMENT ITEM CATEGORY STRUCTURE, COMPONENT, OR STRUCTURE, COMMODITY GROUPING COMPONENT, OR COMMODITY GROUPING MEETS 10CFR54.21(a)(1)(i) (YES/NO) Switchgear, Load Centers, Motor Control No 103 Electrical and Centers, Distribution Panel Internal I&C Component Assemblies (may include internal devices such as, but not limited to, switches, breakers, indicating lights, etc.) (e.g., 4.16 kV switchgear, 480V load centers, 480V motor control centers, 250 VDC motor control centers, 6.9 kV switchgear units, 240/125V power distribution panels) Transformers No 104 Electrical and (e.g., instrument transformers, load center See Appendix C I&C transformers, small distribution Reference 2 transformers, large power transformers, isolation transformers, coupling capacitor voltage transformers) Transmitters No 105 Electrical and (e.g., differential pressure transmitters, I&C pressure transmitters, flow transmitters, level transmitters, radiation transmitters, static pressure transmitters) Hydraulic Operated Valves Yes (Bodies) 106 Valves Explosive Valves Yes (Bodies) 107 Valves Manual Valves Yes (Bodies) 108 Valves Small Valves Yes (Bodies) 109 Valves Motor-Operated Valves Yes (Bodies) 110 Valves B-14
A-47039 LICENSETYPICAL RENEWAL AGING MANAGEMENT STRUCTURE, COMPONENTREVIEW
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GROUPINGS AND COMMODITY SHEET 259 of NEI 363 95-10 Revision 6 AND ACTIVE/PASSIVE DETERMINATIONS FOR THE June 2005 INTEGRATED PLANT ASSESSMENT ITEM CATEGORY STRUCTURE, COMPONENT, OR STRUCTURE, COMMODITY GROUPING COMPONENT, OR COMMODITY GROUPING MEETS 10CFR54.21(a)(1)(i) (YES/NO) Air-Operated Valves Yes (Bodies) 111 Valves Main Steam Isolation Valves Yes (Bodies) 112 Valves Small Relief Valves Yes (Bodies) 113 Valves Check Valves Yes (Bodies) 114 Valves Safety Relief Valves Yes (Bodies) 115 Valves Dampers, louvers, and gravity dampers Yes (Housings) 116 Valves Tanks Air Accumulators Yes 117 Discharge Accumulators (Dampers) Yes 118 Tanks Boron Acid Storage Tanks Yes 119 Tanks B-15
A-47039 LICENSETYPICAL RENEWAL AGING MANAGEMENT STRUCTURE, COMPONENTREVIEW
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GROUPINGS AND COMMODITY SHEET 260 of NEI 363 95-10 Revision 6 AND ACTIVE/PASSIVE DETERMINATIONS FOR THE June 2005 INTEGRATED PLANT ASSESSMENT ITEM CATEGORY STRUCTURE, COMPONENT, OR STRUCTURE, COMMODITY GROUPING COMPONENT, OR COMMODITY GROUPING MEETS 10CFR54.21(a)(1)(i) (YES/NO) Above Ground Oil Tanks Yes 120 Tanks Underground Oil Tanks Yes 121 Tanks Demineralized Water Tanks Yes 122 Tanks Neutron Shield Tank Yes 123 Tanks Fans Ventilation Fans Yes (Housings) 124 (includes intake fans, exhaust fans, and purge fans) Other Fans Yes (Housings) 125 Fans Emergency Lighting No 126 Miscellaneous Hose Stations Yes 127 Miscellaneous B-16
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 261 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 261 of 363 Davis, James T. From: Baker, Ray D. Sent: Friday, April 21, 2000 8:31 AM To: 'William F. Burton (E-mail)'
Subject:
Discussion on Information Presentation in Hatch Application
- Butch, In response to your e-mail, I am providing the following discussion that should assist in clarifying questions regarding how we presented information in the application. The specific discussion relates to questions you asked regarding the Torus Submerged Components Inspection Program, A.3.7.
The first point of clarification relates to program scope. This program narrowly focuses on components that are submerged in torus water. Thus, it is only applicable to components inside the donut-shaped suppression pool ("torus"). A second point of clarification is to note that the program makes no distinction regarding material. It is applicable to components having an aging effect requiring management regardless of material, as long as the components are within the torus. One exception to the scope statement will be discussed below. Thus, the way a reader of the application can tell whether a component is submerged in torus water within the torus is by examining the applicable commodity entry line in the appropriate 6-column table in section 3 to see whether the Torus Submerged Components Inspection Program is credited in the Program column. One exception to this "rule" has to do with primary containment miscellaneous steel (p. 3.3-5 of app). Note that A.3.7 is not credited for this item although torus water is listed as one of the environments. These structural elements receive a separate inspection as a part of IWE/IWL requirements incorporated into our ISI program. Thus, ISI is credited instead of A.3.7. In summary, the typical expectation for program coverage of components exposed to torus water can be summarized as follows:
- submerged components
--carbon steel components typically will credit Protective Coatings and Torus Submerged Components Inspection
--stainless steel components typically will credit Torus Submerged Components Inspection
- components exposed to torus water but not submerged in torus
--these components will typically credit the Treated Water Systems Piping Inspections instead The following bulleted items illustrate how the above points are carried through the application:
x p. 3.2-12 heat exchanger shell & tube sheet: these items are not submerged in the torus x p. 3.2-13 piping: these items are not submerged in the torus x p. 3.2-14 pump casings: these items are not submerged in the torus x p. 3.2-15 strainers: the program is applicable regardless of material x p. 3.2-15 thermowells & valve bodies: these items are not submerged in the torus x p. 3.2-16 strainers: the program is applicable regardless of material x p. 3.2-16 valve bodies: these items are not submerged in the torus x p. 3.2-17 piping (C.2.2.3.1): these items are not submerged in the torus x p. 3.2-17 piping (C.2.2.3.2): the program is applicable regardless of material x p. 3.2-19 strainer: the program is applicable regardless of material x p. 3.2-21 piping (C.2.2.3.2): the program is applicable regardless of material x p. 3.2-22 piping (C.2.2.3.1): these items are not submerged in the torus x p. 3.2-23 strainer: the program is applicable regardless of material x p. 3.3-4 blind flange & CIV: these items are not submerged in the torus x p. 3.3-5 miscellaneous steel: the submerged items are covered by ISI rather than A.3.7 x p. 3.3-5 piping: these items are not submerged in the torus x C.2.2.11.1 & C.2.6.2 the items covered by these commodities are not submerged in the torus. Thus, A.3.7 is not applied to them. x SRV piping is found on p. 3.2-6. Note that there is no carbon steel submerged associated with this. The submerged portion is stainless steel and has A.3.7 credited x Vacuum relief piping is found in table 3.2.3-7 associated with T48. Note that carbon steel credits A.3.7 since some components are submerged. 1
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 262 of 363 A-47039 Attachment C The 1O-attributesl.t~SS~l'!i!Wft/.\\illtt..~MA~di6'MBWP Radf'~~~¥gSl'!lflEitrb~IID~ by aging effects/mechanisms. Thus, for commodity C.2.2.3.1, Table -1 addresses several aging effects/mechanisms for submerged components. Table -2 addresses the same aging effects/mechanisms for components not submerged. Table -3 addresses a different aging effect/mechanism. Note that the non-submerged components credit the Treated Water Systems Piping Inspections whereas the submerged components credit the Torus Submerged Components Inspection as was discussed above. On a separate question, the following discussion is provided to clarify certain information related to Fire Protection System scoping: Functions X43-04, -05 and -07 encompass various fire protection (FP) systems such as L43, T43, U43, etc. A decision was made to group all fire protection into X43 for license renewal scoping. This was done because the one common system runs throughout the entire plant, through most of the buildings and structures. Thus for license renewal scoping , X43 encompasses some or all of the plant wide FP system (L43), reactor building FP system (T43), turbine building FP system (U43), radwaste building FP system (V43), circ water structure FP system (W43), other buildings FP system (X43), yard structures FP system (Y43), and control building FP system (Z43). Also, attached is the updated pdf file containing page markups in a red-line/strikeout format. This update contains the conforming section 2 pages to include bolting in two instances. Please let me know if we can provide additional clarification or discussion regarding any aspects of the application. Ray Baker 8-992-7367 '~/ways do right. This will gratify some people and astonish the rest." -- Mark Twain ATTACHMENT annotated_page_m arkups.pdf (38 ... 2
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 263 of 363 A-47039 Attachment C LICENSE Structures RENEWAL and Components AGING Subject to MANAGEMENT Aging Management REVIEW
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SHEET 263 of 363 Review 2.3, Mechanical Systems Screening Results Component Groups Requiring an Aging Management Review Table 2.3.4-16 Components Supporting Traveling Water Screens/ Trash Rack System [W33] Intended Functions and Their Component Functions Mechanical Component Component Functions Material Bolting Pressure Boundary Carbon Steel Sight Glasses* Pressure Boundary Ceramic Trash Racks Debris Protection Carbon Steel Traveling Screen Debris Protection Carbon Steel Stainless Steel Copper Alloy* Valve Bodies Pressure Boundary Carbon Steel
- No aging effects requiring management Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 2.3-60
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 264 of 363 A-47039 Attachment C LICENSE Structures RENEWAL and Components AGING Subject to MANAGEMENT Aging Management REVIEW Review
SUMMARY
SHEET 264 of 363 2.4, Structures Screening Results Component Groups Requiring an Aging Management Review Table 2.4.3-1 Components Supporting Primary Containment [T23] Intended Functions and Their Component Functions Structural Component Component Functions Material Anchors and Bolts Structural Support; Carbon Steel Nonsafety Related Structural Support Galvanized Steel Stainless Steel Blind Flange* Fission Product Barrier Carbon Steel Bolting* Fission Product Barrier Carbon Steel Containment Isolation Valves
- Fission Product Barrier Carbon Steel Containment Isolation Valves* Fission Product Barrier Stainless Steel Containment Penetrations Fission Product Barrier Carbon Steel (Mechanical only) Stainless Steel Miscellaneous Steel Structural Support; Carbon Steel Radiation Shielding; Galvanized Steel Pipe Whip Restraint; Nonsafety Related Structural Support Piping* Fission Product Barrier Carbon Steel Piping* Fission Product Barrier Stainless Steel Reinforced Concrete Structural Support; Concrete Shelter/Protection; Carbon Steel Flood Barrier; Fission Product Barrier; Radiation Shielding; Missile Barrier; HE/ME Shielding Steel Bellows (inside Vent Pipe) Pressure Boundary; Carbon Steel Fission Product Barrier Stainless Steel Structural Steel Structural Support; Carbon Steel Shelter/Protection; Stainless Steel Radiation Shielding; Missile Barrier; HE/ME Shielding; Pipe Whip Restraint; Nonsafety Related Structural Support; Pressure Boundary Fission Product Barrier; Exchange Heat Tubing* Fission Product Barrier; Pressure Stainless Steel Boundary Unreinforced Concrete Radiation Shielding Unreinforced Concrete**
Vent Pipe, Vent Header, Fission Product Barrier; Carbon Steel Downcomers Pressure Boundary
- Piping and valves include components from systems P51, P21, T23, G51, G11, D11, and C51. These are all included in function T23-01, Torus/Drywell.
** No aging effects requiring management Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 2.4-6
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 265 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 265 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.1-2 Aging Effects Requiring Management for Components Supporting Nuclear Boiler System [B21] Intended Functions and Their Component Functions Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Bolting / C.2.1.1.6 Pressure Boundary Inside Carbon Steel Loss of Preload Torque Activities (Class 1) Fission Product Inservice Inspection Program Barrier Bolting / C.2.2.10.1 Pressure Boundary Inside Carbon Steel Loss of Preload Torque Activities (non-Class 1) Fission Product Loss of Material Protective Coatings Program Barrier Crack Growth Monitor / Pressure Boundary Reactor Water Stainless Steel Loss of Material Reactor Water Chemistry Control C.2.1.1.4 Fission Product Cracking Inservice Inspection Program (Class 1) Barrier Component Cyclic or Transient Limit Program Treated Water Systems Piping Inspections Flow Nozzle / C.2.1.1.3 Pressure Boundary Reactor Water Carbon Steel Loss of Material Reactor Water Chemistry Control (Class 1) Fission Product Cracking Inservice Inspection Program Barrier Galvanic Susceptibility Inspections Component Cyclic or Transient Limit Program Flow Accelerated Corrosion Program Treated Water Systems Piping Inspections Piping / C.2.2.1.1 Pressure Boundary Reactor Water Carbon Steel Loss of Material Reactor Water Chemistry Control (non-Class 1) Fission Product Cracking Galvanic Susceptibility Inspections Barrier Treated Water Systems Piping Inspections Flow Accelerated Corrosion Program Piping / C.2.2.1.2 Pressure Boundary Reactor Water Stainless Steel Loss of Material Reactor Water Chemistry Control (non-Class 1) Fission Product Cracking Treated Water Systems Piping Barrier Inspections Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-5
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 266 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 266 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.1-2 Aging Effects Requiring Management for Components Supporting Nuclear Boiler System [B21] Intended Functions and Their Component Functions (Continued) Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Piping / C.2.2.2.2 Pressure Boundary Demin Water Stainless Steel Loss of Material Demineralized Water and Condensate (non-Class 1) Fission Product Cracking Storage Tank Chemistry Control Barrier Treated Water Systems Piping Inspections Piping / C.2.2.3.1 Pressure Boundary Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control (non-Class 1) Fission Product Cracking Torus Submerged Components Barrier Inspection Program Piping / C.2.2.3.2 Pressure Boundary Torus Water Stainless Steel Loss of Material Suppression Pool Chemistry Control (non-Class 1) Fission Product Cracking Torus Submerged Components Barrier Inspection Program Piping / C.2.1.1.3 Pressure Boundary Reactor Water Carbon Steel Loss of Material Reactor Water Chemistry Control (Class 1) Fission Product Cracking Inservice Inspection Program Barrier Galvanic Susceptibility Inspections Component Cyclic or Transient Limit Program Flow Accelerated Corrosion Program Treated Water Systems Piping Inspections Piping / C.2.1.1.4 Pressure Boundary Reactor Water Stainless Steel Loss of Material Reactor Water Chemistry Control (Class 1) Fission Product Cracking Inservice Inspection Program Barrier Component Cyclic or Transient Limit Program Treated Water Systems Piping Inspections Piping / C.2.2.9.1 Pressure Boundary Wetted Gas Carbon Steel Loss of Material Inservice Inspection Program (Class 1) Fission Product Cracking Gas Systems Component Inspections Barrier Passive Component Inspection Activities Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-6
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 267 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 267 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.1-2 Aging Effects Requiring Management for Components Supporting Nuclear Boiler System [B21] Intended Functions and Their Component Functions (Continued) Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Restricting Orifice / Pressure Boundary Reactor Water Stainless Steel Loss of Material Reactor Water Chemistry Control C.2.1.1.4 Fission Product Cracking Component Cyclic or Transient Limit (Class 1) Barrier Program Inservice Inspection Program Treated Water Systems Piping Inspections Thermowell/ Pressure Boundary Wetted Gas Carbon Steel Loss of Material Gas Systems Component Inspections C.2.2.9.1 Fission Product Cracking Passive Component Inspection (non-Class 1) Barrier Activities Thermowell / Pressure Boundary Reactor Water Stainless Steel Loss of Material Reactor Water Chemistry Control C.2.1.1.4 Fission Product Cracking Inservice Inspection Program (Class 1) Barrier Component Cyclic or Transient Limit Program Treated Water Systems Piping Inspections Valve Bodies / C.2.2.1.1 Pressure Boundary Reactor Water Carbon Steel Loss of Material Reactor Water Chemistry Control (non-Class 1) Fission Product Cracking Flow Accelerated Corrosion Program Barrier Galvanic Susceptibility Inspections Treated Water Systems Piping Inspections Valve Bodies / C.2.2.1.2 Pressure Boundary Reactor Water Stainless Steel Loss of Material Reactor Water Chemistry Control (non-Class 1) Fission Product Cracking Treated Water Systems Piping Barrier Inspections Valve Bodies / C.2.2.9.1 Pressure Boundary Wetted Gas Carbon Steel Loss of Material Gas Systems Component Inspections (non-Class 1) Fission Product Cracking Inservice Inspection Program Barrier Passive Component Inspection Activities Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-7
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 268 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 268 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.3-4 Aging Effects Requiring Management for Components Supporting High Pressure Coolant Injection System [E41] Intended Functions and Their Component Functions Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Bolting / C.2.2.10.1 Pressure Boundary Inside Carbon Steel Loss of Preload Torque Activities Fission Product Barrier Loss of Material Protective Coatings Program Bolting / C.2.2.10.2 Pressure Boundary Inside Stainless Steel Loss of Preload Torque Activities Fission Product Barrier Flexible Connector / Pressure Boundary Dry Wetted Gas Stainless Steel Cracking Gas Systems Component Inspections C.2.2.9.2 Fission Product Barrier Loss of Material Piping / C.2.2.1.1 Pressure Boundary Reactor Water Carbon Steel Loss of Material Reactor Water Chemistry Control Fission Product Barrier Cracking Galvanic Susceptibility Inspections Flow Accelerated Corrosion Program Treated Water Systems Piping Inspections Piping / C.2.2.2.1 Pressure Boundary Demin Water Carbon Steel Loss of Material Demineralized Water and Condensate Fission Product Barrier Cracking Storage Tank Chemistry Control Treated Water Systems Piping Inspections Piping / C.2.2.2.2 Pressure Boundary Demin Water Stainless Steel Loss of Material Demineralized Water and Condensate Fission Product Barrier Cracking Storage Tank Chemistry Control Program Treated Water Systems Piping Inspections Piping / C.2.2.3.1 Pressure Boundary Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control Fission Product Barrier Cracking Galvanic Susceptibility Inspections Treated Water Systems Piping Inspections Torus Submerged Components Inspection Program Protective Coatings Program Piping / C.2.2.3.2 Pressure Boundary Torus Water Stainless Steel Loss of Material Suppression Pool Chemistry Control Fission Product Barrier Cracking Torus Submerged Components Inspection Program Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-17
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 269 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 269 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.3-5 Aging Effects Requiring Management for Components Supporting Reactor Core Isolation Cooling System [E51] Intended Functions and Their Component Functions (Continued) Mechanical Component Environment Material Aging Effects Aging Management Program/ Component Functions Activity Valve Bodies / C.2.2.9.2 Pressure Boundary Wetted Gas Stainless Steel Loss of Material Gas Systems Component Inspections Fission Product Cracking Passive Component Inspection Activities Barrier Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-25
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 270 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 270 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.3-7 Aging Effects Requiring Management for Components Supporting Primary Containment Purge and Inerting System [T48] Intended Functions and Their Component Functions Component Aging Management Mechanical Component Functions Environment Material Aging Effects Program/Activity Bolting / C.2.2.10.1 Pressure Boundary Inside Carbon Steel Loss of Preload Torque Activities Loss of Material Protective Coatings Program Bolting / C.2.2.10.2 Pressure Boundary Inside Stainless Steel Loss of Preload Torque Activities Flex Hose / C.2.2.9.1 Pressure Boundary Air Stainless Steel Cracking Gas Systems Component Inspections Nitrogen Tank Jacket / C.2.2.9.1 Structural Support Air Carbon Steel Cracking Gas Systems Component Inspections Loss of Material Passive Component Inspection Activities Piping / C.2.2.3.1 Pressure Boundary Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control Cracking Galvanic Susceptibility Inspections Torus Submerged Components Inspection Program Protective Coatings Program Piping / C.2.2.3.1 Pressure Boundary Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control Cracking Torus Submerged Components Inspection Program Piping / C.2.2.3.2 Pressure Boundary Torus Water Stainless Steel Loss of Material Suppression Pool Chemistry Control Cracking Treated Water Systems Piping Inspections Piping / C.2.2.8.2 Pressure Boundary Dried Gas Stainless Steel Cracking None Required Piping / C.2.2.9.1 Pressure Boundary Wetted Gas Carbon Steel Cracking Gas Systems Component Inspections Loss of Material Passive Component Inspection Activities Pressure Buildup Coil / C.2.2.8.2 Pressure Boundary Dried Gas Stainless Steel Cracking None Required Exchange Heat Rupture Disc / C.2.2.8.2 Pressure Boundary Dried Gas Stainless Steel Cracking None Required Storage Tank / C.2.2.8.2 Pressure Boundary Dried Gas Stainless Steel Cracking None Required Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-28
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 271 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 271 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.4-2 Aging Effects Requiring Management for Components Supporting Refueling Platform Equipment Assembly [F15] Intended Functions and Their Component Functions Structural Component Component Functions Environment Material Aging Effects Aging Management Program/Activity Anchors and Structural support Inside Carbon steel Loss of material Protective Coatings Program Bolts Nonsafety Related Overhead Crane and Refueling Platform C.2.6.3 Structural Support Inspection Structural Monitoring Program Miscellaneous Structural support; Inside Carbon steel Loss of material Protective Coatings Program Steel Nonsafety Related Overhead Crane and Refueling Platform C.2.6.3 Structural Support Inspection Structural Monitoring Program Rivets Structural Support Inside Aluminum None None Required Structural Steel Structural support Inside Carbon steel Loss of material Protective Coatings Program C.2.6.3 Overhead Crane and Refueling Platform Inspection Structural Monitoring Program Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-33
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 272 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 272 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.4-7 Aging Effects Requiring Management for Components Supporting Plant Service Water System [P41] Intended Functions and Their Component Functions (Continued) Mechanical Component Component Functions Environment Material Aging Effects Aging Management Program/Activity Thermowell / Pressure Boundary Raw Water Carbon Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.1 Cracking Plant Service Water and RHR Service Water Chemistry Control Program Thermowell / Pressure Boundary Raw Water Stainless Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.2 Cracking PSW and RHRSW Chemistry Control Program Valve Bodies / Pressure Boundary Raw Water Carbon Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.1 Flow Blockage PSW and RHRSW Chemistry Control Cracking Program Structural Monitoring Program Galvanic Susceptibility Inspections Valve Bodies / Pressure Boundary Raw Water Stainless Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.2 Flow Blockage PSW and RHRSW Chemistry Control Cracking Program Structural Monitoring Program Valve Bodies / Pressure Boundary Raw Water Copper Alloy Loss of Material PSW and RHRSW Chemistry Control C.2.2.6.3 Cracking Program Flow Blockage Structural Monitoring Program PSW and RHRSW Inspection Program Venturi / Pressure Boundary Raw Water Carbon Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.1 Flow Blockage PSW and RHRSW Chemistry Control Cracking Program Structural Monitoring Program Galvanic Susceptibility Inspections Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-40
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 273 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 273 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.4-13 Aging Effects Requiring Management for Components Supporting Reactor Building Crane [T31] Intended Functions and Their Component Functions Structural Component Component Functions Environment Material Aging Effects Aging Management Program/Activity Structural Steel/ Structural Support Inside Carbon Steel Loss of Material Overhead Crane and Refueling Platform C.2.6.3 Inspection Protective Coatings Program Structural Monitoring Program Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-47
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 274 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 274 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.4-16 Aging Effects Requiring Management for Components Supporting Traveling Water Screens / Trash Rack System [W33] Intended Functions and Their Component Functions Mechanical Component Component Functions Environment Material Aging Effects Aging Management Program/Activity Trash Rack / Debris Protection Submerged Carbon Steel Loss of Material Structural Monitoring Program C.2.6.3 Protective Coatings Program Traveling Screen / Debris Protection Submerged Carbon Steel Loss of Material Structural Monitoring Program C.2.6.3 Stainless Steel Traveling Screen / Debris Protection Submerged Copper Alloy None None Required C.2.6.3 Valve Bodies / Pressure Boundary Raw Water Carbon Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.1 Flow Blockage Plant Service Water and RHR Service Water Cracking Chemistry Control Program Galvanic Susceptibility Inspections Bolting / C.2.2.10.1 Pressure Boundary Outside Carbon Steel Loss of Material Torque Activities Loss of Preload Protective Coatings Program Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-50
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 275 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 275 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.4-18 Aging Effects Requiring Management for Components Supporting Fire Protection System [X43] Intended Functions and Their Intended Functions Component Aging Management Mechanical Component Functions Environment Material Aging Effects Program/Activity Boltings / C.2.2.10.1 Pressure Boundary Inside Carbon Steel Loss of Preload Torque Activities Outside Loss of Material Protective Coatings Program Fire Doors / C.2.3.4.3 Fire Barrier Inside Carbon Steel Loss of Material Fire Protection Activities Fire Doors / C.2.3.4.3 Fire Barrier Inside Galvanized Steel None None Required Copper Alloy Stainless Steel Aluminum Nonmettalic, Inorganic Gypsum Fibers, Nonasbestos Synthetic Nonmetallic, Organic Fire Hydrants / C.2.3.1 Pressure Boundary Raw Water Cast Iron Loss of Material Fire Protection Activities Cracking Flow Blockage Fittings / C.2.3.1 Pressure Boundary Raw Water Cast Iron Loss of Material Fire Protection Activities Air Cracking Flow Blockage Fittings / C.2.3.3 Pressure Boundary Air Copper Alloy Cracking Fire Protection Activities Cast Iron Loss of Material Fusible Material / C.2.3.1 Pressure Boundary Inside Nonferrous Metal Loss of Material Fire Protection Activities Cracking Kaowool and Hold-Down Fire Barrier Inside Galvanized Steel CrackingLoss of Fire Protection Activities Straps / C.2.3.4.3C.2.3.4.2 Insulation Material Material Change in Material Properties Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-52
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 276 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 276 of 363 Aging Management Review Results 3.3, Civil/Structural Table 3.3.1-3 Aging Effects Requiring Management for Components Supporting Primary Containment [T23] Intended Functions and Their Component Functions Structural Component Component Functions Environment Material Aging Effects Aging Management Program/Activity Anchors and Bolts / Structural Support; Containment Carbon Steel Loss of Material Protective Coatings Program C.2.6.2 Nonsafety Related Atmosphere; Galvanized Steel Inservice Inspection Program Structural Support Embedded; Inside Stainless Steel Suppression Pool Chemistry Control Torus Water Blind Flange* / Fission Product Barrier Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control C.2.2.3.1 Cracking Treated Water Systems Piping Inspections Containment Isolation Fission Product Barrier Demin Water Stainless Steel Loss of Material Demineralized Water and Condensate Valves* / C.2.2.2.2 Cracking Storage Tank Chemistry Control Treated Water Systems Piping Inspections Containment Isolation Fission Product Barrier Demin Water Carbon Steel Loss of Material Demineralized Water and Condensate Valves* / C.2.2.3.1 Cracking Storage Tank Chemistry Control Treated Water Systems Piping Inspections Containment Isolation Fission Product Barrier Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control Valves* / C.2.2.3.1 Treated Water Systems Piping Inspections Containment Isolation Fission Product Barrier Raw Water Carbon Steel Loss of Material Passive Component Inspection Activities Valves* / Cracking C.2.2.6.2C.2.6.2 Containment Isolation Fission Product Barrier Wetted Gas Carbon Steel Loss of Material Gas Systems Component Inspections Valves* / C.2.2.9.1 Passive Component Inspection Activities Containment Isolation Fission Product Barrier Wetted Gas Stainless Steel Loss of Material Gas Systems Component Inspection Valves* / C.2.2.9.2 Cracking Containment Fission Product Barrier Containment Carbon Steel Loss of Material Protective Coatings Program Penetrations Atmosphere; Stainless Steel Inservice Inspection Program (Mechanical only) / Embedded; Inside Primary Containment Leakage Rate Testing C.2.6.2 Program Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.3-4
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 277 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 277 of 363 Aging Management Review Results 3.3, Civil/Structural Table 3.3.1-3 Aging Effects Requiring Management for Components Supporting Primary Containment [T23] Intended Functions and Their Component Functions (Continued) Structural Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Structural Steel / Structural Support; Containment Carbon Steel Loss of Material Protective Coatings Program C.2.6.2 Shelter/Protection; Atmosphere; Stainless Steel Cracking Primary Containment Leakage Rate Pressure Boundary; Inside; Testing Program Radiation Shielding; Torus Water; Inservice Inspection Program Nonsafety Related Embedded Suppression Pool Chemistry Control Structural Support; Component Cyclic or Transient Limit HE/ME Shielding; Program Missile Barrier; Pipe Whip Restraint; Fission Product Barrier; Exchange Heat Tubing* / C.2.2.9.2 Fission Product Wetted Gas Stainless Steel Loss of Material Gas Systems Component Inspections Barrier; Cracking Pressure Boundary Vent Pipe, Vent Pressure Boundary Containment Carbon Steel Loss of Material Protective Coatings Program Header, Downcomers / Fission Product Barrier Atmosphere; Cracking Inservice Inspection Program C.2.6.2 High Humidity; Primary Containment Leakage Rate Inside; Testing Program Torus Water Component Cyclic or Transient Limit Program Suppression Pool Chemistry Control Bolting / C.2.2.10.1 Pressure Boundary Inside Carbon Steel Loss of Material Protective Coatings Program Containment Loss of Preload Torque Activities Atmosphere
- Piping and valve bodies include components from systems P51, P21, T23, G51, G11, D11, and C51. These are all included in function T23-01, Torus/Drywell.
Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.3-6
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 278 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 278 of 363 Aging Management Review Results 3.3, Civil/Structural Table 3.3.1-5 Aging Effects Requiring Management for Components Supporting Reactor Building [T29] Intended Functions and Their Component Functions Structural Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Anchors and Bolts / Structural Support; Inside; Outside Carbon Steel Loss of Material Protective Coatings Program C.2.6.3 Nonsafety Related Structural Monitoring Program Structural Support Blowout Panels / Structural Support; Inside Aluminum None None Required C.2.6.6 Fission Product Barrier Miscellaneous Steel / Structural Support; Inside; Outside Carbon Steel Loss of Material Structural Monitoring Program C.2.6.3 HE/ME Shielding; Galvanized Steel Protective Coatings Program Nonsafety Related Structural Support Miscellaneous Steel / Structural Support; Inside; Outside Stainless Steel None None Required C.2.6.3 HE/ME Shielding; Nonsafety Related Structural Support Panel Joint Seals and Shelter/Protection; Inside; Outside Elastomers; Material Property Structural Monitoring Program Sealants / C.2.6.7 Fission Product Barrier Nonmetallic, Changes and Protective Coatings Program Inorganic Cracking Loss of Adhesion Reinforced Concrete Structural Support; Inside; Outside Concrete Loss of Material Structural Monitoring Program C.2.6.1 Fire Barrier; Masonry Block Cracking Protective Coatings Program Shelter/Protection; Carbon Steel Flood Barrier; Fission Product Barrier; Radiation Shielding; Missile Barrier; HE/ME Shielding; Nonsafety Related Structural Support Structural Steel Structural Support; Inside; Outside; Carbon Steel Loss of Material Structural Monitoring Program C.2.6.3 Missile Barrier; Submerged Galvanized Steel Protective Coatings Program Nonsafety Related Stainless Steel Overhead Crane and Refueling Platform Structural Support Inspections Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.3-8
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 279 of 363 A-47039 Attachment C LICENSE Identification RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 279 of 363 of Commodities C.2, Aging Management Reviews C.2.2.3 Non-Class 1 Components Suppression Pool Water Environment Description Components within section C.2.2.3 are subject to an environment of suppression pool water under normal conditions. The suppression pool water environment is defined in section C.1.2.2. C.2.2.3.1 Aging Management Review for Non-Class 1 Carbon Steel Components Within the Suppression Pool Environment This commodity group consists of carbon steel commodities with an internal environment of suppression pool water or submerged within the suppression pool. The following component types are included within this evaluation:
- Piping
- Valve bodies
- Pump casings
- Thermowells
- Blind flange Systems B21 - Nuclear Boiler (2.3.1.2)
- E11 - Residual Heat Removal (2.3.3.2)
- E21 - Core Spray (2.3.3.3)
- E41 - High Pressure Coolant Injection (2.3.3.4)
- E51 - Reactor Core Isolation Cooling (2.3.3.5)
- T23 - Primary Containment (2.4.3)
- T48 - Primary Containment Purge and Inerting (2.3.3.7)
Aging Effects Requiring Management
- Loss of material (C.1.2.2.1) due to general corrosion, galvanic corrosion, crevice corrosion, pitting, microbiologically influenced corrosion (MIC), and erosion corrosion.
- Cracking (C.1.2.2.2) due to thermal fatigue.
A complete discussion of the applicable aging effect determinations may be found in section C.1 of the LRA or by using the above links. Aging Management Programs Aging management programs determined to manage aging effects requiring management are as follows:
- Suppression Pool Chemistry Control (A.1.7)
- Protective Coatings Program (A.2.3)
Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal C.2-60
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 280 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 280 of 363 From: Baker, Ray D. Sent: Friday, April 28, 2000 2:58 PM To: 'William F. Burton (E-mail)'
Subject:
Conforming Annotated Page Change
- Butch, As we discussed this week, both you and I had noted the need to provide the conforming three-column table page change in section 2 for the page change previously identified that clarified the fire protection component group line item as kaowool and hold down straps. Page 2.3-66 is provided in the attached file conforming to the change previously noted for page 3.2-52.
Please let me know if you have any questions regarding this item. Ray Baker 8-992-7367 '~/ways do right. This will gratify some people and astonish the rest." -- Mark Twain ATTACHMENT annotated_page_m arkups.pdf (48 ...
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 281 of 363 A-47039 Attachment C LICENSE Structures RENEWAL and Components AGING Subject to MANAGEMENT Aging Management REVIEW
SUMMARY
SHEET 281 of 363 Review 2.3, Mechanical Systems Screening Results Component Groups Requiring an Aging Management Review Table 2.3.4-16 Components Supporting Traveling Water Screens/ Trash Rack System [W33] Intended Functions and Their Component Functions Mechanical Component Component Functions Material Bolting Pressure Boundary Carbon Steel Sight Glasses* Pressure Boundary Ceramic Trash Racks Debris Protection Carbon Steel Traveling Screen Debris Protection Carbon Steel Stainless Steel Copper Alloy* Valve Bodies Pressure Boundary Carbon Steel
- No aging effects requiring management Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 2.3-60
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 282 of 363 A-47039 Attachment C LICENSE Structures RENEWAL and Components AGING Subject to MANAGEMENT Aging Management REVIEW
SUMMARY
SHEET 282 of 363 Review 2.3, Mechanical Systems Screening Results Component Groups Requiring an Aging Management Review Table 2.3.4-18 Components Supporting Fire Protection System [X43] Intended Functions and Their Component Functions Mechanical Component Component Functions Material Bolting Pressure Boundary Carbon Steel Fire Doors Fire Barrier Carbon Steel Galvanized Steel Copper Alloy Stainless Steel Aluminum Nonmetallic, Inorganic-Gypsum Fibers, nonasbestos synthetic Nonmetallic, organic Fire Hydrants Pressure Boundary Cast Iron Fittings Pressure Boundary Cast Iron Fittings Pressure Boundary Copper Alloy Cast Iron Fusible Material Pressure Boundary Nonferrous Metal Kaowool and Hold-down Straps Fire Barrier Galvanized Steel, Insulation material Nozzles Flow Restriction Aluminum Copper Alloy Nozzles Flow Restriction Copper Alloy Penetration Seals Fire Barrier Concrete Ceramics Carbon Steel Synthetic Fiber Elastomers Pilot Valves Pressure Boundary Aluminum Pipe Line Strainers Pressure Boundary Cast Iron Piping Pressure Boundary Carbon Steel Aluminum Galvanized Steel Copper Alloy Cast Iron Piping Pressure Boundary Carbon Steel Stainless Steel Piping Pressure Boundary Carbon Steel Galvanized Steel Pump Casings Pressure Boundary Cast Iron Restricting Orifices Pressure Boundary, Flow Stainless Steel Restriction Sprinkler Head Bulbs Pressure Boundary Ceramics Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 2.3-66
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 283 of 363 A-47039 Attachment C LICENSE Structures RENEWAL and Components AGING Subject to MANAGEMENT Aging Management REVIEW Review
SUMMARY
SHEET 283 of 363 2.4, Structures Screening Results Component Groups Requiring an Aging Management Review Table 2.4.3-1 Components Supporting Primary Containment [T23] Intended Functions and Their Component Functions Structural Component Component Functions Material Anchors and Bolts Structural Support; Carbon Steel Nonsafety Related Structural Support Galvanized Steel Stainless Steel Blind Flange* Fission Product Barrier Carbon Steel Bolting* Fission Product Barrier Carbon Steel Containment Isolation Valves
- Fission Product Barrier Carbon Steel Containment Isolation Valves* Fission Product Barrier Stainless Steel Containment Penetrations Fission Product Barrier Carbon Steel (Mechanical only) Stainless Steel Miscellaneous Steel Structural Support; Carbon Steel Radiation Shielding; Galvanized Steel Pipe Whip Restraint; Nonsafety Related Structural Support Piping* Fission Product Barrier Carbon Steel Piping* Fission Product Barrier Stainless Steel Reinforced Concrete Structural Support; Concrete Shelter/Protection; Carbon Steel Flood Barrier; Fission Product Barrier; Radiation Shielding; Missile Barrier; HE/ME Shielding Steel Bellows (inside Vent Pipe) Pressure Boundary; Carbon Steel Fission Product Barrier Stainless Steel Structural Steel Structural Support; Carbon Steel Shelter/Protection; Stainless Steel Radiation Shielding; Missile Barrier; HE/ME Shielding; Pipe Whip Restraint; Nonsafety Related Structural Support; Pressure Boundary Fission Product Barrier; Exchange Heat Tubing* Fission Product Barrier; Pressure Stainless Steel Boundary Unreinforced Concrete Radiation Shielding Unreinforced Concrete**
Vent Pipe, Vent Header, Fission Product Barrier; Carbon Steel Downcomers Pressure Boundary
- Piping and valves include components from systems P51, P21, T23, G51, G11, D11, and C51. These are all included in function T23-01, Torus/Drywell.
** No aging effects requiring management Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 2.4-6
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 284 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 284 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.1-2 Aging Effects Requiring Management for Components Supporting Nuclear Boiler System [B21] Intended Functions and Their Component Functions Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Bolting / C.2.1.1.6 Pressure Boundary Inside Carbon Steel Loss of Preload Torque Activities (Class 1) Fission Product Inservice Inspection Program Barrier Bolting / C.2.2.10.1 Pressure Boundary Inside Carbon Steel Loss of Preload Torque Activities (non-Class 1) Fission Product Loss of Material Protective Coatings Program Barrier Crack Growth Monitor / Pressure Boundary Reactor Water Stainless Steel Loss of Material Reactor Water Chemistry Control C.2.1.1.4 Fission Product Cracking Inservice Inspection Program (Class 1) Barrier Component Cyclic or Transient Limit Program Treated Water Systems Piping Inspections Flow Nozzle / C.2.1.1.3 Pressure Boundary Reactor Water Carbon Steel Loss of Material Reactor Water Chemistry Control (Class 1) Fission Product Cracking Inservice Inspection Program Barrier Galvanic Susceptibility Inspections Component Cyclic or Transient Limit Program Flow Accelerated Corrosion Program Treated Water Systems Piping Inspections Piping / C.2.2.1.1 Pressure Boundary Reactor Water Carbon Steel Loss of Material Reactor Water Chemistry Control (non-Class 1) Fission Product Cracking Galvanic Susceptibility Inspections Barrier Treated Water Systems Piping Inspections Flow Accelerated Corrosion Program Piping / C.2.2.1.2 Pressure Boundary Reactor Water Stainless Steel Loss of Material Reactor Water Chemistry Control (non-Class 1) Fission Product Cracking Treated Water Systems Piping Barrier Inspections Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-5
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 285 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 285 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.1-2 Aging Effects Requiring Management for Components Supporting Nuclear Boiler System [B21] Intended Functions and Their Component Functions (Continued) Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Piping / C.2.2.2.2 Pressure Boundary Demin Water Stainless Steel Loss of Material Demineralized Water and Condensate (non-Class 1) Fission Product Cracking Storage Tank Chemistry Control Barrier Treated Water Systems Piping Inspections Piping / C.2.2.3.1 Pressure Boundary Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control (non-Class 1) Fission Product Cracking Torus Submerged Components Barrier Inspection Program Piping / C.2.2.3.2 Pressure Boundary Torus Water Stainless Steel Loss of Material Suppression Pool Chemistry Control (non-Class 1) Fission Product Cracking Torus Submerged Components Barrier Inspection Program Piping / C.2.1.1.3 Pressure Boundary Reactor Water Carbon Steel Loss of Material Reactor Water Chemistry Control (Class 1) Fission Product Cracking Inservice Inspection Program Barrier Galvanic Susceptibility Inspections Component Cyclic or Transient Limit Program Flow Accelerated Corrosion Program Treated Water Systems Piping Inspections Piping / C.2.1.1.4 Pressure Boundary Reactor Water Stainless Steel Loss of Material Reactor Water Chemistry Control (Class 1) Fission Product Cracking Inservice Inspection Program Barrier Component Cyclic or Transient Limit Program Treated Water Systems Piping Inspections Piping / C.2.2.9.1 Pressure Boundary Wetted Gas Carbon Steel Loss of Material Inservice Inspection Program (Class 1) Fission Product Cracking Gas Systems Component Inspections Barrier Passive Component Inspection Activities Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-6
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 286 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 286 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.1-2 Aging Effects Requiring Management for Components Supporting Nuclear Boiler System [B21] Intended Functions and Their Component Functions (Continued) Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Restricting Orifice / Pressure Boundary Reactor Water Stainless Steel Loss of Material Reactor Water Chemistry Control C.2.1.1.4 Fission Product Cracking Component Cyclic or Transient Limit (Class 1) Barrier Program Inservice Inspection Program Treated Water Systems Piping Inspections Thermowell/ Pressure Boundary Wetted Gas Carbon Steel Loss of Material Gas Systems Component Inspections C.2.2.9.1 Fission Product Cracking Passive Component Inspection (non-Class 1) Barrier Activities Thermowell / Pressure Boundary Reactor Water Stainless Steel Loss of Material Reactor Water Chemistry Control C.2.1.1.4 Fission Product Cracking Inservice Inspection Program (Class 1) Barrier Component Cyclic or Transient Limit Program Treated Water Systems Piping Inspections Valve Bodies / C.2.2.1.1 Pressure Boundary Reactor Water Carbon Steel Loss of Material Reactor Water Chemistry Control (non-Class 1) Fission Product Cracking Flow Accelerated Corrosion Program Barrier Galvanic Susceptibility Inspections Treated Water Systems Piping Inspections Valve Bodies / C.2.2.1.2 Pressure Boundary Reactor Water Stainless Steel Loss of Material Reactor Water Chemistry Control (non-Class 1) Fission Product Cracking Treated Water Systems Piping Barrier Inspections Valve Bodies / C.2.2.9.1 Pressure Boundary Wetted Gas Carbon Steel Loss of Material Gas Systems Component Inspections (non-Class 1) Fission Product Cracking Inservice Inspection Program Barrier Passive Component Inspection Activities Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-7
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 287 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 287 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.3-4 Aging Effects Requiring Management for Components Supporting High Pressure Coolant Injection System [E41] Intended Functions and Their Component Functions Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Bolting / C.2.2.10.1 Pressure Boundary Inside Carbon Steel Loss of Preload Torque Activities Fission Product Barrier Loss of Material Protective Coatings Program Bolting / C.2.2.10.2 Pressure Boundary Inside Stainless Steel Loss of Preload Torque Activities Fission Product Barrier Flexible Connector / Pressure Boundary Dry Wetted Gas Stainless Steel Cracking Gas Systems Component Inspections C.2.2.9.2 Fission Product Barrier Loss of Material Piping / C.2.2.1.1 Pressure Boundary Reactor Water Carbon Steel Loss of Material Reactor Water Chemistry Control Fission Product Barrier Cracking Galvanic Susceptibility Inspections Flow Accelerated Corrosion Program Treated Water Systems Piping Inspections Piping / C.2.2.2.1 Pressure Boundary Demin Water Carbon Steel Loss of Material Demineralized Water and Condensate Fission Product Barrier Cracking Storage Tank Chemistry Control Treated Water Systems Piping Inspections Piping / C.2.2.2.2 Pressure Boundary Demin Water Stainless Steel Loss of Material Demineralized Water and Condensate Fission Product Barrier Cracking Storage Tank Chemistry Control Program Treated Water Systems Piping Inspections Piping / C.2.2.3.1 Pressure Boundary Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control Fission Product Barrier Cracking Galvanic Susceptibility Inspections Treated Water Systems Piping Inspections Torus Submerged Components Inspection Program Protective Coatings Program Piping / C.2.2.3.2 Pressure Boundary Torus Water Stainless Steel Loss of Material Suppression Pool Chemistry Control Fission Product Barrier Cracking Torus Submerged Components Inspection Program Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-17
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 288 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 288 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.3-5 Aging Effects Requiring Management for Components Supporting Reactor Core Isolation Cooling System [E51] Intended Functions and Their Component Functions (Continued) Mechanical Component Environment Material Aging Effects Aging Management Program/ Component Functions Activity Valve Bodies / C.2.2.9.2 Pressure Boundary Wetted Gas Stainless Steel Loss of Material Gas Systems Component Inspections Fission Product Cracking Passive Component Inspection Activities Barrier Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-25
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 289 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 289 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.3-7 Aging Effects Requiring Management for Components Supporting Primary Containment Purge and Inerting System [T48] Intended Functions and Their Component Functions Component Aging Management Mechanical Component Functions Environment Material Aging Effects Program/Activity Bolting / C.2.2.10.1 Pressure Boundary Inside Carbon Steel Loss of Preload Torque Activities Loss of Material Protective Coatings Program Bolting / C.2.2.10.2 Pressure Boundary Inside Stainless Steel Loss of Preload Torque Activities Flex Hose / C.2.2.9.1 Pressure Boundary Air Stainless Steel Cracking Gas Systems Component Inspections Nitrogen Tank Jacket / C.2.2.9.1 Structural Support Air Carbon Steel Cracking Gas Systems Component Inspections Loss of Material Passive Component Inspection Activities Piping / C.2.2.3.1 Pressure Boundary Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control Cracking Galvanic Susceptibility Inspections Torus Submerged Components Inspection Program Protective Coatings Program Piping / C.2.2.3.1 Pressure Boundary Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control Cracking Torus Submerged Components Inspection Program Piping / C.2.2.3.2 Pressure Boundary Torus Water Stainless Steel Loss of Material Suppression Pool Chemistry Control Cracking Treated Water Systems Piping Inspections Piping / C.2.2.8.2 Pressure Boundary Dried Gas Stainless Steel Cracking None Required Piping / C.2.2.9.1 Pressure Boundary Wetted Gas Carbon Steel Cracking Gas Systems Component Inspections Loss of Material Passive Component Inspection Activities Pressure Buildup Coil / C.2.2.8.2 Pressure Boundary Dried Gas Stainless Steel Cracking None Required Exchange Heat Rupture Disc / C.2.2.8.2 Pressure Boundary Dried Gas Stainless Steel Cracking None Required Storage Tank / C.2.2.8.2 Pressure Boundary Dried Gas Stainless Steel Cracking None Required Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-28
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 290 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 290 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.4-2 Aging Effects Requiring Management for Components Supporting Refueling Platform Equipment Assembly [F15] Intended Functions and Their Component Functions Structural Component Component Functions Environment Material Aging Effects Aging Management Program/Activity Anchors and Structural support Inside Carbon steel Loss of material Protective Coatings Program Bolts Nonsafety Related Overhead Crane and Refueling Platform C.2.6.3 Structural Support Inspection Structural Monitoring Program Miscellaneous Structural support; Inside Carbon steel Loss of material Protective Coatings Program Steel Nonsafety Related Overhead Crane and Refueling Platform C.2.6.3 Structural Support Inspection Structural Monitoring Program Rivets Structural Support Inside Aluminum None None Required Structural Steel Structural support Inside Carbon steel Loss of material Protective Coatings Program C.2.6.3 Overhead Crane and Refueling Platform Inspection Structural Monitoring Program Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-33
