ML20052G925
| ML20052G925 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 05/12/1982 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML112990915 | List: |
| References | |
| PROC-820512, NUDOCS 8205190159 | |
| Download: ML20052G925 (46) | |
Text
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- NORTHERN STATES POWER COMPANY l
, MONTICELLO NUCLEAR GENERATING PLANT 1 l DOCKET No. 50-263 LICENSE NO. DPR-22 l 1 i 1 ! l i I l ! ! l 1 . t
- i. INSERVICE INSPECTION AND TESTING PROGRAM t
f f SECOND TEN YEAR INSPECTION INTERVAL l i JUNE 30, 1981 - JUNE 29, 1991 l 4 :- i i 1 I i e ( SUBMITTED: March 27, 1981 REVISED: Revision 1 ! July 30, 1981 { Revision 2 January 18, 1982 i i Revision 3 -{ May 12, 1982 l 1 4 I l 8205190159 820513 PDR ADOCK 05000263 ; O PDR a
- O
, 6 m RECORD OF REVISIONS Page No. Revision No. Page No. Revision No. Cover 3 2-1 3 il Original 3-1 2 iii 3 3-2 Original iv Original 3-3 2 1-1 Original 3-4 Original 1-2 through 1-3 3 3-5 3 1-4 Original 3-6 Original 1-5 through 1-6 3 3-7 3 1-7 Original 3-8 2 1-8 through 1-9 3 3-9 Original 1-10 through 1-20 Original 3-10 through 3-12 3 1-21 through 1-23 3 3-13 2 1-24 Original 3-14 3 1-25 3 3-15 through 3-16 2 1-26 Original 3-17 through 3-18 3 1-27 through 1-28 3 3-19 through 3-22 Original 1-29 through 1-32 Original 3-23 3 1-33 3 4-1 3 1-34 through 1-38 Original 4-2 through 4-7 Original 1-39 3 4-8 through 4-9 3 O 1-40 through 1-43 1-44 1-44A Original 3 3 4-10 4-11 4-12 Original 3 Original 1-45 3 4-14 through 4-15 Original 1-46 through 1-48 Original 4-16 through 4-17 3 1-49 through 1-50 3 4-18 2 1-51 through 1-52 Original 4-20 through 4-32 Original 1-53 through 1-54 3 4"33 through 4-35 1 1-55 Original 4-36 through 4-38 2 1-56 3 4-39 through 4-40 3 1-57 Original 5-1 through 5-31 Original 1-58 3 6-1 through 6-21 Original 1-59 through 1-61 Original 1-62 3 1-63 through 1-65 Original 1-66 3 1-67 through 1-71 Original
-iii- Revision 3 \
5/12/82
]
O O O MONTICELLO NUCLEAR GENERATING PLANT TABLE l1 TEN YEAR INTERVAL - EXAMINATION
SUMMARY
PAGE 1 __ OF 2 ITEM DESOR PilON NDE TOTAL EXAMINATION .NSPECTIONRUPNNG pgyAgg$ COMPONENIOR $YSTEM IDENilFICATION NO. METHOD ITEMS AMOUNi & EXTENT PERIOD % EXAMINATION CATEGORY B-A; PRESSURE RETAINING WELDS IN REACTOR VESSEL Bl.10 SilELL WELDS Bl.11 CIRCUMFERENTIAL FIGURE 2 L=57' RELIEF NO.16 VCBB-1 IID - SilELL VOL 1 6'8" 100% OtiE 12 6'8" 100% TilREE 23 VCBA-2 BELTLINE - 1 NOT ACCESSIBLE - - VCBB-3 COURSE 2-3 - 1 NOT ACCESSIBLE - - Y VCBB-4 COURSE 3-4 VOL 1 4" 5 " 100% ONE 8 10'8" 100% TWO 26 5 '4 " 100% TilREE 36 Bl.12 LONGITUDINAL FIGURE 2 L-11' RELIEF NO.16 VLAA-1 27" BELTLINE VOL 1 4' 100% TilREE 36 VLAA-2 27" BELTLINE VOL 1 9' (l'4" Bel t)l00% TWO 82 VLBA-1 117"BELTLNE - 1 NOT ACCESSIBLE - - VLBA-2 117"BELTLNE - 1 NOT ACCESSIBLE - - VLCB-1 COURSE 3 VOL 1 5'8" 100% TilREE 52 VLCB-2 COURSE 3 VOL 1 5'8" 100% ONE 52 VLDB-1 COURSE 4 VOL 1 4' 100% TilREE 36 VLDB-2 COURSE 4 VOL 1 4'9" 100% ONE 43 m, Bl.20 llEAD WELDS D$ Np Bl.21 CIRCUMFERENTIAL llCCB-2 CLOSURE IID VOL 1 8.5' MIN 100% ONE 34
$g FIGURE 5 8' MIN 100% TWO 66 D L=25' 8.5' MIN 100% TilREE 100 W
FORM 9 7-4 57 8
O O O TABLE I1 MONilCELLO NUCLEAR GENERATING PLANT ' TEN YEAR INTERVAL - EXAMINATION
SUMMARY
PAGE 2 OF 2 ITEM DESCRiPilON NDE TOTAL EXAMINATION NSPECilOta RUttatC pgygpg5 COMPONENT OR SYSTEM IDENilFICATION % NO. METHOD ITEMS AMOUNi& EXTENT PERIOD Bl.21 (CONTINUED) IICAB-1 BOT llD VOL 1 3 100% ONE 7 FIGURE 5 3 100% TWO 14 L-44' 3 100% TilREE 20 Bl.22 MERIDONAL WELD N0'S FIGURE 5 VOL 16 IIMCB-1 CLOSURE IID VOL 1 7 100% ONE 100 llMCB-2 L-7' VOL 1 7' 100% ONE 100 llMCB-3 VOL 1 7' 100% Tl!REE 100 llMCB-4 VOL 1 7' 100% 111REE 100 > llMCB-5 VOL 1 7' 100% Ivo 100
,_. IIMCB-6 VOL 1 7, ' 100% IVO 100 d, llMAB-1 BOT llD VOL 1 2'5" 100% ONE 100 llMAB-2 L=6'2" VOL 1 2'5" 100% TWO 100 llMAB-3 VOL 1 2'5" 100% TWO .