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 291 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 291 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.4-7 Aging Effects Requiring Management for Components Supporting Plant Service Water System [P41] Intended Functions and Their Component Functions (Continued) Mechanical Component Component Functions Environment Material Aging Effects Aging Management Program/Activity Thermowell / Pressure Boundary Raw Water Carbon Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.1 Cracking Plant Service Water and RHR Service Water Chemistry Control Program Thermowell / Pressure Boundary Raw Water Stainless Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.2 Cracking PSW and RHRSW Chemistry Control Program Valve Bodies / Pressure Boundary Raw Water Carbon Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.1 Flow Blockage PSW and RHRSW Chemistry Control Cracking Program Structural Monitoring Program Galvanic Susceptibility Inspections Valve Bodies / Pressure Boundary Raw Water Stainless Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.2 Flow Blockage PSW and RHRSW Chemistry Control Cracking Program Structural Monitoring Program Valve Bodies / Pressure Boundary Raw Water Copper Alloy Loss of Material PSW and RHRSW Chemistry Control C.2.2.6.3 Cracking Program Flow Blockage Structural Monitoring Program PSW and RHRSW Inspection Program Venturi / Pressure Boundary Raw Water Carbon Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.1 Flow Blockage PSW and RHRSW Chemistry Control Cracking Program Structural Monitoring Program Galvanic Susceptibility Inspections Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-40
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 292 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 292 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.4-13 Aging Effects Requiring Management for Components Supporting Reactor Building Crane [T31] Intended Functions and Their Component Functions Structural Component Component Functions Environment Material Aging Effects Aging Management Program/Activity Structural Steel/ Structural Support Inside Carbon Steel Loss of Material Overhead Crane and Refueling Platform C.2.6.3 Inspection Protective Coatings Program Structural Monitoring Program Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-47
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 293 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 293 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.4-16 Aging Effects Requiring Management for Components Supporting Traveling Water Screens / Trash Rack System [W33] Intended Functions and Their Component Functions Mechanical Component Component Functions Environment Material Aging Effects Aging Management Program/Activity Trash Rack / Debris Protection Submerged Carbon Steel Loss of Material Structural Monitoring Program C.2.6.3 Protective Coatings Program Traveling Screen / Debris Protection Submerged Carbon Steel Loss of Material Structural Monitoring Program C.2.6.3 Stainless Steel Traveling Screen / Debris Protection Submerged Copper Alloy None None Required C.2.6.3 Valve Bodies / Pressure Boundary Raw Water Carbon Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.1 Flow Blockage Plant Service Water and RHR Service Water Cracking Chemistry Control Program Galvanic Susceptibility Inspections Bolting / C.2.2.10.1 Pressure Boundary Outside Carbon Steel Loss of Material Torque Activities Loss of Preload Protective Coatings Program Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-50
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 294 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 294 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.4-18 Aging Effects Requiring Management for Components Supporting Fire Protection System [X43] Intended Functions and Their Intended Functions Component Aging Management Mechanical Component Functions Environment Material Aging Effects Program/Activity Boltings / C.2.2.10.1 Pressure Boundary Inside Carbon Steel Loss of Preload Torque Activities Outside Loss of Material Protective Coatings Program Fire Doors / C.2.3.4.3 Fire Barrier Inside Carbon Steel Loss of Material Fire Protection Activities Fire Doors / C.2.3.4.3 Fire Barrier Inside Galvanized Steel None None Required Copper Alloy Stainless Steel Aluminum Nonmettalic, Inorganic Gypsum Fibers, Nonasbestos Synthetic Nonmetallic, Organic Fire Hydrants / C.2.3.1 Pressure Boundary Raw Water Cast Iron Loss of Material Fire Protection Activities Cracking Flow Blockage Fittings / C.2.3.1 Pressure Boundary Raw Water Cast Iron Loss of Material Fire Protection Activities Air Cracking Flow Blockage Fittings / C.2.3.3 Pressure Boundary Air Copper Alloy Cracking Fire Protection Activities Cast Iron Loss of Material Fusible Material / C.2.3.1 Pressure Boundary Inside Nonferrous Metal Loss of Material Fire Protection Activities Cracking Kaowool and Hold-Down Fire Barrier Inside Galvanized Steel CrackingLoss of Fire Protection Activities Straps / C.2.3.4.3C.2.3.4.2 Insulation Material Material Change in Material Properties Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-52
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 295 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 295 of 363 Aging Management Review Results 3.3, Civil/Structural Table 3.3.1-3 Aging Effects Requiring Management for Components Supporting Primary Containment [T23] Intended Functions and Their Component Functions Structural Component Component Functions Environment Material Aging Effects Aging Management Program/Activity Anchors and Bolts / Structural Support; Containment Carbon Steel Loss of Material Protective Coatings Program C.2.6.2 Nonsafety Related Atmosphere; Galvanized Steel Inservice Inspection Program Structural Support Embedded; Inside Stainless Steel Suppression Pool Chemistry Control Torus Water Blind Flange* / Fission Product Barrier Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control C.2.2.3.1 Cracking Treated Water Systems Piping Inspections Containment Isolation Fission Product Barrier Demin Water Stainless Steel Loss of Material Demineralized Water and Condensate Valves* / C.2.2.2.2 Cracking Storage Tank Chemistry Control Treated Water Systems Piping Inspections Containment Isolation Fission Product Barrier Demin Water Carbon Steel Loss of Material Demineralized Water and Condensate Valves* / C.2.2.3.1 Cracking Storage Tank Chemistry Control Treated Water Systems Piping Inspections Containment Isolation Fission Product Barrier Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control Valves* / C.2.2.3.1 Treated Water Systems Piping Inspections Containment Isolation Fission Product Barrier Raw Water Carbon Steel Loss of Material Passive Component Inspection Activities Valves* / Cracking C.2.2.6.2C.2.6.2 Containment Isolation Fission Product Barrier Wetted Gas Carbon Steel Loss of Material Gas Systems Component Inspections Valves* / C.2.2.9.1 Passive Component Inspection Activities Containment Isolation Fission Product Barrier Wetted Gas Stainless Steel Loss of Material Gas Systems Component Inspection Valves* / C.2.2.9.2 Cracking Containment Fission Product Barrier Containment Carbon Steel Loss of Material Protective Coatings Program Penetrations Atmosphere; Stainless Steel Inservice Inspection Program (Mechanical only) / Embedded; Inside Primary Containment Leakage Rate Testing C.2.6.2 Program Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.3-4
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 296 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 296 of 363 Aging Management Review Results 3.3, Civil/Structural Table 3.3.1-3 Aging Effects Requiring Management for Components Supporting Primary Containment [T23] Intended Functions and Their Component Functions (Continued) Structural Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Structural Steel / Structural Support; Containment Carbon Steel Loss of Material Protective Coatings Program C.2.6.2 Shelter/Protection; Atmosphere; Stainless Steel Cracking Primary Containment Leakage Rate Pressure Boundary; Inside; Testing Program Radiation Shielding; Torus Water; Inservice Inspection Program Nonsafety Related Embedded Suppression Pool Chemistry Control Structural Support; Component Cyclic or Transient Limit HE/ME Shielding; Program Missile Barrier; Pipe Whip Restraint; Fission Product Barrier; Exchange Heat Tubing* / C.2.2.9.2 Fission Product Wetted Gas Stainless Steel Loss of Material Gas Systems Component Inspections Barrier; Cracking Pressure Boundary Vent Pipe, Vent Pressure Boundary Containment Carbon Steel Loss of Material Protective Coatings Program Header, Downcomers / Fission Product Barrier Atmosphere; Cracking Inservice Inspection Program C.2.6.2 High Humidity; Primary Containment Leakage Rate Inside; Testing Program Torus Water Component Cyclic or Transient Limit Program Suppression Pool Chemistry Control Bolting / C.2.2.10.1 Pressure Boundary Inside Carbon Steel Loss of Material Protective Coatings Program Containment Loss of Preload Torque Activities Atmosphere
- Piping and valve bodies include components from systems P51, P21, T23, G51, G11, D11, and C51. These are all included in function T23-01, Torus/Drywell.
Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.3-6
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 297 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 297 of 363 Aging Management Review Results 3.3, Civil/Structural Table 3.3.1-5 Aging Effects Requiring Management for Components Supporting Reactor Building [T29] Intended Functions and Their Component Functions Structural Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Anchors and Bolts / Structural Support; Inside; Outside Carbon Steel Loss of Material Protective Coatings Program C.2.6.3 Nonsafety Related Structural Monitoring Program Structural Support Blowout Panels / Structural Support; Inside Aluminum None None Required C.2.6.6 Fission Product Barrier Miscellaneous Steel / Structural Support; Inside; Outside Carbon Steel Loss of Material Structural Monitoring Program C.2.6.3 HE/ME Shielding; Galvanized Steel Protective Coatings Program Nonsafety Related Structural Support Miscellaneous Steel / Structural Support; Inside; Outside Stainless Steel None None Required C.2.6.3 HE/ME Shielding; Nonsafety Related Structural Support Panel Joint Seals and Shelter/Protection; Inside; Outside Elastomers; Material Property Structural Monitoring Program Sealants / C.2.6.7 Fission Product Barrier Nonmetallic, Changes and Protective Coatings Program Inorganic Cracking Loss of Adhesion Reinforced Concrete Structural Support; Inside; Outside Concrete Loss of Material Structural Monitoring Program C.2.6.1 Fire Barrier; Masonry Block Cracking Protective Coatings Program Shelter/Protection; Carbon Steel Flood Barrier; Fission Product Barrier; Radiation Shielding; Missile Barrier; HE/ME Shielding; Nonsafety Related Structural Support Structural Steel Structural Support; Inside; Outside; Carbon Steel Loss of Material Structural Monitoring Program C.2.6.3 Missile Barrier; Submerged Galvanized Steel Protective Coatings Program Nonsafety Related Stainless Steel Overhead Crane and Refueling Platform Structural Support Inspections Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.3-8
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 298 of 363 A-47039 Attachment C LICENSE Identification RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 298 of 363 of Commodities C.2, Aging Management Reviews C.2.2.3 Non-Class 1 Components Suppression Pool Water Environment Description Components within section C.2.2.3 are subject to an environment of suppression pool water under normal conditions. The suppression pool water environment is defined in section C.1.2.2. C.2.2.3.1 Aging Management Review for Non-Class 1 Carbon Steel Components Within the Suppression Pool Environment This commodity group consists of carbon steel commodities with an internal environment of suppression pool water or submerged within the suppression pool. The following component types are included within this evaluation:
- Piping
- Valve bodies
- Pump casings
- Thermowells
- Blind flange Systems B21 - Nuclear Boiler (2.3.1.2)
- E11 - Residual Heat Removal (2.3.3.2)
- E21 - Core Spray (2.3.3.3)
- E41 - High Pressure Coolant Injection (2.3.3.4)
- E51 - Reactor Core Isolation Cooling (2.3.3.5)
- T23 - Primary Containment (2.4.3)
- T48 - Primary Containment Purge and Inerting (2.3.3.7)
Aging Effects Requiring Management
- Loss of material (C.1.2.2.1) due to general corrosion, galvanic corrosion, crevice corrosion, pitting, microbiologically influenced corrosion (MIC), and erosion corrosion.
- Cracking (C.1.2.2.2) due to thermal fatigue.
A complete discussion of the applicable aging effect determinations may be found in section C.1 of the LRA or by using the above links. Aging Management Programs Aging management programs determined to manage aging effects requiring management are as follows:
- Suppression Pool Chemistry Control (A.1.7)
- Protective Coatings Program (A.2.3)
Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal C.2-60
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 299 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 299 of 363 From: Baker, Ray D. Sent: Friday, May 05, 2000 10:54 AM To: 'William F. Burton (E-mail)'
Subject:
Follow Up to 514100 Telecon
- Butch, In the telecon, I committed to provide you with the line items for a vertical slice of the application for the SRV discharge lines. The following references are provided that show how the information is developed in the application:
- Page 2.2-2 Table 2.2-1 Function B21-02 This function includes the SRV discharge lines.
- Pages 2.3-5, -6 A discussion of intended function B21-02 is provided.
- Page 2.3-7 Table 2.3.1-2 Line items 4 and 5 are for carbon steel and stainless steel non-class 1 piping. The SRV discharge lines are carbon steel except for the part that is submerged in the torus, which is stainless steel. This table provides the component functions that support intended function B21-02. The component functions are pressure boundary and fission product barrier. This table presents the scoping/screening results
- Pages 3.2-5 through 3.2-8 Table 3.2.1-2 This table is the corresponding table for presentation of aging management review results. The corresponding line items in this table are on page 3.2-6. The carbon steel SRV discharge line piping is the last item on the page. The stainless steel SRV discharge line piping is included in the third line item on the page. Please refer to the attached annotated pages file for the markups associated with this page. An additional markup has been provided for this page for the last line item on the page. The line item entry is for non-Class 1 rather than Class 1 piping with a wetted gas environment. The commodity reference correctly indicates this and links to the correct section of the application.
- The stainless steel line item indicates that the aging management review and demonstration can be found in section C.2.2.3.2 (pages C.2-66 through -71) and that the activities credited for managing the applicable aging effects are Suppression Pool Chemistry Control (A.1.7) and the Torus Submerged Components Inspection Program (A.3.7).
- The carbon steel line item indicates that the aging management review and demonstration can be found in section C.2.2.9.1 (pages C.2-114 through -117) and that the activities credited for managing the applicable aging effects are Gas Systems Components Inspection (A.3.3) and the Passive Component Inspection Activities (A.3.5).
Please let me know if we can be of further assistance regarding this question. Ray Baker 8-992-7367 '~/ways do right. This will gratify some people and astonish the rest." -- Mark Twain annotated_page_m arkups.pdf (49 ...
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 300 of 363 A-47039 Attachment C LICENSE Structures RENEWAL and Components AGING Subject to MANAGEMENT Aging Management REVIEW
SUMMARY
SHEET 300 of 363 Review 2.3, Mechanical Systems Screening Results Component Groups Requiring an Aging Management Review Table 2.3.4-16 Components Supporting Traveling Water Screens/ Trash Rack System [W33] Intended Functions and Their Component Functions Mechanical Component Component Functions Material Bolting Pressure Boundary Carbon Steel Sight Glasses* Pressure Boundary Ceramic Trash Racks Debris Protection Carbon Steel Traveling Screen Debris Protection Carbon Steel Stainless Steel Copper Alloy* Valve Bodies Pressure Boundary Carbon Steel
- No aging effects requiring management Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 2.3-60
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 301 of 363 A-47039 Attachment C LICENSE Structures RENEWAL and Components AGING Subject to MANAGEMENT Aging Management REVIEW
SUMMARY
SHEET 301 of 363 Review 2.3, Mechanical Systems Screening Results Component Groups Requiring an Aging Management Review Table 2.3.4-18 Components Supporting Fire Protection System [X43] Intended Functions and Their Component Functions Mechanical Component Component Functions Material Bolting Pressure Boundary Carbon Steel Fire Doors Fire Barrier Carbon Steel Galvanized Steel Copper Alloy Stainless Steel Aluminum Nonmetallic, Inorganic-Gypsum Fibers, nonasbestos synthetic Nonmetallic, organic Fire Hydrants Pressure Boundary Cast Iron Fittings Pressure Boundary Cast Iron Fittings Pressure Boundary Copper Alloy Cast Iron Fusible Material Pressure Boundary Nonferrous Metal Kaowool and Hold-down Straps Fire Barrier Galvanized Steel, Insulation material Nozzles Flow Restriction Aluminum Copper Alloy Nozzles Flow Restriction Copper Alloy Penetration Seals Fire Barrier Concrete Ceramics Carbon Steel Synthetic Fiber Elastomers Pilot Valves Pressure Boundary Aluminum Pipe Line Strainers Pressure Boundary Cast Iron Piping Pressure Boundary Carbon Steel Aluminum Galvanized Steel Copper Alloy Cast Iron Piping Pressure Boundary Carbon Steel Stainless Steel Piping Pressure Boundary Carbon Steel Galvanized Steel Pump Casings Pressure Boundary Cast Iron Restricting Orifices Pressure Boundary, Flow Stainless Steel Restriction Sprinkler Head Bulbs Pressure Boundary Ceramics Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 2.3-66
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 302 of 363 A-47039 Attachment C LICENSE Structures RENEWAL and Components AGING Subject to MANAGEMENT Aging Management REVIEW Review
SUMMARY
SHEET 302 of 363 2.4, Structures Screening Results Component Groups Requiring an Aging Management Review Table 2.4.3-1 Components Supporting Primary Containment [T23] Intended Functions and Their Component Functions Structural Component Component Functions Material Anchors and Bolts Structural Support; Carbon Steel Nonsafety Related Structural Support Galvanized Steel Stainless Steel Blind Flange* Fission Product Barrier Carbon Steel Bolting* Fission Product Barrier Carbon Steel Containment Isolation Valves
- Fission Product Barrier Carbon Steel Containment Isolation Valves* Fission Product Barrier Stainless Steel Containment Penetrations Fission Product Barrier Carbon Steel (Mechanical only) Stainless Steel Miscellaneous Steel Structural Support; Carbon Steel Radiation Shielding; Galvanized Steel Pipe Whip Restraint; Nonsafety Related Structural Support Piping* Fission Product Barrier Carbon Steel Piping* Fission Product Barrier Stainless Steel Reinforced Concrete Structural Support; Concrete Shelter/Protection; Carbon Steel Flood Barrier; Fission Product Barrier; Radiation Shielding; Missile Barrier; HE/ME Shielding Steel Bellows (inside Vent Pipe) Pressure Boundary; Carbon Steel Fission Product Barrier Stainless Steel Structural Steel Structural Support; Carbon Steel Shelter/Protection; Stainless Steel Radiation Shielding; Missile Barrier; HE/ME Shielding; Pipe Whip Restraint; Nonsafety Related Structural Support; Pressure Boundary Fission Product Barrier; Exchange Heat Tubing* Fission Product Barrier; Pressure Stainless Steel Boundary Unreinforced Concrete Radiation Shielding Unreinforced Concrete**
Vent Pipe, Vent Header, Fission Product Barrier; Carbon Steel Downcomers Pressure Boundary
- Piping and valves include components from systems P51, P21, T23, G51, G11, D11, and C51. These are all included in function T23-01, Torus/Drywell.
** No aging effects requiring management Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 2.4-6
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 303 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 303 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.1-2 Aging Effects Requiring Management for Components Supporting Nuclear Boiler System [B21] Intended Functions and Their Component Functions Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Bolting / C.2.1.1.6 Pressure Boundary Inside Carbon Steel Loss of Preload Torque Activities (Class 1) Fission Product Inservice Inspection Program Barrier Bolting / C.2.2.10.1 Pressure Boundary Inside Carbon Steel Loss of Preload Torque Activities (non-Class 1) Fission Product Loss of Material Protective Coatings Program Barrier Crack Growth Monitor / Pressure Boundary Reactor Water Stainless Steel Loss of Material Reactor Water Chemistry Control C.2.1.1.4 Fission Product Cracking Inservice Inspection Program (Class 1) Barrier Component Cyclic or Transient Limit Program Treated Water Systems Piping Inspections Flow Nozzle / C.2.1.1.3 Pressure Boundary Reactor Water Carbon Steel Loss of Material Reactor Water Chemistry Control (Class 1) Fission Product Cracking Inservice Inspection Program Barrier Galvanic Susceptibility Inspections Component Cyclic or Transient Limit Program Flow Accelerated Corrosion Program Treated Water Systems Piping Inspections Piping / C.2.2.1.1 Pressure Boundary Reactor Water Carbon Steel Loss of Material Reactor Water Chemistry Control (non-Class 1) Fission Product Cracking Galvanic Susceptibility Inspections Barrier Treated Water Systems Piping Inspections Flow Accelerated Corrosion Program Piping / C.2.2.1.2 Pressure Boundary Reactor Water Stainless Steel Loss of Material Reactor Water Chemistry Control (non-Class 1) Fission Product Cracking Treated Water Systems Piping Barrier Inspections Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-5
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 304 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 304 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.1-2 Aging Effects Requiring Management for Components Supporting Nuclear Boiler System [B21] Intended Functions and Their Component Functions (Continued) Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Piping / C.2.2.2.2 Pressure Boundary Demin Water Stainless Steel Loss of Material Demineralized Water and Condensate (non-Class 1) Fission Product Cracking Storage Tank Chemistry Control Barrier Treated Water Systems Piping Inspections Piping / C.2.2.3.1 Pressure Boundary Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control (non-Class 1) Fission Product Cracking Torus Submerged Components Barrier Inspection Program Piping / C.2.2.3.2 Pressure Boundary Torus Water Stainless Steel Loss of Material Suppression Pool Chemistry Control (non-Class 1) Fission Product Cracking Torus Submerged Components Barrier Inspection Program Piping / C.2.1.1.3 Pressure Boundary Reactor Water Carbon Steel Loss of Material Reactor Water Chemistry Control (Class 1) Fission Product Cracking Inservice Inspection Program Barrier Galvanic Susceptibility Inspections Component Cyclic or Transient Limit Program Flow Accelerated Corrosion Program Treated Water Systems Piping Inspections Piping / C.2.1.1.4 Pressure Boundary Reactor Water Stainless Steel Loss of Material Reactor Water Chemistry Control (Class 1) Fission Product Cracking Inservice Inspection Program Barrier Component Cyclic or Transient Limit Program Treated Water Systems Piping Inspections Piping / C.2.2.9.1 Pressure Boundary Wetted Gas Carbon Steel Loss of Material Inservice Inspection Program (non-Class 1) Fission Product Cracking Gas Systems Component Inspections Barrier Passive Component Inspection Activities Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-6
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 305 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 305 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.1-2 Aging Effects Requiring Management for Components Supporting Nuclear Boiler System [B21] Intended Functions and Their Component Functions (Continued) Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Restricting Orifice / Pressure Boundary Reactor Water Stainless Steel Loss of Material Reactor Water Chemistry Control C.2.1.1.4 Fission Product Cracking Component Cyclic or Transient Limit (Class 1) Barrier Program Inservice Inspection Program Treated Water Systems Piping Inspections Thermowell/ Pressure Boundary Wetted Gas Carbon Steel Loss of Material Gas Systems Component Inspections C.2.2.9.1 Fission Product Cracking Passive Component Inspection (non-Class 1) Barrier Activities Thermowell / Pressure Boundary Reactor Water Stainless Steel Loss of Material Reactor Water Chemistry Control C.2.1.1.4 Fission Product Cracking Inservice Inspection Program (Class 1) Barrier Component Cyclic or Transient Limit Program Treated Water Systems Piping Inspections Valve Bodies / C.2.2.1.1 Pressure Boundary Reactor Water Carbon Steel Loss of Material Reactor Water Chemistry Control (non-Class 1) Fission Product Cracking Flow Accelerated Corrosion Program Barrier Galvanic Susceptibility Inspections Treated Water Systems Piping Inspections Valve Bodies / C.2.2.1.2 Pressure Boundary Reactor Water Stainless Steel Loss of Material Reactor Water Chemistry Control (non-Class 1) Fission Product Cracking Treated Water Systems Piping Barrier Inspections Valve Bodies / C.2.2.9.1 Pressure Boundary Wetted Gas Carbon Steel Loss of Material Gas Systems Component Inspections (non-Class 1) Fission Product Cracking Inservice Inspection Program Barrier Passive Component Inspection Activities Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-7
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 306 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 306 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.3-4 Aging Effects Requiring Management for Components Supporting High Pressure Coolant Injection System [E41] Intended Functions and Their Component Functions Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Bolting / C.2.2.10.1 Pressure Boundary Inside Carbon Steel Loss of Preload Torque Activities Fission Product Barrier Loss of Material Protective Coatings Program Bolting / C.2.2.10.2 Pressure Boundary Inside Stainless Steel Loss of Preload Torque Activities Fission Product Barrier Flexible Connector / Pressure Boundary Dry Wetted Gas Stainless Steel Cracking Gas Systems Component Inspections C.2.2.9.2 Fission Product Barrier Loss of Material Piping / C.2.2.1.1 Pressure Boundary Reactor Water Carbon Steel Loss of Material Reactor Water Chemistry Control Fission Product Barrier Cracking Galvanic Susceptibility Inspections Flow Accelerated Corrosion Program Treated Water Systems Piping Inspections Piping / C.2.2.2.1 Pressure Boundary Demin Water Carbon Steel Loss of Material Demineralized Water and Condensate Fission Product Barrier Cracking Storage Tank Chemistry Control Treated Water Systems Piping Inspections Piping / C.2.2.2.2 Pressure Boundary Demin Water Stainless Steel Loss of Material Demineralized Water and Condensate Fission Product Barrier Cracking Storage Tank Chemistry Control Program Treated Water Systems Piping Inspections Piping / C.2.2.3.1 Pressure Boundary Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control Fission Product Barrier Cracking Galvanic Susceptibility Inspections Treated Water Systems Piping Inspections Torus Submerged Components Inspection Program Protective Coatings Program Piping / C.2.2.3.2 Pressure Boundary Torus Water Stainless Steel Loss of Material Suppression Pool Chemistry Control Fission Product Barrier Cracking Torus Submerged Components Inspection Program Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-17
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 307 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 307 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.3-5 Aging Effects Requiring Management for Components Supporting Reactor Core Isolation Cooling System [E51] Intended Functions and Their Component Functions (Continued) Mechanical Component Environment Material Aging Effects Aging Management Program/ Component Functions Activity Valve Bodies / C.2.2.9.2 Pressure Boundary Wetted Gas Stainless Steel Loss of Material Gas Systems Component Inspections Fission Product Cracking Passive Component Inspection Activities Barrier Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-25
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 308 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 308 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.3-7 Aging Effects Requiring Management for Components Supporting Primary Containment Purge and Inerting System [T48] Intended Functions and Their Component Functions Component Aging Management Mechanical Component Functions Environment Material Aging Effects Program/Activity Bolting / C.2.2.10.1 Pressure Boundary Inside Carbon Steel Loss of Preload Torque Activities Loss of Material Protective Coatings Program Bolting / C.2.2.10.2 Pressure Boundary Inside Stainless Steel Loss of Preload Torque Activities Flex Hose / C.2.2.9.1 Pressure Boundary Air Stainless Steel Cracking Gas Systems Component Inspections Nitrogen Tank Jacket / C.2.2.9.1 Structural Support Air Carbon Steel Cracking Gas Systems Component Inspections Loss of Material Passive Component Inspection Activities Piping / C.2.2.3.1 Pressure Boundary Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control Cracking Galvanic Susceptibility Inspections Torus Submerged Components Inspection Program Protective Coatings Program Piping / C.2.2.3.1 Pressure Boundary Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control Cracking Torus Submerged Components Inspection Program Piping / C.2.2.3.2 Pressure Boundary Torus Water Stainless Steel Loss of Material Suppression Pool Chemistry Control Cracking Treated Water Systems Piping Inspections Piping / C.2.2.8.2 Pressure Boundary Dried Gas Stainless Steel Cracking None Required Piping / C.2.2.9.1 Pressure Boundary Wetted Gas Carbon Steel Cracking Gas Systems Component Inspections Loss of Material Passive Component Inspection Activities Pressure Buildup Coil / C.2.2.8.2 Pressure Boundary Dried Gas Stainless Steel Cracking None Required Exchange Heat Rupture Disc / C.2.2.8.2 Pressure Boundary Dried Gas Stainless Steel Cracking None Required Storage Tank / C.2.2.8.2 Pressure Boundary Dried Gas Stainless Steel Cracking None Required Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-28
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 309 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 309 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.4-2 Aging Effects Requiring Management for Components Supporting Refueling Platform Equipment Assembly [F15] Intended Functions and Their Component Functions Structural Component Component Functions Environment Material Aging Effects Aging Management Program/Activity Anchors and Structural support Inside Carbon steel Loss of material Protective Coatings Program Bolts Nonsafety Related Overhead Crane and Refueling Platform C.2.6.3 Structural Support Inspection Structural Monitoring Program Miscellaneous Structural support; Inside Carbon steel Loss of material Protective Coatings Program Steel Nonsafety Related Overhead Crane and Refueling Platform C.2.6.3 Structural Support Inspection Structural Monitoring Program Rivets Structural Support Inside Aluminum None None Required Structural Steel Structural support Inside Carbon steel Loss of material Protective Coatings Program C.2.6.3 Overhead Crane and Refueling Platform Inspection Structural Monitoring Program Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-33
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 310 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 310 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.4-7 Aging Effects Requiring Management for Components Supporting Plant Service Water System [P41] Intended Functions and Their Component Functions (Continued) Mechanical Component Component Functions Environment Material Aging Effects Aging Management Program/Activity Thermowell / Pressure Boundary Raw Water Carbon Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.1 Cracking Plant Service Water and RHR Service Water Chemistry Control Program Thermowell / Pressure Boundary Raw Water Stainless Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.2 Cracking PSW and RHRSW Chemistry Control Program Valve Bodies / Pressure Boundary Raw Water Carbon Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.1 Flow Blockage PSW and RHRSW Chemistry Control Cracking Program Structural Monitoring Program Galvanic Susceptibility Inspections Valve Bodies / Pressure Boundary Raw Water Stainless Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.2 Flow Blockage PSW and RHRSW Chemistry Control Cracking Program Structural Monitoring Program Valve Bodies / Pressure Boundary Raw Water Copper Alloy Loss of Material PSW and RHRSW Chemistry Control C.2.2.6.3 Cracking Program Flow Blockage Structural Monitoring Program PSW and RHRSW Inspection Program Venturi / Pressure Boundary Raw Water Carbon Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.1 Flow Blockage PSW and RHRSW Chemistry Control Cracking Program Structural Monitoring Program Galvanic Susceptibility Inspections Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-40
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 311 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 311 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.4-13 Aging Effects Requiring Management for Components Supporting Reactor Building Crane [T31] Intended Functions and Their Component Functions Structural Component Component Functions Environment Material Aging Effects Aging Management Program/Activity Structural Steel/ Structural Support Inside Carbon Steel Loss of Material Overhead Crane and Refueling Platform C.2.6.3 Inspection Protective Coatings Program Structural Monitoring Program Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-47
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 312 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 312 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.4-16 Aging Effects Requiring Management for Components Supporting Traveling Water Screens / Trash Rack System [W33] Intended Functions and Their Component Functions Mechanical Component Component Functions Environment Material Aging Effects Aging Management Program/Activity Trash Rack / Debris Protection Submerged Carbon Steel Loss of Material Structural Monitoring Program C.2.6.3 Protective Coatings Program Traveling Screen / Debris Protection Submerged Carbon Steel Loss of Material Structural Monitoring Program C.2.6.3 Stainless Steel Traveling Screen / Debris Protection Submerged Copper Alloy None None Required C.2.6.3 Valve Bodies / Pressure Boundary Raw Water Carbon Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.1 Flow Blockage Plant Service Water and RHR Service Water Cracking Chemistry Control Program Galvanic Susceptibility Inspections Bolting / C.2.2.10.1 Pressure Boundary Outside Carbon Steel Loss of Material Torque Activities Loss of Preload Protective Coatings Program Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-50
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 313 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 313 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.4-18 Aging Effects Requiring Management for Components Supporting Fire Protection System [X43] Intended Functions and Their Intended Functions Component Aging Management Mechanical Component Functions Environment Material Aging Effects Program/Activity Boltings / C.2.2.10.1 Pressure Boundary Inside Carbon Steel Loss of Preload Torque Activities Outside Loss of Material Protective Coatings Program Fire Doors / C.2.3.4.3 Fire Barrier Inside Carbon Steel Loss of Material Fire Protection Activities Fire Doors / C.2.3.4.3 Fire Barrier Inside Galvanized Steel None None Required Copper Alloy Stainless Steel Aluminum Nonmettalic, Inorganic Gypsum Fibers, Nonasbestos Synthetic Nonmetallic, Organic Fire Hydrants / C.2.3.1 Pressure Boundary Raw Water Cast Iron Loss of Material Fire Protection Activities Cracking Flow Blockage Fittings / C.2.3.1 Pressure Boundary Raw Water Cast Iron Loss of Material Fire Protection Activities Air Cracking Flow Blockage Fittings / C.2.3.3 Pressure Boundary Air Copper Alloy Cracking Fire Protection Activities Cast Iron Loss of Material Fusible Material / C.2.3.1 Pressure Boundary Inside Nonferrous Metal Loss of Material Fire Protection Activities Cracking Kaowool and Hold-Down Fire Barrier Inside Galvanized Steel CrackingLoss of Fire Protection Activities Straps / C.2.3.4.3C.2.3.4.2 Insulation Material Material Change in Material Properties Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-52
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 314 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 314 of 363 Aging Management Review Results 3.3, Civil/Structural Table 3.3.1-3 Aging Effects Requiring Management for Components Supporting Primary Containment [T23] Intended Functions and Their Component Functions Structural Component Component Functions Environment Material Aging Effects Aging Management Program/Activity Anchors and Bolts / Structural Support; Containment Carbon Steel Loss of Material Protective Coatings Program C.2.6.2 Nonsafety Related Atmosphere; Galvanized Steel Inservice Inspection Program Structural Support Embedded; Inside Stainless Steel Suppression Pool Chemistry Control Torus Water Blind Flange* / Fission Product Barrier Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control C.2.2.3.1 Cracking Treated Water Systems Piping Inspections Containment Isolation Fission Product Barrier Demin Water Stainless Steel Loss of Material Demineralized Water and Condensate Valves* / C.2.2.2.2 Cracking Storage Tank Chemistry Control Treated Water Systems Piping Inspections Containment Isolation Fission Product Barrier Demin Water Carbon Steel Loss of Material Demineralized Water and Condensate Valves* / C.2.2.3.1 Cracking Storage Tank Chemistry Control Treated Water Systems Piping Inspections Containment Isolation Fission Product Barrier Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control Valves* / C.2.2.3.1 Treated Water Systems Piping Inspections Containment Isolation Fission Product Barrier Raw Water Carbon Steel Loss of Material Passive Component Inspection Activities Valves* / Cracking C.2.2.6.2C.2.6.2 Containment Isolation Fission Product Barrier Wetted Gas Carbon Steel Loss of Material Gas Systems Component Inspections Valves* / C.2.2.9.1 Passive Component Inspection Activities Containment Isolation Fission Product Barrier Wetted Gas Stainless Steel Loss of Material Gas Systems Component Inspection Valves* / C.2.2.9.2 Cracking Containment Fission Product Barrier Containment Carbon Steel Loss of Material Protective Coatings Program Penetrations Atmosphere; Stainless Steel Inservice Inspection Program (Mechanical only) / Embedded; Inside Primary Containment Leakage Rate Testing C.2.6.2 Program Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.3-4
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 315 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 315 of 363 Aging Management Review Results 3.3, Civil/Structural Table 3.3.1-3 Aging Effects Requiring Management for Components Supporting Primary Containment [T23] Intended Functions and Their Component Functions (Continued) Structural Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Structural Steel / Structural Support; Containment Carbon Steel Loss of Material Protective Coatings Program C.2.6.2 Shelter/Protection; Atmosphere; Stainless Steel Cracking Primary Containment Leakage Rate Pressure Boundary; Inside; Testing Program Radiation Shielding; Torus Water; Inservice Inspection Program Nonsafety Related Embedded Suppression Pool Chemistry Control Structural Support; Component Cyclic or Transient Limit HE/ME Shielding; Program Missile Barrier; Pipe Whip Restraint; Fission Product Barrier; Exchange Heat Tubing* / C.2.2.9.2 Fission Product Wetted Gas Stainless Steel Loss of Material Gas Systems Component Inspections Barrier; Cracking Pressure Boundary Vent Pipe, Vent Pressure Boundary Containment Carbon Steel Loss of Material Protective Coatings Program Header, Downcomers / Fission Product Barrier Atmosphere; Cracking Inservice Inspection Program C.2.6.2 High Humidity; Primary Containment Leakage Rate Inside; Testing Program Torus Water Component Cyclic or Transient Limit Program Suppression Pool Chemistry Control Bolting / C.2.2.10.1 Pressure Boundary Inside Carbon Steel Loss of Material Protective Coatings Program Containment Loss of Preload Torque Activities Atmosphere
- Piping and valve bodies include components from systems P51, P21, T23, G51, G11, D11, and C51. These are all included in function T23-01, Torus/Drywell.
Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.3-6
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 316 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 316 of 363 Aging Management Review Results 3.3, Civil/Structural Table 3.3.1-5 Aging Effects Requiring Management for Components Supporting Reactor Building [T29] Intended Functions and Their Component Functions Structural Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Anchors and Bolts / Structural Support; Inside; Outside Carbon Steel Loss of Material Protective Coatings Program C.2.6.3 Nonsafety Related Structural Monitoring Program Structural Support Blowout Panels / Structural Support; Inside Aluminum None None Required C.2.6.6 Fission Product Barrier Miscellaneous Steel / Structural Support; Inside; Outside Carbon Steel Loss of Material Structural Monitoring Program C.2.6.3 HE/ME Shielding; Galvanized Steel Protective Coatings Program Nonsafety Related Structural Support Miscellaneous Steel / Structural Support; Inside; Outside Stainless Steel None None Required C.2.6.3 HE/ME Shielding; Nonsafety Related Structural Support Panel Joint Seals and Shelter/Protection; Inside; Outside Elastomers; Material Property Structural Monitoring Program Sealants / C.2.6.7 Fission Product Barrier Nonmetallic, Changes and Protective Coatings Program Inorganic Cracking Loss of Adhesion Reinforced Concrete Structural Support; Inside; Outside Concrete Loss of Material Structural Monitoring Program C.2.6.1 Fire Barrier; Masonry Block Cracking Protective Coatings Program Shelter/Protection; Carbon Steel Flood Barrier; Fission Product Barrier; Radiation Shielding; Missile Barrier; HE/ME Shielding; Nonsafety Related Structural Support Structural Steel Structural Support; Inside; Outside; Carbon Steel Loss of Material Structural Monitoring Program C.2.6.3 Missile Barrier; Submerged Galvanized Steel Protective Coatings Program Nonsafety Related Stainless Steel Overhead Crane and Refueling Platform Structural Support Inspections Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.3-8
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 317 of 363 A-47039 Attachment C LICENSE Identification RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 317 of 363 of Commodities C.2, Aging Management Reviews C.2.2.3 Non-Class 1 Components Suppression Pool Water Environment Description Components within section C.2.2.3 are subject to an environment of suppression pool water under normal conditions. The suppression pool water environment is defined in section C.1.2.2. C.2.2.3.1 Aging Management Review for Non-Class 1 Carbon Steel Components Within the Suppression Pool Environment This commodity group consists of carbon steel commodities with an internal environment of suppression pool water or submerged within the suppression pool. The following component types are included within this evaluation:
- Piping
- Valve bodies
- Pump casings
- Thermowells
- Blind flange Systems B21 - Nuclear Boiler (2.3.1.2)
- E11 - Residual Heat Removal (2.3.3.2)
- E21 - Core Spray (2.3.3.3)
- E41 - High Pressure Coolant Injection (2.3.3.4)
- E51 - Reactor Core Isolation Cooling (2.3.3.5)
- T23 - Primary Containment (2.4.3)
- T48 - Primary Containment Purge and Inerting (2.3.3.7)
Aging Effects Requiring Management
- Loss of material (C.1.2.2.1) due to general corrosion, galvanic corrosion, crevice corrosion, pitting, microbiologically influenced corrosion (MIC), and erosion corrosion.
- Cracking (C.1.2.2.2) due to thermal fatigue.
A complete discussion of the applicable aging effect determinations may be found in section C.1 of the LRA or by using the above links. Aging Management Programs Aging management programs determined to manage aging effects requiring management are as follows:
- Suppression Pool Chemistry Control (A.1.7)
- Protective Coatings Program (A.2.3)
Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal C.2-60
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 318 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 318 of 363 From: Baker, Ray D. Sent: Tuesday, May 23, 2000 8:43 AM To: 'William F. Burton (E-mail)'
Subject:
Oglethorpe Power Corporation Board Changes
- Butch, In response to your follow-up request regarding the recent Oglethorpe Power Corporation board changes, I am providing as attachment to this memo, a red-line/strikeout markup of the applicable pabes in the application. Also provided are the remaining pages to the end of the section since page breaks were affected by the markup. This markup is consistent with the information provided to Southern Nuclear by OPC.
As previously noted, the principal OPC officers and board members listed are U.S. citizens. Please let me know if you have any additional questions regarding this item. Ray Baker 8-992-7367 '~/ways do right. This will gratify some people and astonish the rest." -- Mark Twain ATTAHCMENT sec1_0PC.pdf (111 KB)
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 319 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 319 of 363 Introduction 1.1, General Information - 10 CFR 54.19 Patrick Bowie, P. O. Box 430 Board Member LaGrange, Georgia 30241 The Honorable Ansley L. Meaders, 205 Lawrence Street Board Member Marietta, Georgia 30061 Roland C. Stubbs Jr., 113 Sylvan Terrace Board Member Sylvania, Georgia 30467 The Honorable Gerald Thompson P. O. Box 425 Board Member Fitzgerald, Georgia 31750 Kerry Waldron, P. O. Box 672 Board Member Thomaston, Georgia 30286-0009 Joel T. Wood P. O. Box 487 Board Member West Point, Georgia 31833 Principal Officers Robert P. Johnston, 14370 Riveredge Pkwy. NW President Atlanta, Georgia 30328 Mary Jackson, 14370 Riveredge Pkwy. NW Vice President and Atlanta, Georgia 30328 Chief Financial Officer James Fuller, 14370 Riveredge Pkwy. NW Treasurer Atlanta, Georgia 30328 MEAG is neither owned, controlled, nor dominated by an alien, foreign corporation, or foreign government. OGLETHORPE POWER CORPORATION Oglethorpe Power Corporation (an Electric Membership Corporation) operating on a not-for-profit basis, was organized under the Georgia Electric Membership Corporation Act (Official Code of Georgia Annotated, Title 46, Chapter 3, Article 4) and other applicable laws of the State of Georgia. The names and addresses of Oglethorpes principal officers and the members of its governing body, all of whom are citizens of the United States, are as follows: Board of Directors J. Calvin Earwood, 2100 East Exchange Place Chairman Tucker, GA 30085-1349 Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 1.1-6
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 320 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 320 of 363 Introduction 1.1, General Information - 10 CFR 54.19 Benny W. DenhamSam Rabun, 2100 East Exchange Place Vice Chairman Tucker, GA 30085-1349 Central Regional Director Mac F. Oglesby, 2100 East Exchange Place Treasurer Tucker, GA 30085-1349 Larry N. Chadwick, 2100 East Exchange Place NW Regional Director Tucker, GA 30085-1349 Sammy Jenkins, 2100 East Exchange Place SE Regional Director Tucker, GA 30085-1349 Sam RabunBenny W. Denham, 2100 East Exchange Place Central SW Regional Director Tucker, GA 30085-1349 Ashley C. Brown, 2100 East Exchange Place Outside Director Tucker, GA 30085-1349 Newton A. Campbell, 2100 East Exchange Place Outside Director Tucker, GA 30085-1349 Wm. Ronald Duffy, 2100 East Exchange Place Outside Director Tucker, GA 30085-1349 John S. Ranson, 2100 East Exchange Place Outside Director Tucker, GA 30085-1349 Jeffrey D. Tranen 2100 East Exchange Place Outside Director Tucker, GA 30085-1349 Principal Officers Thomas A. Smith, 2100 East Exchange Place President and Chief Executive Officer Tucker, GA 30085-1349 Michael W. Price, 2100 East Exchange Place Chief Operating Officer Tucker, GA 30085-1349 W. Clayton Robbins, 2100 East Exchange Place Senior Vice President, Tucker, GA 30085-1349 Finance and Administration Clarence D. Mitchell, 2100 East Exchange Place Senior Vice President, Tucker, GA 30085-1349 Operations and Projects Betsy Higgins, 2100 East Exchange Place Vice President, Tucker, GA 30085-1349 Assistant to the CEO Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 1.1-7
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 321 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 321 of 363 Introduction 1.1, General Information - 10 CFR 54.19 Dale R. Murphy, 2100 East Exchange Place Vice President, Tucker, GA 30085-1349 Planning and Administration Robert D. Steele, 2100 East Exchange Place Vice President, Tucker, GA 30085-1349 External Affairs Glenn Loomer 2100 East Exchange Place Vice President, Tucker, GA 30085-1349 Contracts Administration and Analysis Willie Collins, 2100 East Exchange Place Controller and Chief Risk Officer Tucker, GA 30085-1349 James E. Kofron, 2100 East Exchange Place Corporate Treasurer Tucker, GA 30085-1349 Patricia N. Nash, 2100 East Exchange Place Corporate Secretary Tucker, GA 30085-1349 Oglethorpe is neither owned, controlled, nor dominated by an alien, foreign corporation, or foreign government. CITY OF DALTON The names and addresses of Daltons governing body (councilmen) and principal officers (mayor and city administrator), all of whom are citizens of the United States, are as follows: Councilmen Ray Elrod, 1508 Rio Vista Drive Mayor Dalton, GA 30720 Bobby Joe Grant Paramount Printing P. O. Box 4569 Dalton, GA 30719-4569 Charles Whitener 123 Lisa Lane Dalton, GA 30720 Terry Christie 607 Murray Hill Drive Dalton, GA 30720 Michael Robinson 2006 West Brookhaven Circle Dalton, GA 30720 Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 1.1-8
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 322 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 322 of 363 Introduction 1.1, General Information - 10 CFR 54.19 Officers Ray Elrod, 1508 Rio Vista Drive Mayor Dalton, GA 30720 Butch Sanders, City Hall City Administrator P. O. Box 1205 Dalton, GA 30722-1205 Faye Martin, City Hall City Clerk P. O. Box 1205 Dalton, GA 30722-1205 Dalton is neither owned, controlled, nor dominated by an alien, foreign corporation, or foreign government. The names and addresses of Dalton Utilities governing body (Commissioners) and principal officers (chairman, president/chief executive officer, and secretary), all of whom are citizens of the United States, are as follows: Commissioners Justin Robinson 2203 Druid Lane Chairman Dalton, GA 30720 Norman D. Burkett 2209 Rocky Face Circle Vice Chairman Dalton, GA 30720 Todd Reigel c/o Paradigm Printing, Inc. Secretary 429 Virgil Drive Dalton, GA 30720 George Mitchell c/o Dalton Paving & Construction Company 530 North Elm Street Dalton, GA 30720 Jim Bethel c/o J & J Industries, Inc. 818 J & J Drive Dalton, GA 30720 Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 1.1-9
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 323 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 323 of 363 Introduction 1.1, General Information - 10 CFR 54.19 Officers Justin Robinson 2203 Druid Lane Chairman Dalton, GA 30720 Don Cope 1200 V. D. Parrott, Jr. Parkway President/Chief Executive Officer Dalton, GA 30720 Todd Reigel c/o Paradigm Printing, Inc. Secretary 429 Virgil Drive Dalton, GA 30720 1.1.5 CLASS OF LICENSE, USE OF THE FACILITY, AND PERIOD OF TIME FOR WHICH THE LICENSE IS SOUGHT SNC requests a Class 104 operating license for Plant Hatch Unit 1 and a Class 103 operating license for Unit 2 (License Nos. DPR-57 and NPF-5, respectively) for a period 20 years beyond the expiration of the current licenses, midnight, August 6, 2014 for Unit 1 and midnight, June 13, 2018 for Unit 2. Because the current licensing basis is carried forward with the possible exception of some aging issues, Southern Nuclear expects the form and content of the licenses to be generally the same as they now exist. Southern Nuclear, thus, also requires similar extensions of specific licenses under Parts 30, 40, and 70 that are contained in the current operating licenses. 1.1.6 EARLIEST AND LATEST DATES FOR ALTERATIONS, IF PROPOSED No physical plant alterations or modifications have been identified as necessary in order to implement the provisions of this application. 1.1.7 RESTRICTED DATA With regard to the requirements of 10 CFR 54.17(f), this application does not contain any Restricted Data, as that term is defined in the Atomic Energy Act of 1954, as amended, or other defense information, and it is not expected that any such information will become involved in these licensed activities. In accordance with the requirements of 10 CFR 54.17(g), the applicants will not permit any individual to have access to, or any facility to possess restricted data or classified national security information until the individual and/or facility has been approved for such access under the provisions of 10 CFR Parts 25 and/or 95. 1.1.8 REGULATORY AGENCIES The direct costs incurred by SNC in connection with HNP are billed directly to GPC. Expenses which are not direct charges to specific plants are allocated to GPC and others for whom the expenses are incurred, as appropriate. GPC recovers a portion of HNP direct and Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 1.1-10
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 324 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 324 of 363 Introduction 1.1, General Information - 10 CFR 54.19 allocated costs from the other co-owners in relation to their respective ownership interests in HNP, and the remainder through rates. The rates charged and services provided by GPC are subject to the jurisdiction of the Georgia Public Service Commission and the Federal Energy Regulatory Commission. Georgia Public Service Commission 244 Washington St. S.W. Atlanta, Georgia 30334 Federal Energy Regulatory Commission 888 First St. N.E. Washington, DC 20426 1.1.9 LOCAL NEWS PUBLICATIONS News publications in circulation near Plant Hatch which are considered appropriate to give reasonable notice of the application are as follows: The Baxley News-Banner P.O. Box 409 Baxley, Georgia 31513 912-367-2468 Fax-912-367-0277 Vidalia Advance-Progress P.O. Box 669 Vidalia, GA 30474 912-537-4899 Fax-912-537-4899 The Tattnall Journal P.O. Box 278 Reidsville, GA 30453 912-557-6761 Fax-912-557-4132 The Jeff Davis Ledger P.O. Box 338 Hazlehurst, GA 31539 912-375-4225 Fax-912-375-3704 The Macon Telegraph P.O. Box 4167 Macon, GA 31208 912-744-4200 Fax-912-744-4385 Savannah Morning News P.O. Box 1088 Savannah, GA 31402 Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 1.1-11
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 325 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 325 of 363 Introduction 1.1, General Information - 10 CFR 54.19 912-236-9511 Fax-912-234-6522 1.1.10 CONFORMING CHANGES TO STANDARD INDEMNITY AGREEMENT 10 CFR 54.19(b) requires that each application must include conforming changes to the standard indemnity agreement, 10 CFR 140.92, Appendix B, to account for the expiration term of the proposed renewed license. Article VII of the original Indemnity Agreement, which was issued on August 2, 1973, along with the HNP Materials License, provides that the Agreement will terminate at the expiration of the license identified in Item 3 of the Attachment (SNM-1378). Since August 2, 1973, the Indemnity Agreement has been amended from time to time. Two of these amendments added license numbers DPR-57 and NPF-5 to Item 3 of the Attachment. As a consequence of these amendments, the existing Indemnity Agreement is presently due to terminate at midnight, June 13, 2018, as the last of these two licenses expires. SNC requests that conforming changes be made to Item 3 of the Attachment to the Indemnity Agreement (and any other provision of the Attachment or Indemnity Agreement) to make clear that the Indemnity Agreement is extended until the expiration date of the renewed HNP operating licenses issued by the Commission in response to this application. Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 1.1-12
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 326 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 326 of 363 From: Baker, Ray D. Sent: Tuesday, June 20, 2000 3:56 PM To: 'William F. Burton (E-mail)'
Subject:
Hatch Application Review Tool - Cracking Mechanisms Matrix by Commodity Group
- Butch, In previous discussions, the NRC staff had expressed interest in a matrix that would map the cracking aging mechanisms discussed in the various C.2 commodity groups to the six-column table entries. The attached matrix provides a concise way for the reviewer to see which cracking mechanisms are considered applicable when examining the six-column tables.
The commodity group number is in the same box as the component name. Find the commodity group number in the matrix and see which mechanisms are considered applicable. The corresponding discussion in section C.2 of the application addresses the management of each of the aging mechanisms specified. During the preparation of this tool we identified areas where annotations/clarifications of the application might prove useful. These pages have been incorporated into an update of the annotated page markups file previously provided. This revised file has been renamed to include the date in order to provide version control of the annotations. Note that none of the pages provided previously have been further annotated by the clarifications provided with the cracking mechanism matrix tool. The only change to the previous annotated page markups file is to add the clarifications pages noted below. The clarifications can be grouped as follows:
- 1. Editorial/typos - pages 2.3-15, 3.2-14, -15, and C.2-101
- 2. Clarifications of applicability of an aging effect to a specific component - pages 3.2-14, -38, -39, -56, C.2-1, -9, -87, -92,
-101, -105, and -108 Please let me know if you have any questions or comments regarding the matrix or the updated annotated pages file. Ray Baker 8-992-7367 '~/ways do right. This will gratify some people and astonish the rest." -- Mark Twain ATTACHMENTS Cracking by annotated_page_m
- ommodity Matrix.p. arkups_6_20.pd ...
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 327 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 327 of 363 Cracking Mechanisms Matrix by Commodity Group Commodity Fatigue SCC IGA Other Group Cracking Cracking Cracking Cracking C.2.1.1.1 X X C.2.1.1.2 X X C.2.1.1.3 X C.2.1.1.4 X X X C.2.1.1.5 X X X C.2.1.1.6 C.2.2.1.1 X C.2.2.1.2 X X X C.2.2.2.1 X C.2.2.2.2 X C.2.2.2.3 C.2.2.3.1 X C.2.2.3.2 X X X C.2.2.4.1 X C.2.2.4.2 X C.2.2.5.1 X C.2.2.5.2 X C.2.2.5.3 X C.2.2.6.1 X C.2.2.6.2 X C.2.2.6.3 X C.2.2.6.4 X C.2.2.7.1 X C.2.2.7.2 X C.2.2.8.1 X C.2.2.8.2 X C.2.2.8.3 X C.2.2.9.1 X C.2.2.9.2 X X X C.2.2.9.3 X C.2.2.9.4 X C.2.2.10.1 C.2.2.10.2 C.2.2.11.1 X X X C.2.3.1 X X X C.2.3.2 X X X C.2.3.3 X X X C.2.3.4.1 X C.2.3.4.2 X C.2.3.4.3 C.2.4.1 C.2.4.2 C.2.4.3 C.2.4.4.1 X X C.2.4.4.2 X 06/20/00 1
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 328 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 328 of 363 Cracking Mechanisms Matrix by Commodity Group Commodity Fatigue SCC IGA Other Group Cracking Cracking Cracking Cracking C.2.5.1 C.2.5.2 C.2.5.3 C.2.5.4 C.2.5.5 C.2.6.1 X C.2.6.2 X C.2.6.3 C.2.6.4 C.2.6.5 C.2.6.6 C.2.6.7 X C.2.6.8 X 06/20/00 2
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 329 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT Structures REVIEW and Components
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Subject SHEET to Aging 329 of 363 Management Review 2.3, Mechanical Systems Screening Results Component Groups Requiring an Aging Management Review Table 2.3.3-2 Components Supporting Residual Heat Removal System [E11] Intended Functions and Their Component Functions Mechanical Component Component Functions Material Bolting Pressure Boundary Carbon Steel Bolting Pressure Boundary Stainless Steel Conductivity Element Fission Product Barrier, Stainless Steel Pressure Boundary Heat Exchanger Channel Pressure Boundary Carbon Steel Assembly Heat Exchanger Impingement Shelter/ Protection Stainless Steel Plate Heat Exchanger- Shell Fission Product Barrier, Carbon Steel Pressure Boundary Heat Exchanger Tube Sheet Fission Product Barrier Carbon Steel Pressure Boundary Stainless Steel Heat Exchanger Tubes Fission Product Barrier, Stainless Steel Pressure Boundary Piping Fission Product Barrier, Carbon Steel Pressure Boundary Pump Casings Fission Product Barrier, Carbon Steel Pressure Boundary Pump Casings - Bowl Pressure Boundary Cast Austenitic Stainless Steel Assembly Pump Column / Discharge Pressure Boundary Carbon Steel Head Pump Sub Base Structural Support Carbon Steel Restricting Orifices Fission Product Barrier, Stainless Steel Pressure Boundary, Flow Restriction Strainer Basket Debris Protection Stainless Steel Strainer Bodies Debris Protection Carbon Steel Strainers Debris Protection Stainless Steel Thermowell Fission Product Barrier, Carbon Steel Pressure Boundary Tubing Pressure Boundary Copper Alloy Valve Bodies Pressure Boundary Carbon Steel Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 2.3-15
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 330 of 363 A-47039 Attachment C LICENSE Structures RENEWAL and Components AGING Subject to MANAGEMENT Aging Management REVIEW
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SHEET 330 of 363 Review 2.3, Mechanical Systems Screening Results Component Groups Requiring an Aging Management Review Table 2.3.4-16 Components Supporting Traveling Water Screens/ Trash Rack System [W33] Intended Functions and Their Component Functions Mechanical Component Component Functions Material Bolting Pressure Boundary Carbon Steel Sight Glasses* Pressure Boundary Ceramic Trash Racks Debris Protection Carbon Steel Traveling Screen Debris Protection Carbon Steel Stainless Steel Copper Alloy* Valve Bodies Pressure Boundary Carbon Steel
- No aging effects requiring management Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 2.3-60
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 331 of 363 A-47039 Attachment C LICENSE Structures RENEWAL and Components AGING Subject to MANAGEMENT Aging Management REVIEW
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SHEET 331 of 363 Review 2.3, Mechanical Systems Screening Results Component Groups Requiring an Aging Management Review Table 2.3.4-18 Components Supporting Fire Protection System [X43] Intended Functions and Their Component Functions Mechanical Component Component Functions Material Bolting Pressure Boundary Carbon Steel Fire Doors Fire Barrier Carbon Steel Galvanized Steel Copper Alloy Stainless Steel Aluminum Nonmetallic, Inorganic-Gypsum Fibers, nonasbestos synthetic Nonmetallic, organic Fire Hydrants Pressure Boundary Cast Iron Fittings Pressure Boundary Cast Iron Fittings Pressure Boundary Copper Alloy Cast Iron Fusible Material Pressure Boundary Nonferrous Metal Kaowool and Hold-down Straps Fire Barrier Galvanized Steel, Insulation material Nozzles Flow Restriction Aluminum Copper Alloy Nozzles Flow Restriction Copper Alloy Penetration Seals Fire Barrier Concrete Ceramics Carbon Steel Synthetic Fiber Elastomers Pilot Valves Pressure Boundary Aluminum Pipe Line Strainers Pressure Boundary Cast Iron Piping Pressure Boundary Carbon Steel Aluminum Galvanized Steel Copper Alloy Cast Iron Piping Pressure Boundary Carbon Steel Stainless Steel Piping Pressure Boundary Carbon Steel Galvanized Steel Pump Casings Pressure Boundary Cast Iron Restricting Orifices Pressure Boundary, Flow Stainless Steel Restriction Sprinkler Head Bulbs Pressure Boundary Ceramics Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 2.3-66
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 332 of 363 A-47039 Attachment C LICENSE Structures RENEWAL and Components AGING Subject to MANAGEMENT Aging Management REVIEW Review
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SHEET 332 of 363 2.4, Structures Screening Results Component Groups Requiring an Aging Management Review Table 2.4.3-1 Components Supporting Primary Containment [T23] Intended Functions and Their Component Functions Structural Component Component Functions Material Anchors and Bolts Structural Support; Carbon Steel Nonsafety Related Structural Support Galvanized Steel Stainless Steel Blind Flange* Fission Product Barrier Carbon Steel Bolting* Fission Product Barrier Carbon Steel Containment Isolation Valves
- Fission Product Barrier Carbon Steel Containment Isolation Valves* Fission Product Barrier Stainless Steel Containment Penetrations Fission Product Barrier Carbon Steel (Mechanical only) Stainless Steel Miscellaneous Steel Structural Support; Carbon Steel Radiation Shielding; Galvanized Steel Pipe Whip Restraint; Nonsafety Related Structural Support Piping* Fission Product Barrier Carbon Steel Piping* Fission Product Barrier Stainless Steel Reinforced Concrete Structural Support; Concrete Shelter/Protection; Carbon Steel Flood Barrier; Fission Product Barrier; Radiation Shielding; Missile Barrier; HE/ME Shielding Steel Bellows (inside Vent Pipe) Pressure Boundary; Carbon Steel Fission Product Barrier Stainless Steel Structural Steel Structural Support; Carbon Steel Shelter/Protection; Stainless Steel Radiation Shielding; Missile Barrier; HE/ME Shielding; Pipe Whip Restraint; Nonsafety Related Structural Support; Pressure Boundary Fission Product Barrier; Exchange Heat Tubing* Fission Product Barrier; Pressure Stainless Steel Boundary Unreinforced Concrete Radiation Shielding Unreinforced Concrete**
Vent Pipe, Vent Header, Fission Product Barrier; Carbon Steel Downcomers Pressure Boundary
- Piping and valves include components from systems P51, P21, T23, G51, G11, D11, and C51. These are all included in function T23-01, Torus/Drywell.
** No aging effects requiring management Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 2.4-6
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 333 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 333 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.1-2 Aging Effects Requiring Management for Components Supporting Nuclear Boiler System [B21] Intended Functions and Their Component Functions Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Bolting / C.2.1.1.6 Pressure Boundary Inside Carbon Steel Loss of Preload Torque Activities (Class 1) Fission Product Inservice Inspection Program Barrier Bolting / C.2.2.10.1 Pressure Boundary Inside Carbon Steel Loss of Preload Torque Activities (non-Class 1) Fission Product Loss of Material Protective Coatings Program Barrier Crack Growth Monitor / Pressure Boundary Reactor Water Stainless Steel Loss of Material Reactor Water Chemistry Control C.2.1.1.4 Fission Product Cracking Inservice Inspection Program (Class 1) Barrier Component Cyclic or Transient Limit Program Treated Water Systems Piping Inspections Flow Nozzle / C.2.1.1.3 Pressure Boundary Reactor Water Carbon Steel Loss of Material Reactor Water Chemistry Control (Class 1) Fission Product Cracking Inservice Inspection Program Barrier Galvanic Susceptibility Inspections Component Cyclic or Transient Limit Program Flow Accelerated Corrosion Program Treated Water Systems Piping Inspections Piping / C.2.2.1.1 Pressure Boundary Reactor Water Carbon Steel Loss of Material Reactor Water Chemistry Control (non-Class 1) Fission Product Cracking Galvanic Susceptibility Inspections Barrier Treated Water Systems Piping Inspections Flow Accelerated Corrosion Program Piping / C.2.2.1.2 Pressure Boundary Reactor Water Stainless Steel Loss of Material Reactor Water Chemistry Control (non-Class 1) Fission Product Cracking Treated Water Systems Piping Barrier Inspections Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-5
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 334 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 334 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.1-2 Aging Effects Requiring Management for Components Supporting Nuclear Boiler System [B21] Intended Functions and Their Component Functions (Continued) Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Piping / C.2.2.2.2 Pressure Boundary Demin Water Stainless Steel Loss of Material Demineralized Water and Condensate (non-Class 1) Fission Product Cracking Storage Tank Chemistry Control Barrier Treated Water Systems Piping Inspections Piping / C.2.2.3.1 Pressure Boundary Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control (non-Class 1) Fission Product Cracking Torus Submerged Components Barrier Inspection Program Piping / C.2.2.3.2 Pressure Boundary Torus Water Stainless Steel Loss of Material Suppression Pool Chemistry Control (non-Class 1) Fission Product Cracking Torus Submerged Components Barrier Inspection Program Piping / C.2.1.1.3 Pressure Boundary Reactor Water Carbon Steel Loss of Material Reactor Water Chemistry Control (Class 1) Fission Product Cracking Inservice Inspection Program Barrier Galvanic Susceptibility Inspections Component Cyclic or Transient Limit Program Flow Accelerated Corrosion Program Treated Water Systems Piping Inspections Piping / C.2.1.1.4 Pressure Boundary Reactor Water Stainless Steel Loss of Material Reactor Water Chemistry Control (Class 1) Fission Product Cracking Inservice Inspection Program Barrier Component Cyclic or Transient Limit Program Treated Water Systems Piping Inspections Piping / C.2.2.9.1 Pressure Boundary Wetted Gas Carbon Steel Loss of Material Inservice Inspection Program (non-Class 1) Fission Product Cracking Gas Systems Component Inspections Barrier Passive Component Inspection Activities Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-6
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 335 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 335 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.1-2 Aging Effects Requiring Management for Components Supporting Nuclear Boiler System [B21] Intended Functions and Their Component Functions (Continued) Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Restricting Orifice / Pressure Boundary Reactor Water Stainless Steel Loss of Material Reactor Water Chemistry Control C.2.1.1.4 Fission Product Cracking Component Cyclic or Transient Limit (Class 1) Barrier Program Inservice Inspection Program Treated Water Systems Piping Inspections Thermowell/ Pressure Boundary Wetted Gas Carbon Steel Loss of Material Gas Systems Component Inspections C.2.2.9.1 Fission Product Cracking Passive Component Inspection (non-Class 1) Barrier Activities Thermowell / Pressure Boundary Reactor Water Stainless Steel Loss of Material Reactor Water Chemistry Control C.2.1.1.4 Fission Product Cracking Inservice Inspection Program (Class 1) Barrier Component Cyclic or Transient Limit Program Treated Water Systems Piping Inspections Valve Bodies / C.2.2.1.1 Pressure Boundary Reactor Water Carbon Steel Loss of Material Reactor Water Chemistry Control (non-Class 1) Fission Product Cracking Flow Accelerated Corrosion Program Barrier Galvanic Susceptibility Inspections Treated Water Systems Piping Inspections Valve Bodies / C.2.2.1.2 Pressure Boundary Reactor Water Stainless Steel Loss of Material Reactor Water Chemistry Control (non-Class 1) Fission Product Cracking Treated Water Systems Piping Barrier Inspections Valve Bodies / C.2.2.9.1 Pressure Boundary Wetted Gas Carbon Steel Loss of Material Gas Systems Component Inspections (non-Class 1) Fission Product Cracking Inservice Inspection Program Barrier Passive Component Inspection Activities Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-7
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 336 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 336 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.3-2 Aging Effects Requiring Management for Components Supporting Residual Heat Removal System [E11] Intended Functions and Their Component Functions (Continued) Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Pump Casings / Fission Product Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control C.2.2.3.1 Barrier, Pressure Cracking Galvanic Susceptibility Inspections Boundary Treated Water Systems Piping Inspections Pump Casings - Bowl Pressure Boundary Raw Water Cast Austenitic Loss of Material PSW and RHRSW Inspection Program Assembly/ C.2.2.6.2 Stainless Steel Flow Blockage Plant Service Water and RHR Service Cracking Water Chemistry Control Program Loss of Heat Structural Monitoring Program Exchanger Performance Pump Column / Pressure Boundary Raw Water Carbon Steel Loss of Material PSW and RHRSW Inspection Program Discharge Head / Flow Blockage PSW and RHRSW Chemistry Control C.2.2.6.1 Cracking Program Structural Monitoring Program Galvanic Susceptibility Inspections Pump Sub Base / Structural Support Inside Carbon Steel Loss of Material Protective Coatings Program C.2.4.1 Restricting Orifices / Fission Product Torus Water Stainless Steel Loss of Material Suppression Pool Chemistry Control C.2.2.3.2 Barrier, Pressure Cracking Treated Water Systems Piping Boundary Inspection Restricting Orifices / Fission Product Torus Water Stainless Steel Loss of Material Suppression Pool Chemistry Control C.2.2.3.2 Barrier, Pressure Cracking Treated Water Systems Piping Boundary, Flow Inspection Restriction Restricting Orifices / Pressure Boundary, Raw Water Stainless Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.2 Flow Restriction Flow Blockage PSW and RHRSW Chemistry Control Cracking Program Structural Monitoring Program Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-14
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 337 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 337 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.3-2 Aging Effects Requiring Management for Components Supporting Residual Heat Removal System [E11] Intended Functions and Their Component Functions (Continued) Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Strainer Bodies / Debris Protection Raw Water Carbon Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.1 Flow Blockage Plant Service Water and RHR Service Cracking Water Chemistry Control Program Galvanic Susceptibility Inspections Structural Monitoring Program Strainers / C.2.2.3.2 Debris Protection Torus Water Stainless Steel Loss of Material Suppression Pool Chemistry Control Cracking Torus Submerged Components Inspection Program Thermowell / C.2.2.3.1 Fission Product Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control Barrier, Pressure Cracking Treated Water Systems Piping Boundary Inspections Tubing / C.2.2.6.3 Pressure Boundary Raw Water Copper Alloy Loss of Material PSW and RHRSW Chemistry Control Cracking Program Flow Blockage PSW and RHRSW Inspection Program Structural Monitoring Program Valve Bodies / C.2.2.3.1 Pressure Boundary, Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control Fission Product Cracking Galvanic Susceptibility Inspection Barrier Treated Water Systems Piping Inspection Valve Bodies/ C.2.2.6.1 Pressure Boundary Raw Water Carbon Steel Loss of Material PSW and RHRSW Inspection Program Flow Blockage PSW and RHRSW Chemistry Control Cracking Program Galvanic Susceptibility Inspections Structural Monitoring Program Strainer Basket/ Debris Protection Raw Water Stainless Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.2 Flow Blockage PSW and RHRSW Chemistry Control Program Structural Monitoring Program Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-15
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 338 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 338 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.3-4 Aging Effects Requiring Management for Components Supporting High Pressure Coolant Injection System [E41] Intended Functions and Their Component Functions Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Bolting / C.2.2.10.1 Pressure Boundary Inside Carbon Steel Loss of Preload Torque Activities Fission Product Barrier Loss of Material Protective Coatings Program Bolting / C.2.2.10.2 Pressure Boundary Inside Stainless Steel Loss of Preload Torque Activities Fission Product Barrier Flexible Connector / Pressure Boundary Dry Wetted Gas Stainless Steel Cracking Gas Systems Component Inspections C.2.2.9.2 Fission Product Barrier Loss of Material Piping / C.2.2.1.1 Pressure Boundary Reactor Water Carbon Steel Loss of Material Reactor Water Chemistry Control Fission Product Barrier Cracking Galvanic Susceptibility Inspections Flow Accelerated Corrosion Program Treated Water Systems Piping Inspections Piping / C.2.2.2.1 Pressure Boundary Demin Water Carbon Steel Loss of Material Demineralized Water and Condensate Fission Product Barrier Cracking Storage Tank Chemistry Control Treated Water Systems Piping Inspections Piping / C.2.2.2.2 Pressure Boundary Demin Water Stainless Steel Loss of Material Demineralized Water and Condensate Fission Product Barrier Cracking Storage Tank Chemistry Control Program Treated Water Systems Piping Inspections Piping / C.2.2.3.1 Pressure Boundary Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control Fission Product Barrier Cracking Galvanic Susceptibility Inspections Treated Water Systems Piping Inspections Torus Submerged Components Inspection Program Protective Coatings Program Piping / C.2.2.3.2 Pressure Boundary Torus Water Stainless Steel Loss of Material Suppression Pool Chemistry Control Fission Product Barrier Cracking Torus Submerged Components Inspection Program Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-17
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 339 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 339 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.3-5 Aging Effects Requiring Management for Components Supporting Reactor Core Isolation Cooling System [E51] Intended Functions and Their Component Functions (Continued) Mechanical Component Environment Material Aging Effects Aging Management Program/ Component Functions Activity Valve Bodies / C.2.2.9.2 Pressure Boundary Wetted Gas Stainless Steel Loss of Material Gas Systems Component Inspections Fission Product Cracking Passive Component Inspection Activities Barrier Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-25
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 340 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 340 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.3-7 Aging Effects Requiring Management for Components Supporting Primary Containment Purge and Inerting System [T48] Intended Functions and Their Component Functions Component Aging Management Mechanical Component Functions Environment Material Aging Effects Program/Activity Bolting / C.2.2.10.1 Pressure Boundary Inside Carbon Steel Loss of Preload Torque Activities Loss of Material Protective Coatings Program Bolting / C.2.2.10.2 Pressure Boundary Inside Stainless Steel Loss of Preload Torque Activities Flex Hose / C.2.2.9.1 Pressure Boundary Air Stainless Steel Cracking Gas Systems Component Inspections Nitrogen Tank Jacket / C.2.2.9.1 Structural Support Air Carbon Steel Cracking Gas Systems Component Inspections Loss of Material Passive Component Inspection Activities Piping / C.2.2.3.1 Pressure Boundary Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control Cracking Galvanic Susceptibility Inspections Torus Submerged Components Inspection Program Protective Coatings Program Piping / C.2.2.3.1 Pressure Boundary Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control Cracking Torus Submerged Components Inspection Program Piping / C.2.2.3.2 Pressure Boundary Torus Water Stainless Steel Loss of Material Suppression Pool Chemistry Control Cracking Treated Water Systems Piping Inspections Piping / C.2.2.8.2 Pressure Boundary Dried Gas Stainless Steel Cracking None Required Piping / C.2.2.9.1 Pressure Boundary Wetted Gas Carbon Steel Cracking Gas Systems Component Inspections Loss of Material Passive Component Inspection Activities Pressure Buildup Coil / C.2.2.8.2 Pressure Boundary Dried Gas Stainless Steel Cracking None Required Exchange Heat Rupture Disc / C.2.2.8.2 Pressure Boundary Dried Gas Stainless Steel Cracking None Required Storage Tank / C.2.2.8.2 Pressure Boundary Dried Gas Stainless Steel Cracking None Required Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-28
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 341 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 341 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.4-2 Aging Effects Requiring Management for Components Supporting Refueling Platform Equipment Assembly [F15] Intended Functions and Their Component Functions Structural Component Component Functions Environment Material Aging Effects Aging Management Program/Activity Anchors and Structural support Inside Carbon steel Loss of material Protective Coatings Program Bolts Nonsafety Related Overhead Crane and Refueling Platform C.2.6.3 Structural Support Inspection Structural Monitoring Program Miscellaneous Structural support; Inside Carbon steel Loss of material Protective Coatings Program Steel Nonsafety Related Overhead Crane and Refueling Platform C.2.6.3 Structural Support Inspection Structural Monitoring Program Rivets Structural Support Inside Aluminum None None Required Structural Steel Structural support Inside Carbon steel Loss of material Protective Coatings Program C.2.6.3 Overhead Crane and Refueling Platform Inspection Structural Monitoring Program Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-33
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 342 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 342 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.4-7 Aging Effects Requiring Management for Components Supporting Plant Service Water System [P41] Intended Functions and Their Component Functions Mechanical Component Component Functions Environment Material Aging Effects Aging Management Program/Activity Bolting / Pressure Boundary Outside, Inside Carbon Steel Loss of Preload Torque Activities C.2.2.10.1 Loss of Material Protective Coatings Program Flexible Pressure Boundary Raw Water Stainless Steel Loss of Material PSW and RHRSW Inspection Program Connector / Flow Blockage Plant Service Water and RHR Service Water C.2.2.6.2 Cracking Chemistry Control Program Structural Monitoring Program Piping / C.2.2.6.1 Pressure Boundary Raw Water Carbon Steel Loss of Material PSW and RHRSW Inspection Program Flow Blockage PSW and RHRSW Chemistry Control Cracking Program Structural Monitoring Program Galvanic Susceptibility Inspections Piping / C.2.2.6.2 Pressure Boundary Raw Water Stainless Steel Loss of Material PSW and RHRSW Inspection Program Flow Blockage PSW and RHRSW Chemistry Control Cracking Program Structural Monitoring Program Pump Bowl Pressure Boundary Raw Water Cast Austenitic Loss of Material PSW and RHRSW Inspection Program Assembly / Stainless Steel Flow Blockage PSW and RHRSW Chemistry Control C.2.2.6.2 Cracking Program Structural Monitoring Program Pump Discharge Pressure Boundary Raw Water Carbon Steel Loss of Material PSW and RHRSW Inspection Program Column / Flow Blockage PSW and RHRSW Chemistry Control C.2.2.6.1 Cracking Program Structural Monitoring Program Pump Discharge Pressure Boundary Raw Water Carbon Steel Loss of Material PSW and RHRSW Inspection Program Head / C.2.2.6.1 Flow Blockage PSW and RHRSW Chemistry Control Cracking Program Structural Monitoring Program Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-38
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 343 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 343 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.4-7 Aging Effects Requiring Management for Components Supporting Plant Service Water System [P41] Intended Functions and Their Component Functions (Continued) Mechanical Component Component Functions Environment Material Aging Effects Aging Management Program/Activity Pump Sub Base / Structural Support Inside Carbon Steel Loss of Material Protective Coatings Program C.2.4.1 Restricting Pressure Raw Water Stainless Steel Loss of Material PSW and RHRSW Inspection Program Orifices / Boundary, Flow Flow Blockage Plant Service Water and RHR Service Water C.2.2.6.2 Restriction Cracking Chemistry Control Program Structural Monitoring Program Sight Glass Body Pressure Boundary Raw Water Carbon Steel Loss of Material PSW and RHRSW Inspection Program
/ C.2.2.6.1 Flow Blockage PSW and RHRSW Chemistry Control Galvanic Corrosion Program Cracking Structural Monitoring Program Sight Glass Pressure Boundary Raw Water Stainless Steel Loss of Material PSW and RHRSW Inspection Program Body/ Flow Blockage PSW and RHRSW Chemistry Control C.2.2.6.2 Cracking Program Structural Monitoring Program Strainer / Pressure Boundary Raw Water Carbon Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.1 Flow Blockage PSW and RHRSW Chemistry Control Cracking Program Structural Monitoring Program Strainer / Pressure Boundary Raw Water Gray Cast Iron Loss of Material PSW and RHRSW Inspection Program C.2.2.6.4 Flow Blockage PSW and RHRSW Chemistry Control Cracking Program Structural Monitoring Program Strainer Basket / Debris Protection Raw Water Stainless Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.2 Flow Blockage PSW and RHRSW Chemistry Control Cracking Program Structural Monitoring Program Strainer Basket / Debris Protection Raw Water Gray Cast Iron Loss of Material PSW and RHRSW Inspection Program C.2.2.6.4 Flow Blockage PSW and RHRSW Chemistry Control Cracking Program Structural Monitoring Program Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-39
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 344 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 344 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.4-7 Aging Effects Requiring Management for Components Supporting Plant Service Water System [P41] Intended Functions and Their Component Functions (Continued) Mechanical Component Component Functions Environment Material Aging Effects Aging Management Program/Activity Thermowell / Pressure Boundary Raw Water Carbon Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.1 Cracking Plant Service Water and RHR Service Water Chemistry Control Program Thermowell / Pressure Boundary Raw Water Stainless Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.2 Cracking PSW and RHRSW Chemistry Control Program Valve Bodies / Pressure Boundary Raw Water Carbon Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.1 Flow Blockage PSW and RHRSW Chemistry Control Cracking Program Structural Monitoring Program Galvanic Susceptibility Inspections Valve Bodies / Pressure Boundary Raw Water Stainless Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.2 Flow Blockage PSW and RHRSW Chemistry Control Cracking Program Structural Monitoring Program Valve Bodies / Pressure Boundary Raw Water Copper Alloy Loss of Material PSW and RHRSW Chemistry Control C.2.2.6.3 Cracking Program Flow Blockage Structural Monitoring Program PSW and RHRSW Inspection Program Venturi / Pressure Boundary Raw Water Carbon Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.1 Flow Blockage PSW and RHRSW Chemistry Control Cracking Program Structural Monitoring Program Galvanic Susceptibility Inspections Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-40
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 345 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 345 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.4-13 Aging Effects Requiring Management for Components Supporting Reactor Building Crane [T31] Intended Functions and Their Component Functions Structural Component Component Functions Environment Material Aging Effects Aging Management Program/Activity Structural Steel/ Structural Support Inside Carbon Steel Loss of Material Overhead Crane and Refueling Platform C.2.6.3 Inspection Protective Coatings Program Structural Monitoring Program Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-47
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 346 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 346 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.4-16 Aging Effects Requiring Management for Components Supporting Traveling Water Screens / Trash Rack System [W33] Intended Functions and Their Component Functions Mechanical Component Component Functions Environment Material Aging Effects Aging Management Program/Activity Trash Rack / Debris Protection Submerged Carbon Steel Loss of Material Structural Monitoring Program C.2.6.3 Protective Coatings Program Traveling Screen / Debris Protection Submerged Carbon Steel Loss of Material Structural Monitoring Program C.2.6.3 Stainless Steel Traveling Screen / Debris Protection Submerged Copper Alloy None None Required C.2.6.3 Valve Bodies / Pressure Boundary Raw Water Carbon Steel Loss of Material PSW and RHRSW Inspection Program C.2.2.6.1 Flow Blockage Plant Service Water and RHR Service Water Cracking Chemistry Control Program Galvanic Susceptibility Inspections Bolting / C.2.2.10.1 Pressure Boundary Outside Carbon Steel Loss of Material Torque Activities Loss of Preload Protective Coatings Program Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-50
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 347 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 347 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.4-18 Aging Effects Requiring Management for Components Supporting Fire Protection System [X43] Intended Functions and Their Intended Functions Component Aging Management Mechanical Component Functions Environment Material Aging Effects Program/Activity Boltings / C.2.2.10.1 Pressure Boundary Inside Carbon Steel Loss of Preload Torque Activities Outside Loss of Material Protective Coatings Program Fire Doors / C.2.3.4.3 Fire Barrier Inside Carbon Steel Loss of Material Fire Protection Activities Fire Doors / C.2.3.4.3 Fire Barrier Inside Galvanized Steel None None Required Copper Alloy Stainless Steel Aluminum Nonmettalic, Inorganic Gypsum Fibers, Nonasbestos Synthetic Nonmetallic, Organic Fire Hydrants / C.2.3.1 Pressure Boundary Raw Water Cast Iron Loss of Material Fire Protection Activities Cracking Flow Blockage Fittings / C.2.3.1 Pressure Boundary Raw Water Cast Iron Loss of Material Fire Protection Activities Air Cracking Flow Blockage Fittings / C.2.3.3 Pressure Boundary Air Copper Alloy Cracking Fire Protection Activities Cast Iron Loss of Material Fusible Material / C.2.3.1 Pressure Boundary Inside Nonferrous Metal Loss of Material Fire Protection Activities Cracking Kaowool and Hold-Down Fire Barrier Inside Galvanized Steel CrackingLoss of Fire Protection Activities Straps / C.2.3.4.3C.2.3.4.2 Insulation Material Material Change in Material Properties Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-52
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 348 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 348 of 363 Aging Management Review Results 3.2, Mechanical Systems Table 3.2.4-19 Aging Effects Requiring Management for Components Supporting Fuel Oil System [Y52] Intended Functions and Their Component Functions Mechanical Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Bolting / C.2.2.10.1 Pressure Boundary Inside Carbon Steel Loss of Preload Torque Activities Loss of Material Protective Coatings Program Discharge Head / Pressure Boundary Fuel Oil Carbon Steel Loss of Material Diesel Fuel Oil Testing C.2.2.7.1 Cracking Flex Hose / C.2.2.7.2 Pressure Boundary Fuel Oil Stainless Steel Loss of Material Diesel Fuel Oil Testing Cracking Manway Shell / Shelter/ Protection Air Carbon Steel Cracking Gas Systems Component C.2.2.9.1 Loss of Material Inspections Passive Component Inspection Activities Piping / C.2.2.7.1 Pressure Boundary Fuel Oil Carbon Steel Loss of Material Diesel Fuel Oil Testing Cracking Piping / C.2.2.7.2 Pressure Boundary Fuel Oil Stainless Steel Loss of Material Diesel Fuel Oil Testing Cracking Piping / C.2.2.9.1 Pressure Boundary Air Carbon Steel Loss of Material Gas Systems Component Cracking Inspection Passive Component Inspection Activities Piping / C.2.2.9.2 Pressure Boundary Air Stainless Steel Cracking Gas Systems Component Loss of Material Inspections Pump / C.2.2.7.1 Pressure Boundary Fuel Oil Carbon Steel Loss of Material Diesel Fuel Oil Testing Cracking Strainer Basket / Shelter/ Protection Fuel Oil Stainless Steel Loss of Material Diesel Fuel Oil Testing C.2.2.7.2 Cracking Tank / C.2.2.7.1 Pressure Boundary Fuel Oil Carbon Steel Cracking Diesel Fuel Oil Testing Loss of Material Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.2-56
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 349 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 349 of 363 Aging Management Review Results 3.3, Civil/Structural Table 3.3.1-3 Aging Effects Requiring Management for Components Supporting Primary Containment [T23] Intended Functions and Their Component Functions Structural Component Component Functions Environment Material Aging Effects Aging Management Program/Activity Anchors and Bolts / Structural Support; Containment Carbon Steel Loss of Material Protective Coatings Program C.2.6.2 Nonsafety Related Atmosphere; Galvanized Steel Inservice Inspection Program Structural Support Embedded; Inside Stainless Steel Suppression Pool Chemistry Control Torus Water Blind Flange* / Fission Product Barrier Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control C.2.2.3.1 Cracking Treated Water Systems Piping Inspections Containment Isolation Fission Product Barrier Demin Water Stainless Steel Loss of Material Demineralized Water and Condensate Valves* / C.2.2.2.2 Cracking Storage Tank Chemistry Control Treated Water Systems Piping Inspections Containment Isolation Fission Product Barrier Demin Water Carbon Steel Loss of Material Demineralized Water and Condensate Valves* / C.2.2.3.1 Cracking Storage Tank Chemistry Control Treated Water Systems Piping Inspections Containment Isolation Fission Product Barrier Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control Valves* / C.2.2.3.1 Treated Water Systems Piping Inspections Containment Isolation Fission Product Barrier Raw Water Carbon Steel Loss of Material Passive Component Inspection Activities Valves* / Cracking C.2.2.6.2C.2.6.2 Containment Isolation Fission Product Barrier Wetted Gas Carbon Steel Loss of Material Gas Systems Component Inspections Valves* / C.2.2.9.1 Passive Component Inspection Activities Containment Isolation Fission Product Barrier Wetted Gas Stainless Steel Loss of Material Gas Systems Component Inspection Valves* / C.2.2.9.2 Cracking Containment Fission Product Barrier Containment Carbon Steel Loss of Material Protective Coatings Program Penetrations Atmosphere; Stainless Steel Inservice Inspection Program (Mechanical only) / Embedded; Inside Primary Containment Leakage Rate Testing C.2.6.2 Program Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.3-4
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 350 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 350 of 363 Aging Management Review Results 3.3, Civil/Structural Table 3.3.1-3 Aging Effects Requiring Management for Components Supporting Primary Containment [T23] Intended Functions and Their Component Functions (Continued) Structural Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Structural Steel / Structural Support; Containment Carbon Steel Loss of Material Protective Coatings Program C.2.6.2 Shelter/Protection; Atmosphere; Stainless Steel Cracking Primary Containment Leakage Rate Pressure Boundary; Inside; Testing Program Radiation Shielding; Torus Water; Inservice Inspection Program Nonsafety Related Embedded Suppression Pool Chemistry Control Structural Support; Component Cyclic or Transient Limit HE/ME Shielding; Program Missile Barrier; Pipe Whip Restraint; Fission Product Barrier; Exchange Heat Tubing* / C.2.2.9.2 Fission Product Wetted Gas Stainless Steel Loss of Material Gas Systems Component Inspections Barrier; Cracking Pressure Boundary Vent Pipe, Vent Pressure Boundary Containment Carbon Steel Loss of Material Protective Coatings Program Header, Downcomers / Fission Product Barrier Atmosphere; Cracking Inservice Inspection Program C.2.6.2 High Humidity; Primary Containment Leakage Rate Inside; Testing Program Torus Water Component Cyclic or Transient Limit Program Suppression Pool Chemistry Control Bolting / C.2.2.10.1 Pressure Boundary Inside Carbon Steel Loss of Material Protective Coatings Program Containment Loss of Preload Torque Activities Atmosphere
- Piping and valve bodies include components from systems P51, P21, T23, G51, G11, D11, and C51. These are all included in function T23-01, Torus/Drywell.
Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.3-6
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 351 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 351 of 363 Aging Management Review Results 3.3, Civil/Structural Table 3.3.1-5 Aging Effects Requiring Management for Components Supporting Reactor Building [T29] Intended Functions and Their Component Functions Structural Component Aging Management Component Functions Environment Material Aging Effects Program/Activity Anchors and Bolts / Structural Support; Inside; Outside Carbon Steel Loss of Material Protective Coatings Program C.2.6.3 Nonsafety Related Structural Monitoring Program Structural Support Blowout Panels / Structural Support; Inside Aluminum None None Required C.2.6.6 Fission Product Barrier Miscellaneous Steel / Structural Support; Inside; Outside Carbon Steel Loss of Material Structural Monitoring Program C.2.6.3 HE/ME Shielding; Galvanized Steel Protective Coatings Program Nonsafety Related Structural Support Miscellaneous Steel / Structural Support; Inside; Outside Stainless Steel None None Required C.2.6.3 HE/ME Shielding; Nonsafety Related Structural Support Panel Joint Seals and Shelter/Protection; Inside; Outside Elastomers; Material Property Structural Monitoring Program Sealants / C.2.6.7 Fission Product Barrier Nonmetallic, Changes and Protective Coatings Program Inorganic Cracking Loss of Adhesion Reinforced Concrete Structural Support; Inside; Outside Concrete Loss of Material Structural Monitoring Program C.2.6.1 Fire Barrier; Masonry Block Cracking Protective Coatings Program Shelter/Protection; Carbon Steel Flood Barrier; Fission Product Barrier; Radiation Shielding; Missile Barrier; HE/ME Shielding; Nonsafety Related Structural Support Structural Steel Structural Support; Inside; Outside; Carbon Steel Loss of Material Structural Monitoring Program C.2.6.3 Missile Barrier; Submerged Galvanized Steel Protective Coatings Program Nonsafety Related Stainless Steel Overhead Crane and Refueling Platform Structural Support Inspections Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal 3.3-8
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 352 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
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Identification SHEET 352 ofof Commodities 363 C.2, Aging Management Reviews C.2 AGING MANAGEMENT REVIEWS Section C.2 of Appendix C provides an aging management summary for each unique structure, component, or commodity group at Plant Hatch determined to require aging management during the period of extended operation. This summary includes identification of aging effects requiring management, aging management programs utilized to manage these aging effects, and a demonstration as to how the identified aging management programs manage aging effects requiring management using attribute tables. Section C.1 of the LRA provides discussion of aging effects and environments. Appendix A of the LRA provides descriptions of aging management programs required to manage aging effects requiring management. C.2.1 AGING MANAGEMENT REVIEWS FOR CLASS 1 MECHANICAL DISCIPLINE COMMODITIES C.2.1.1 Class 1 Components Environment Description Class 1 components are subject to an environment of reactor water under normal conditions. The reactor water environment is defined in section C.1.2.1. C.2.1.1.1 Aging Management Review for the Reactor Pressure Vessel The reactor pressure vessel (RPV) consists of the following components:
- Shell and closure heads
- Nozzles, Appurtenances, and Penetrations
- Attachments and connecting welds (brackets and lugs)
- RPV head closure studs The RPV and associated components are constructed from carbon steel, low alloy steel, austenitic stainless steel, and nickel based alloys.
Systems B11 - Reactor Assembly (2.3.1.1) Aging Effects Requiring Management
- Cracking (C.1.2.1.2) due to stress corrosion cracking (SCC) and fatigue. The SCC aging effect does not apply to the CRD stub tubes and the low alloy and carbon steel reactor vessel safe ends.
- Loss of fracture toughness (C.1.2.1.3) due to neutron embrittlement.
A complete discussion of the applicable aging effect determinations may be found in section C.1 of the LRA or by using the above links. Aging Management Programs Aging management programs determined to manage aging effects requiring management are as follows: Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal C.2-1
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 353 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
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Identification SHEET 353 of of Commodities 363 C.2, Aging Management Reviews C.2.1.1.2 Aging Management Review for the Reactor Pressure Vessel Internals The reactor pressure vessel internals requiring an aging management review consist of the following components:
- Shroud and repair hardware
- Shroud support
- Core spray spargers and internal piping
- Top guide - Unit 1 only (Unit 2 has wedges and will not lift even with completely cracked holddown assemblies)
- CRD housing and control rod guide tubes
- Jet pump assemblies The reactor pressure vessel internals (RPV Internals) are constructed from carbon low alloy steel, cast, wrought, and forged austenitic stainless steels, and nickel based alloys.
Systems B11 - Reactor Assembly (2.3.1.1) Aging Effects Requiring Management
- Cracking (C.1.2.1.2) due to stress corrosion cracking (SCC) and fatigue. The SCC aging effect is not applicable to the low alloy steel reactor assembly shroud supports.
Aging Management Programs Aging management programs determined to manage aging effects requiring management are as follows:
- Reactor Water Chemistry Control (A.1.1)
- Inservice Inspection Program (ISI Program) (A.1.9)
- Boiling Water Reactor Vessel Internals Program (BWRVIP) (A.1.15)
A complete discussion of the applicable aging management programs may be found in Appendix A of the LRA or by using the above links. Demonstration of Aging Management What follows is a demonstration that the aging effects requiring management identified will be adequately managed during the period of extended operation. Management of Cracking due to Stress Corrosion Cracking Reactor Water Chemistry Control serves to manage cracking due to SCC by controlling electrochemical corrosion potential (ECP) in accordance with the recommendations of EPRI BWR water chemistry guidelines. This can be accomplished through the use of filter / demineralizers which limit halides and other impurities within the feedwater and hydrogen Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal C.2-9
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 354 of 363 A-47039 Attachment C LICENSE Identification RENEWAL AGING MANAGEMENT REVIEW
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SHEET 354 of 363 of Commodities C.2, Aging Management Reviews C.2.2.3 Non-Class 1 Components Suppression Pool Water Environment Description Components within section C.2.2.3 are subject to an environment of suppression pool water under normal conditions. The suppression pool water environment is defined in section C.1.2.2. C.2.2.3.1 Aging Management Review for Non-Class 1 Carbon Steel Components Within the Suppression Pool Environment This commodity group consists of carbon steel commodities with an internal environment of suppression pool water or submerged within the suppression pool. The following component types are included within this evaluation:
- Piping
- Valve bodies
- Pump casings
- Thermowells
- Blind flange Systems B21 - Nuclear Boiler (2.3.1.2)
- E11 - Residual Heat Removal (2.3.3.2)
- E21 - Core Spray (2.3.3.3)
- E41 - High Pressure Coolant Injection (2.3.3.4)
- E51 - Reactor Core Isolation Cooling (2.3.3.5)
- T23 - Primary Containment (2.4.3)
- T48 - Primary Containment Purge and Inerting (2.3.3.7)
Aging Effects Requiring Management
- Loss of material (C.1.2.2.1) due to general corrosion, galvanic corrosion, crevice corrosion, pitting, microbiologically influenced corrosion (MIC), and erosion corrosion.
- Cracking (C.1.2.2.2) due to thermal fatigue.
A complete discussion of the applicable aging effect determinations may be found in section C.1 of the LRA or by using the above links. Aging Management Programs Aging management programs determined to manage aging effects requiring management are as follows:
- Suppression Pool Chemistry Control (A.1.7)
- Protective Coatings Program (A.2.3)
Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal C.2-60
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 355 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
Identification SHEET 355 of of Commodities 363 C.2, Aging Management Reviews C.2.2.6 Non-Class 1 Components River Water Environment Description River water consists of water taken directly from the Altamaha River for use as cooling water for various systems. See section C.1.2.4 for a description of the river water environment. C.2.2.6.1 Aging Management Review for Non-Class 1 Carbon Steel Components Within the River Water Environment This commodity group includes carbon steel components exposed to an internal environment of river water. The following component types are included within this evaluation:
- Piping
- Valve bodies
- Strainer bodies
- Discharge venturies
- Sight glass bodies
- Thermowells
- Pump discharge columns
- Pump discharge heads Systems
- W33 - Traveling Water Screen, Trash Racks (2.3.4.16)
- P41 - Plant Service Water (2.3.4.7)
- E11 - Residual Heat Removal (2.3.3.2)
Aging Effects Requiring Management
- Loss of material (C.1.2.4.1) due to general corrosion, galvanic corrosion, erosion corrosion, crevice corrosion, pitting, microbiologically influenced corrosion (MIC), and fouling.
- Cracking (C.1.2.4.2) due to thermal fatigue. This aging effect is not applicable to the E11 and P41 pump discharge columns/discharge heads in this environment since the components are submerged in river water and are free to expand or contract.
- Flow blockage (C.1.2.4.3) due to fouling.
A complete discussion of aging effect determination is found in section C.1 or by following the above links. Aging Management Programs Aging management programs determined to manage aging effects requiring management are as follows:
- PSW and RHRSW Chemistry Control (A.1.4)
- PSW and RHRSW Inspection Program (A.1.13)
Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal C.2-87
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 356 of 363 A-47039 Attachment C LICENSE Identification RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 356 of 363 of Commodities C.2, Aging Management Reviews C.2.2.6.2 Aging Management Review for Non-Class 1 Stainless Steel Components Within the River Water Environment This commodity group includes stainless steel and cast austenitic stainless steel components with an internal environment of river water. The following component types are included within this evaluation:
- Piping
- Tubing
- Restricting orifices
- Thermowells
- Strainer baskets
- Flexible connectors
- Valve bodies
- Pump bowl assemblies
- Site glass body Systems
- E11 - Residual Heat Removal System (2.3.3.2)
- P41 - Plant Service Water (2.3.4.7)
Aging Effects Requiring Management
- Loss of material (C.1.2.4.1) due to crevice corrosion, pitting, microbiologically influenced corrosion (MIC), and fouling.
- Cracking (C.1.2.4.2) due thermal fatigue. This aging effect is not applicable to the P41 strainer baskets and the E11 and P41 pump bowl assemblies in this environment since the components are submerged in river water and are free to expand or contract.
- Flow blockage (C.1.2.4.3) due to fouling.
A complete discussion of aging effect determination is found in section C.1 or by following the above links. Aging Management Programs Aging management programs determined to manage aging effects requiring management are as follows:
- PSW and RHRSW Chemistry Control (A.1.4)
- PSW and RHRSW Inspection Program (A.1.13)
- Structural Monitoring Program (A.2.5)
A complete discussion of the applicable aging management programs may be found in Appendix A of the LRA or by using the above links. Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal C.2-92
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 357 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
Identification SHEET 357 of of Commodities 363 C.2, Aging Management Reviews C.2.2.6.4 Aging Management Review for Non-Class 1 Gray Cast Iron Components Within the River Water Environment This commodity group includes gray cast iron components with an internal environment of river water. The following component types are included within this evaluation:
- Strainers and Strainer Baskets Systems P41 - Plant Service Water (2.3.4.7)
Aging Effects Requiring Management
- Loss of material (C.1.2.4.1) due to crevice corrosion, pitting, general corrosion, microbiologically influenced corrosion (MIC), selective leaching, erosion corrosion, galvanic corrosion, and fouling.
- Cracking (C.1.2.4.2) due to thermal fatigue. This aging effect is not applicable to the strainer baskets since the components are submerged in this environment and are free to expand or contract.
- Flow blockage (C.1.2.4.3) due to fouling.
A complete discussion of aging effect determination is found in section C.1 or by following the above links. Aging Management Programs Aging management programs determined to manage aging effects requiring management are as follows:
- PSW and RHRSW Chemistry Control (A.1.4)
- PSW and RHRSW Inspection Program (A.1.13)
- Structural Monitoring Program (A.2.5)
A complete discussion of the applicable aging management programs may be found in Appendix A of the LRA or by using the above links. Demonstration of Aging Management What follows is a demonstration that the aging effects requiring management identified will be adequately managed during the period of extended operation. Management of Loss of Material and Flow Blockage PSW and RHRSW Chemistry Control Program provides for treatment with sodium hypochlorite and sodium bromide. Both sodium hypochlorite and sodium bromide are batch added (shock treatment) to the PSW Systems as required. These additions are intended to minimize MIC and macroorganism intrusion within service water systems. The PSW and RHRSW Inspection Program addresses loss of material and flow blockage and implements Plant Hatchs commitment with regard to Generic Letter 89-13. This program Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal C.2-101
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 358 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
Identification SHEET 358 of of Commodities 363 C.2, Aging Management Reviews C.2.2.7 Non-Class 1 Components Fuel Oil Environment Description Components within section C.2.2.7 are subject to an environment of fuel oil under normal conditions. The fuel oil environment is described in section C.1.2.5. C.2.2.7.1 Aging Management Review for Non-Class 1 Carbon Steel Components Within the Fuel Oil Environment This commodity group includes carbon steel exposed to an internal environment of fuel oil. The following component types are included within this evaluation:
- Large and small bore piping
- Valve bodies
- EDG transfer pump
- EDG day tanks
- EDG storage tanks
- EDG transfer pump discharge head Systems Y52 - Fuel Oil (2.3.4.19)
Aging Effects Requiring Management
- Loss of material (C.1.2.5.1) due to general corrosion, galvanic corrosion, crevice corrosion, pitting, and MIC.
- Cracking (C.1.2.5.2) due to thermal fatigue. This aging effect is not applicable to the EDG storage tanks since the tanks are underground and temperature fluctuations are insignificant.
A complete discussion of the applicable aging effect determinations may be found in section C.1 of the LRA or by using the above links. Aging Management Programs Aging management programs determined to manage aging effects requiring management are as follows:
- Diesel Fuel Oil Testing (A.1.3)
A complete discussion of the applicable aging management programs may be found in Appendix A of the LRA or by using the above links. Demonstration of Aging Management What follows is a demonstration that the aging effects requiring management identified will be adequately managed during the period of extended operation. Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal C.2-105
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 359 of 363 A-47039 Attachment C LICENSE Identification RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 359 of 363 of Commodities C.2, Aging Management Reviews C.2.2.7.2 Aging Management Review for Non-Class 1 Stainless Steel Components Within the Fuel Oil Environment This commodity group includes stainless steel components exposed to an internal environment of fuel oil. The following component types are included within this evaluation:
- Piping
- Flexible hose
- Strainer baskets
- Valve bodies Systems Y52 - Fuel Oil (2.3.4.19)
Aging Effects Requiring Management
- Loss of material (C.1.2.5.1) due to crevice corrosion, pitting, and microbiologically influenced corrosion (MIC).
- Cracking (C.1.2.5.2) due to thermal fatigue. This aging effect is not applicable to the strainer baskets since the components are submerged in fuel oil.
A complete discussion of the applicable aging effect determinations may be found in section C.1 of the LRA or by using the above links. Aging Management Programs Aging management programs determined to manage aging effects requiring management are as follows:
- Diesel Fuel Oil Testing (A.1.3)
A complete discussion of the applicable aging management programs may be found in Appendix A of the LRA or by using the above links. Demonstration of Aging Management What follows is a demonstration that the aging effects requiring management identified will be adequately managed during the period of extended operation. Management of Loss of Material due to General Corrosion, Galvanic corrosion, Pitting, Crevice Corrosion, and MIC Diesel Fuel Oil Testing provides for sampling and analysis of fuel oil deliveries for water and sediment contamination. Biocides are also added at this time in order to minimize the potential for MIC within components. Water and sediment contamination levels within storage tanks are checked on a regular basis to assure that no significant buildup of contaminants exists. If excessive contamination does occur, the program provides for draining and cleaning of the tank as required to reestablish and maintain acceptable contaminant levels. Fuel oil is also tested for proper viscosity and specific gravity, thereby Edwin I. Hatch Nuclear Plant February 2000 Application for License Renewal C.2-108
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 360 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 360 of 363 From: Baker, Ray D. Sent: Friday, October 13, 2000 1:34 PM To: 'William F. Burton (E-mail)'
Subject:
Scoping/Screening RAI Follow-up
- Butch, Discussions were conducted the week of September 11, 2000 with NRC regarding certain fire protection RAls and responses. Several aspects of those questions and responses have been clarified by NRC and SNC. The attached files along with files provided to NRC on October 1, 2000 document those clarifications. The clarifications include:
- RAI 2.3.4-FPS-3 Part 1: Additional discussion of the basis for make-up water to the fire water tanks not being in the scope of license renewal for Plant Hatch is provided. REVISED RAI RESPONSE ATTACHED.
- RAI 2.3.4-FPS-3 Part 2: The Fire Hazards Analysis is being revised to restore language previously removed regarding operability requirements for three fire hydrants, including surveillance requirements for those hydrants.
This revised RAI response was previously provided to NRC by electronic communication on October 1, 2000.
- RAI 2.3.4-FPS-3 Part 5: Additional discussion is provided regarding the short lived determination for several components. In addition, documentation is provided regarding water fire hose surveillance/replacement.
REVISED RAI RESPONSE ATTACHED.
- RAI 2.3.4-FPS-3 Part 7: Additional clarification regarding short lived determination for certain components is provided in the revised response to RAI 2.3.4-FPS-3 Part 5.
- RAI 2.3.4-FPS-3 Part 8: This revised response was previously provided to NRC by electronic communication on October 1, 2000. Also included in that e-mail were three revised evaluation boundary drawing files.
- RAI 2.3.4-FPS-10: This revised response confirms discussions between SNC and NRC regarding a one-time removal and inspection of sprinkler heads consistent with guidance contained in NFPA 25. REVISED RAI RESPONSE ATTACHED.
Please let me know if you have any questions regarding these revised responses. Ray Baker 8-992-7367 '~/ways do right. This will gratify some people and astonish the rest." -- Mark Twain ATTACHMENTS RAl-2.3.4-FPS-3_ 1rRAl-2.3.4-FPS-3_5r'.:{Al-2.3.4-FPS-1 Or1 1.doc (25 KB... 1.doc (26 KB... doc (26 KB) ...
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 361 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 361 of 363 PART 1 OF RAI - 2.3.4 - FPS - 3: Exclusion of certain fire protection components from the scope of license renewal and from an aging management review
- 1. Dedicated Storage Tanks (a) The applicant states in LRA Section 2.3.4.18, that the water supply for the fire protection system inside the protected area is provided by two 300,000 gallon dedicated storage tanks. Each tank is supplied by two deep wells, each with a 700 gpm makeup pump capable of refilling either tank within 8 hours. Flow diagram Volume 1, HL-11033, Sheet 1, Fire Protection Piping P&ID Pumphouse Layout, shows that the tank fill line is not highlighted to include this piping within the scope of license renewal.
This piping appears to provide water from underground wells to the dedicated storage tanks. Justify the exclusion of this piping from within the scope of license renewal. (b) Flow diagram Volume 1, HL-11033, Sheet 1, Fire Protection Piping P&ID Pumphouse Layout, does not show the pumps which draw water from the wells. Since these wells supply the dedicated storage tanks with water for use by the fire protection system, discuss if these pumps (casings) should also be included within the scope of license renewal and subject to an AMR. RESPONSE TO PART 1 OF RAI - 2.3.4 - FPS - 3 (Revised 9/28/00): As described in the response to RAI 2.3.4-FPS-1, FHA section 9.2 Appendix B identifies the SSCs required to protect safety related or safe shutdown components from the effects of fire, and these SSCs are in scope for license renewal. The well water supply system is not relied upon in FHA section 9.2 Appendix B, and is therefore not in the scope of license renewal. As discussed in a 9/28/00 telecon with NRC, the intent of the well water supply system is not to fight a fire, but to maintain level in the two redundant, 100% capacity each, fire water storage tanks which are maintained at a prescribed level by surveillance requirements. There is sufficient capacity in one tank, at the minimum surveillance level, to quench the design basis fire. The well water supply system is capable of refilling either tank in a minimum of 8 hours, as specified by regulatory requirements. The fill line connects to each tank at the roof such that a break in this line would not drain the associated tank.
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 362 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 362 of 363 PART 5 OF RAI - 2.3.4 - FPS - 3: Exclusion of certain fire protection components from the scope of license renewal and from an aging management review
- 5. System filters, fire extinguishers, fire hoses, and air packs:
System filters, fire extinguishers, fire hoses, and air packs are not included within the scope of license renewal and are not subject to an AMR. (In a July 6, 2000 phone call, the applicant clarified that systems filters were included within scope and are subject to an AMR. However, in the LRA, they are listed as strainers in Table 2.3.4-18). As a result of the staffs experience with license renewal, the staff has found that fire extinguishers, fire hoses, and air packs (within the scope of license renewal) may be excluded, on a plant-specific basis, from an aging management review under 10 CFR 54.21(a)(1)(ii). These components are considered within the scope of license renewal and are typically replaced based on specific performance and condition monitoring activities that clearly establish a routine replacement practice based on a qualified life component. These components may be excluded based on specific performance and condition monitoring activities provided that the applicant (1) identifies and lists in the LRA each component type subject to such replacement, and (2) identifies the applicable programs that conform to appropriate standards (e.g., for fire protection components - applicable NFPA standards and 42 CFR Part 84). Justify the exclusion of these components from the scope of license renewal and an AMR. RESPONSE TO PART 5 OF RAI - 2.3.4 - FPS - 3 (Revised 9/28/00): Pursuant to discussions held with NRC during the scoping inspection performed September 11, 2000 through September 15, 2000, the following revised response to this RAI is provided. Filters are identified as strainers in the fire protection system. There are two types of strainers used in the fire protection system: Y-strainers and pipe line basket strainers. Both types are subject to aging management and are included in scope for license renewal. Fire extinguishers, air packs, and CO2 hoses are short lived components based on replacement intervals per site approved procedures, and are therefore not subject to AMR. The replacement intervals established by plant procedures are as follows: CO2 fire extinguisher replacement every 5 years, and dry chemical fire extinguisher replacement every 12 years; air pack replacement every 15 years; CO2 hose replacement every 5 years. The plant procedures also specify inspection and testing intervals. Water fire hoses are condition and performance monitored routinely, and replaced based on degradation criteria specified in a site-approved procedure, and are therefore not subject to AMR. By plant procedure, water fire hoses are to be unracked, visually inspected, and hydrostatically tested every 2 years. Water fire hoses that do not meet the inspection or hydrostatic test criteria are replaced. Water fire hoses were inadvertently omitted from Table 3.2.4-18.
A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW
SUMMARY
SHEET 363 of 363 A-47039 Attachment C LICENSE RENEWAL AGING MANAGEMENT REVIEW
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SHEET 363 of 363 RAI - 2.3.4 - FPS - 10: LRA Section A.2.1.3 states that the fire protection system design was reviewed against the applicable NFPA codes. NFPA 25, Section 2.3.3.1, Sprinklers, states that where sprinklers have been in place for 50 years, they shall be replaced or representative samples from one or more sample areas shall be submitted to a recognized testing laboratory for field service testing. As part of the fire protection license renewal programs at Hatch, discuss if NFPA 25 will be implemented to ensure that any aging effects have not degraded the sprinkler and its components from the original performance criteria as intended by the listing. If NFPA 25 will not be implemented at Hatch, provide justification and evidence that other means to detect aging of sprinklers, equivalent to NFPA 25, are available through plant-specific programs and procedures. RESPONSE TO RAI - 2.3.4 - FPS - 10 (Revised 9/28/00): Pursuant to discussions held with NRC during the scoping inspection performed September 11, 2000 through September 15, 2000, the following revised response to this RAI is provided. Although Plant Hatch uses NFPA 25 as general design guidance, Plant Hatch is not committed to compliance with it. Plant Hatch is committed to regulatory requirements as described in the FHA. Thus, in a manner consistent with the guidance of NFPA 25, a one-time inspection will be performed at, or before, 50 years of service life for sprinkler heads in the scope of license renewal. A random sampling of each type of sprinkler head in the scope of license renewal will be submitted to a recognized laboratory for testing. Based on the results, corrective actions would be accomplished, if required, to assure continued sprinkler head function during the period of extended operation. Appendix B, Section 2.1, descibes this one-time inspection which is called Sprinkler Head Inspections. Periodic condition and performance monitoring of sprinkler heads is also performed by the fire protection activities.
L9 101 -H UNIT 23 ' - I 1" 23'-11 " 21*-11
- 5'-9" 23'-l I" DRYER & SEPARATOR SUNG ASSEl.lBLY (1) COMMON BOTH UNITS REFUELING FLOOR STORED IN ORYWELL HEAD/ EQUIPMENT HATCH REACTOR CAVITY SHIELD l '+~~-+---~ I PLUG LAYOOWN AREA OF UNIT IN OPERATION TRANSFER CANAL 5 TONS SEAL ASSEMBLY 16 TONS (1) COMMON BOTH UNITS TRANSFER CANAL SEAL ASSEMBLY z 16 TONS ;:/._ °:i
( 1) COMMON BOTH ~ ~ UNITS --=
'- z-FUEL POOL GATES EXCLUSION AREA FO R V IT 2 CRANE
~: ~5 Tci~~s (8~PE~) ~~ISu;m 1 CRANE AUX. OR MONORAIL 80 TONS EA CH GATES ARE NOT USED (TYP 3 PLACES) ON SOUTH WALL OF CASK PIT NOTES : !'IDlES.;_(CONT'D)
HEAD STRONGBACK 4 TONS (1) COJ.1MON BOTH UNITS 1 . 0NLY THE UNIT 1 CRANE MAIN HOIST IS SINGLE-FAILURE PROOF 17. 33 TON PLUG #4 MAY BE STACKED ON 33 TON PLUG 12 FLOOR
- 2. USE OF ANY HOIST OTHER THAN THE UN IT 11 CRANE MAIN HOIST OVER ANY LOAD ING BETWEEN THE STACKED PLUGS AND MOISTURE SEPARATOR EQUIPMENT REQUIRED TO REACH & MAINTAIN COLD SHUTDOWN IS PROHIBITED POOL MUST BE LIM ITED TO 200 PSf WITH PLUGS IN A STACKED 3, ONLY THE UNIT 1 CRANE MAIN HOIST WILL BE USED TO LIFT THE 125 TON CONF IGURATION SPENT FUEL CASK AND THE FUEL POOL GATES UNIT 1 - HEAVY LOAO PATHS FOR CONTROL
- 18. THE STORAGE LOCATION FOR THE 10 TON SPENT FUEL POOL PLUGS IS ROOM ROOF 4 . 0NLY THE UNIT 1 CRANE MAIN HOIST Will BE USED IN EITHER UNIT TO MOVE NOT SHOWN. THE FLOOR LOAD ING FOR THESE PLUGS IS _s: 1000 PSF THE REACTOR CAV1TY SHIELD PLUGS. DRYWELL HEAD. RPV HEAD. RPV HEAO AND MAY BE STORED IN ANY CONVENIENT LOCATION WHERE THE H-10171 HEAVY LOAOS MATRIX WEIGHTS & LIFTS HEAVY LOAD ITEM WEIGHT MAX HEIGHT IFTJ ON ABOVE REFUEL Fl OOR ;~~oi~~,;~~S~OA~~~ ~~M~~\~~IT~Rg~ ~~~~~u~o~~~L R~E~~1~6~~~T~g~ ALLOWAB LE FLOOR LOADING IS 1000 PSF HT - 1 630 REQUEST FOR ENGINEERING ASSISTANCE REF UEL ING ~ f80TTOM OF JTEHJ 5. THE UNIT 2 CRANE SHALL NOT BE USED TO MOVE EITHER UNIT ' S DRYWELL SlGM-MLH-004-0 NUREG-0612 HEAVY LOAD MOVEMENT HEAD OR REACTOR PRESSURE VESSEL HEAO FROM ONE UNIT TO THE OTHER 1 REACTOR PRESSURE (SEE NOTES 5, 15 & 16)
- 6. THE UNIT 2 CRANE MAY BE USED TO MOVE THE MOISTURE SEPARATOR OR VESSEL HEA O STEAM DRYER TO OR FROM THEIR OPERATING LOCATIONS TO THE APPROPRtATE 2 REACTOR CAVITY (SEE NOTES 7 & 8) LAYDOWN AREA FOR THAT SPECIFIC UNIT WITH A LIFT HEIGHT RESTRICTION OF GE REPORT A00-576 SHROUD HEAD ANO STEAM DRYER DROP SH I ELD PLUGS (OUTER) 6-5 FEET ABOVE THE LAYDOWN AREA (EL 203 ' -0") CONSEQUENCES ( IC- 19039)
J REACTOR CAVITY (SEE NOTES 7 & 8) 7. THE UNIT 2 CRANE CAN BE USED TO CARRY REACTOR CAVITY SHIELD PLUGS ALONG LOAD PATH FROM ONE UNIT TO THE OTHER PROVIDED THAT THEY ARE BECHTEL CALCULATION DROP OF SEPARATOR, STEAM DRYER AND REACTOR SH I El D Pl UGS (INNER) BH0-C-S08-V003-00 16 CAVITY SHIELD PLUGS ORIENTED TO ENSURE THAT NO PORTION TRAVELS OVER THE FUEL POOLS OR 4 ORYllELL HEAD Lf5.0 5.0 (SEE NOTE 5) EQUIPMENT HATCHES BECHTEL CALCULATION CASK. RPV HEAD ANO ORYWELL HEAO DROPS s POOL PL UGS 7o.o LARGE ONE 2.0 8 . SHIELD PLUGS CAN BE TEMPORARILY SET DOWN ANYWHERE ON THE NORTH- 8HO-C-S08-V001-0009 ONTO REFUEL FLOOR
*n.o
,_o SMALLER SOUTH LOAD PATH ALONG COLUMN LI NE RH FOR TRANSFERRING FROM ONE UN IT CRANE TO THE OTHER BECHTEL CALCULATION REFUEL FLOOR SLAB ANALYSIS FOR MISC 6 SPENT FUEL POOL ro .o 9 . FLOOR OESIGNED FOR 1000 PSF LIV E LOAD UNLESS OTHERWISE NOTED 8HO-C-S08-V002-0001 LOAD DROPS PLUGS 10 . 0N LY THE UNIT 1 CRANE MAIN HOIST WILL BE USED TO LIFT THE 360 DEGREE 7 SERVICE PLATFORM WORK PLATFORM FROM ONE REACTOR BUILDING TO THE OTHER USING DESIGNATED 8 RPV HEA D INSULATI ON 12.0 WIRE ROPE SLINGS. SAFE LOAD PATH INCLUDES A SUFFICIENT LIFT HEIGHT TO
'-0 AVOID INTERFERENCES SUCH AS HANDRAIL & DECAY HEAT REMOVAL PIPING 9 REACTOR CAVITY / SPENT FUEL POO L AND SUPPORTS CAffiE CHUTE 11
- 10. TRANSFER CANAL SEAL ASSY 11 DRYER SEPARATOR POOL GATES 16.0 20.0 (SEE NOTE 14)
* ~E~W~Z~~~:~~:~EtJ!! ~Ll~s~1:rm~:t2 !E\it~~~t~~f:g~~~1~~1s GREATER THAN 30" A
(SEE NOTE 11) 12. ~5 i~R~Gb._DL~~~e.~To~FMr~E Bk4~N?~~~~~~gT~~TSA~r s~~~8lLUGS LOCAT ION SHOWN FOR THE DRYWELL HEAD SOUTHERN 13
- R;i6 \~~E~NliL~G~r~~$RBfA~~Rf~ ~~ f~~G*TN (~~~E9~i~T~~u~~v~D 1
COMPANY SHIELD PLUGS OF UNIT 2. PROVIDED THE UNIT 1 CRANE MAIN HOIST IS USED TO LIFT AND MOVE PLUGS TO AND FROM THIS LOCATIO N. PLUGS CAN BE STACKED TWO HIGH
- 14. THE DRYER/SEPARATOR GATES ARE NOT COMMONLY USED. MOVEMENT OF THE DRYER SEPARATOR GATES WITH THE UNIT 2 CRANE CONSTITUTES A SPECIAL LIFT REQUIRING A LOAD DROP EVALUATION RE VISED PER
- 15. TH E UNIT 2 CRANE SHALL NOT BE USED TO MOVE THE REACTOR PRESSURE ABN- H03967,VER1.0 VESSEL HEAO CAROUSEL/TENSIONER ASSEMBLY (WITH OR WITHOUT THE RPV HEAO ATIACHED) 16.LIFTING OF THE RPV HEAO IS ONLY ALLOWED WITH THE USE OF THE HEAD STRONGBACK (1F13-E009) FOR THIS EVALUATED HEIGHT 10-502 H-10167 13.0
6l 0 l l-H H- 11 174 TB-1-20 GV-242 I N. 174 N21*FI 10
< H-1107S) NOTES I ~O~~ll'~ DWG . WITH DWGS H-116()'3, H*l !6Cfi ,
< ~~~~~~J~~3) E - ~- SEE H*l 1616 FOR VENTS & DRAINS 1N21-R811 REFER TO PIPING & INSTRUMENT SYMBOLS D\.Ki. S*ISOSI FOO LEC£ND 4 FOR COMPO NENTS REPLACED AS A RESULT OF FLOW ACCELERATED CORROSION ( FAC),
REFER TO HATCH UNIT 1 EROSION/CORROSION MAN UAL 24"GEE 5 1N21 B003A, 1 N2 180038, 1N218004A & 1 N2 1 800 48 TUBE SLEEVES INSTALLED.
~-
1N21-R811 REFERENCES'
- 1. H*l 1601 P.&I.D. COND.& FEEDNATER SYS. SHT.2.
- 2. H-11604 P&l.D COND.& FEEDWATER SYS. SHT. 1 J H-l lbl'Y1 P.&10. COND.& FE£D,./ATER SYS. SHT. 4 .
- 4. H- 11148 SERVICE JET AIR EJECTION DRAIN TO CONDENSATE
- 5. H- 11 066 PIPING: REACTOR FEED Pl..W DISCH
- 6. H- 11 076 PIPING: COND. MAKE-UP & STORAGE INS1DE TURBINE BLDG. & OEMIN-IS " GEE ERAL12ED WATER INSIDE BLDG
- 1. H-! 1077 PIPING: CONO.MAKE*UP & STORAGE aJTSIDE OF BLDG a H- 1107"3 PlPING : COND. CONDENSER TO GLAND SEAL STEAM CONDENSER.
l H-11018 P.& I.D. DEMlNERALIZED WATER .
< H~~;~~:~~;10&- A- - ~O ~;~* -~~4J: 10 H- l l lOS PIPING- RFP MINIMUM FLOW TO CONDENSER.
- 11. H- 11162 PI PING MODIF!CATlON -COND. AND
- -~ COND. BOOSTER PUMP MIN. FLOW B TO N21-R04JB 12. D-11040 COND. BOOSTER PUMP MIN. FLOW 101!:! STG . L. P. HEATER .. 8. SPRAY HEADER N21*00018 ( s:j~l0=26~)~-t--t+- 13.8-1 1020 RFP A& B MIN. FLOW SPRAY HEADER
- 14. H-11074 PIPING: COND.-GLAND SEAL STEAM (S EE NOTE 5) COND. TO TENTH STG. HEATER .
t5. H-1107S PIPING : COND . TENTH STG.HTR.TO REACTOR FEED AJMP
- 16. DELETED
- 17. H-16408
- 18. H-11026 19 H*ll 6 1S 24 "GEE 20.H- 11616 21.H-1 1000 22H -l 1471 23.S- 14815
< H-11605
~_Z_ON_E_E_ -_2_~ CRITICAL CCCUMENT MPL # N21 ovv2000 SOUTHERN COMPANY A
1
- ~~~~g3m. VER. 1.0 EOW~~p11NGH~Cl~S~~~~~~~A~l~~TOl~~~A~o.
CONOENSATE & fEEOWATER SYS. SHT. 1
R~-N7S8A,8&C fl.HA-I R43 R43 N0 14A,8&C;N016A,B&C "'
§ R43- R43-N013A,8&C;N015A.B&C R43-N767A,B&C HlA-\
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- 1. UN!T-2 PIPINGfROM'EF!JELOIL 5:W:=R1 STORAGE TANKS TO THE OIESH SKIDISSEISl.UC 2.Al.J.PIPINGTHISOl?AW!NGfORUNrT I T081:ClASSR43-HG£ 3.f0ROIESELGENERATOR2A&2CPIPING SEEH-210H
- 4. fOR 1R~-N768A, THIS Oll.IENSIONISJ 1/2'.
5.fOR1R43- N767A,THISOIMENSIONIS131/2" CRITICAL OCCUMENT MPL No. R43 1AcA0200 0! H110l7 1 SOUTHERN COMPANY A REVISED PER EOW!N I. HATCH NUC LEAR PLANT UNIT No. 1 ABN-H01523.VER.1.0 P&!O FUEL OIL DIESEL OIL SYSTEM P.,,~'~"'!",f"AA"1;f'i!!eif.i~sti\'i'!Jll\~i/.f,,1==:::i~=F=:"'C::::::I 10-502 H-11037 29.0 7 I
6£01 t-H fROUP52-f405 COMPRESSOR IN TERNAL INST. MPL NUMBERS H-11641 B-11 OOMESTIC VENDOR DOMESTIC VENDOR TE-N076A TT11 OP-N085A TE-N077A TT21 .------------------------------- TE-N078A TT18 TE-N079A TT29 , 1/2" HEE TE-NOBOA TT44 TE-N082A TT59 L 8"J8E 8"X<" 8 TO P52 INSTRUMENT AIR SYSTEM 4-JBE SEE NOTE 8
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SEE REFERENCE 5 ANO 6 COMPRESSOR INTERNAL INST. MPL NUMBERS DOMESTIC VENDOR DOMESTIC VE NDOR NOTES* TT11 1 ALL EQUIPMENT ANO INSTRUMENTS PREFIXED BY 10"MEE TE N0776 TI21 MPL NO. P51 UNLESS OTI-IERWISE NOTED TE N078B ms PTN0876 2 ANY ADDITIONAL HIGH POINT VENTS &: LOW TE - N079B TT29 P~NT DRAINS TO BE ADOED BY FJELD TE-NOBOB n .. ppo AS NECESSARY TE N0818 TT51 3 ALL DRAINS ARE 1" UNLESS SPECIFIED OTHERWISE TE N0828 PTN091B 4 FOR LOCATION ANO IDENTIFICATION Of" INSTRUMENTS TE N0838 S£E INSTRUMENT DATA SHEET LISTED IN MPL FOR EACH INSTRUMEN T 5
'i-iLELA:~V1TiEHAJ'kC~~~~1!iis:A~~s TO BE 1" UNLESS SPECIFIED OTI-IERWISE 6 INSTRUMENT AIR(P52) RELATED COMPONENTS ARE ON H-11641
- 7. CONNECT THIS INSTRUMENT TO INDICATING FLOW METER IN.324-0/P51-R501
- 8. f200A,6,C VALVES OPEN AT 100 PSI ANO CLOSE AT 80 PSI
- 9. PRESSURE SWITCHES N201A,8,C OPEN AT 80 PSI ANO CLOSE AT 100 PSI
- 10. THERE IS NO HANOWHEEL FOR VALVES f10B1A, 8 &: C THESE ARE MANUAL CONTROL VALVES USEO FOR INITIAL SETUP Of THE DRYER EQUIPMENT
- 11. SAMPLE VALVES f319A, B &: C ARE NORMALLY THROTTLED
_ TO APPROXIMATELY 2 SCFH 49 0
- 12. OUTLINED COMPONENTS ARE INTEGRAL TO DRYER ASSEMBLY COMPRESSOR INTERNAL DOMESTIC VENDOR
REFERENCES:
TE N076C TT11 PIPING DIAGRAM INST AIR TO HVAC TE-N077C TT21 &: H.P.SER'vlCE AIR PIPING-SHT.2 TE-N078C TT18 CONTROL BUILDING SER'vlCE AIR TE N079C TT29 SYSTEM-P&:ID SHT.1 TE - N080C TT44 T-N089C PT29 TE N081 C TT51 PIPING &: INSTRUMENTATION DIAGRAM TE-N082C TT59 SER'vlCE AIR AT HIGH PRESSURE AIR COMPRESSOR-SHEET 2 PIPING &: INSTRUMENTATION DIAGRAM INSTRUMENT AIR TO HVAC &: H.P 1 t/2" HEE SER'vlCE AIR PIPING-SHEET 1 STATION SER'vlCE AIR COMPRESSORS-CLOSED LOOP COOLING SYSTEM P&:ID P&ID-STATION SERVICE AIR COMPRESSOR INTERNALS 8"JBE 8"J8E CRITICAL OOCUMENT MPL # P51-1010 1Aca d2K I H11 039 I SOUTHERN COMPANY A e~~~~ ~:~ A6N-H0332 1, EDWIN I. HATCH NUCLEAR PLANT UNIT No 1 PIPING&: IN STRU MENTATION DIAGRAM SE RVICE AI R AT HI GH PRESS URE 1/2"UNION AIR CO MPRESSORS FlOORDRAINY 7 I
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- 1 11"1'°'\ R£VISEOPERABN EDW IN I. HATCH NU CLEAR PLANT UNIT No. 1 30" 5£RV ICE 'WAr£R lm lT 1"10 I IH-!114t..) 106078980 1Ml21 , V[R .1.0 GE NERA L ARRAN GEMENT - OUTSIDE PIPING N57 +50 TO N60+ 00 & E5 1+00 TO E5 4+ 70 ,
N60+ 40 & E49 +20 TO RIVER
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( NOTE 6 ) \ ~ P41 -F1286l
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P41-F1285 ~ \_ _/w/15.850RILL (NOTE 6) 6" HEE (NOTE 7) 10°P41-HEETOREACTORBLDG IN.407-2 FOR CONTINUATION
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0-11001 30" P41-HEE 30"P4\ -HEE ZONE A-2 i----- ---- --------- ------ ------ -----------------------------.., ~:::~WA~W= INTAKE FOR CONTI NUATION SEE OWG. H- 11036 a 6"N1-HEE P41-0171
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--f -- ji' P41-0169- LC GV- 1558 . . RI.IS
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- 1. THIS DRAWING WK.:. ORJGINALLY A PART OF 0 -11001
- 2. WORK THIS DRAWING WITH OWG. 0-11001
- 3. ~~~E~~~~G H-11 024 FOR NOTES ANO P41-f553A
- 4. VENT & DRAIN VALVES MARKED :t' ARE IN324F-l PART OF 12" SHIELD P!PE.
5 1/2"X 1/4-ROCR
- l~~cJi~L Tgn~~.'6~A%':Et 0:0uMR~; ~~IONAL ALIGNMENT. SEE RER C050450001
,, CRITICAL DCCUMENT MPL NO. P41 SOUTHERN COMPANY A.
6 . VALVE F1285 ts NORMALLY CLOSED AND BLIND
~~~~ ~U~~~~~~A~[~~~:;~~:~;~=D CHILLED WATER SYSTEM REVISEOPERABN EDWIN I. HATCH NUCLEAR PLANT UNIT No. 1
- 7. TEMPORARY CHILLED WATER PIPING IS CLASS SNC351750M006, VER 1.0 HEE MATERIAL. HOWEVER, CONSTRUCTION MAY IAK.R0-4A BE WELDED OR MECHANICAL JOINTED PIPING P.~l&E(~~NSE~~~lg: :~~g 20 (VlCTAULlC GROOVED PIPING OR EQUAL)
~--'-----------j >( :i~~1l 3DISC. RUPTURE PflESS 95PSll.(SEEH-11146)
TO 12TH STACE LOW PRESSURE HEATER "A" H-11020 C-8
~ N21LS
~---- N083 TO 10TH STAGE P650 LOW PRESSURE HEATER "A" 1*x1;r RDCR TX TO 10TH STAGE N025 LOW PRESSURE HEATER "B" 7ii, lfR!FlCE VOLUME H-11020 D-6 P650 , __ L:'~'-, TO 12TH STAGE
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~ N21LS N21-R810 I ,---, I HEATER "B"
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~' 2. THIS DWG ORIGNATED FRO~ OWG H1 1020 11
- 3. WORK THIS OWG WITH OWG'S H11020 H11607
~' H11608, H11646, H11018, H11647 AND H1li74
- 4. FOR ADDITIONAL NOTES & REF.SEE owe H11020.
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- 5. 0 OR 00 DENOTES LINE CONT.ON owc*s H11020. H11607. H11608, H11018 AND H1 1647 6
- itH~~0;~EfRECEDEO BY N22- (UNLESS NOTED
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CRITICAL DOCUMENT MPL NO. N22 SOUTHERN COMPANY A
~~iJf3~\1woo1, VER. 1.0 EDWIN I. HATCH NUCLEAR PLANT UNn No. 1 P & I 0 l.IOISTURE SEPARATOR AND HEATER S~~~}N SYSTEM 2
10-502 1 I}}