100 llMAB-4 VOL 1 2'5" 100% TilREE 100 llMAB-5 VOL 1 2'5" 100% TilREE 100 llMAB-6 VOL 1 2'5" 100% ONE 100 llMAB-7 VOL 1 2'5" 100% ONE 100 llMAB-8 VOL 1 2'5" 100% ONE 100 llMAB-9 VOL 1 2' 100% ONE 100 llMAB-10 VOL 1 2' 100% TilREE 100 Bl.30 SilELL-TO-FLANGE WELD VCBC-5 FIGURE 6 VOL 1 19' MIN 100% ONE 33 L=57' 19' MIN 100% IWO 67 19' MIN 100% 111REE 100 31.40 llEAD-TO-FLANGE WELD llCCC-1 FIGURE 5&6 VOL 1 19' MIN 100% ONE 33 t'; L=57' 19' MIN 100% IWO 67
$ 19' MIN 100% 111REE 100
" 31.50 REPAIR WELDS NONE - - - - - - -
FOHM 37 4579
~
MONTICELLO NUCLEAR GENERAllNG PLANT ~ TABLE 3.1 TEN YEAR INTERVAL. - EXAMINATION
SUMMARY
PAGE 1 OF . 2 8IEM COMPONENT OR $YSTEM IDENilflCAllON DESCR PiiON NDE TOTAL EXAMINAllON iNSPECilON RUtNNG REMARKS NO. METHOD ITEMS AMOUNT & EXTENT , PERIOD % EXAMINATION CATEGO3Y B-D, FULL PENETRATION P'LDS d IN VESSELS-INSPECTION PROGRMI A REACTOR VESSEL B3.10 N0ZZLE-TO-VESSEL WELDS & 6 B3.20 N0ZZLE INSIDE RADIUS WELD N0'S FIGURE 4 VOL 29 7 SECTION , un IIEAD VENT N7 IIVAD-1 ISI-15 1 100% ONE 33 IIEAD SPRAY N6A RilDD-1 ISI-11D 1 100% IWO 67 IIEAD SPARE N6B llSBD-1 ISI-14 1 100% TilREE 100 STANDBY LIQUID CPAE-1 ISI-17 1 100% IWO 100 CONTROL N10 l MAIN STEAM N3A MSAD-1 ISI-1 1 100% ONE 25 MAIN STEAM N3B MSBD-1 ISI-2 1 100% 111REE 75 MAIN STEAM N3C MSCD-1 ISI-3 1 100% 1MO 50 MAIN STEAM N3D MSDD-1 ISI-4 1 100% 111REE 100 FEEIMATER N4A WAD-1 ISI -5 A 1* 100% ONE 25 *2 per refueling FEEDWATER N4B WBD-1 ISI'5A 1* 100% 1WO 50 outage (NRC FEEDWATER N4C WCD-1 ISI-5B 1* 100% IMO 75 letter to Mr. FEEDWATER N4D WDD-1 ISI-5B 1* 100% 111REE 100 f/ayer, dated RE CORE SPRAY NSA CSAD-1 ISI-6A 1 100% 111REE 100 8-27-81) l-~ $ CORE SPRAY NSB CSBD-1 ISI-6B 1 100% ONE 50 2$ CONTROL ROD DRIVE CRAD-1 ISI-10 1 100% ONE 100 "O RETURN N9 u RECIRC OUTLET N1A RCAD-1 ISI-13A 1 100% ONE 50 RECIRC OUTLET N1B RCB D-1 ISI-13B 1 100% 111REE 100 FORM 17-4579
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MONTICELLO NUCLEAR GENERATING PLANT ' TABLE 3.1 TEN YEAR INTERVAL - EXAMINATION
SUMMARY
PAGE 2 op 2 ITEM COMPONENI OR SYSTEM IDENilFICAllON DESCRsPTION NDE TOTAL EXAMINATION iNSPECilOtw rut # JING ptyggg$ NO. METHOD ITEMS AMOUNT & EX1 TNT PERIOD % B3.106 (CONTINUED) WELD ID'S FIGURE 4 VOL 29 B3.20 RECIRC INLET N2A RRAD-1 ISI-13D 1 100% ONE 10 N2D RRDD-1 ISI-13D 1 100% ONE 20 N2J RRJD-1 ISI-13C 1 100% ONE 30 N211 RRilD-1 ISI-13C 1 100% luo 40 N2E RRED-1 ISI-13D 1 100% 1MO 50 N2C RRCD-1 ISI-13C 1 100% 1WO 60 N2B RRBD-1 ISI-13D 1 100% DIREE 70 N2F RRFD-1 ISI-13C 1 100% DIREE 80 N2C RRCD-1 ISI-13D 1 100% DIREE 90 g N2K RRKD-1 ISI-13C 1 100% DIREE 100 JET PUMP INSTR N8A JPAD-1 ISI-16 1 100% ONE 50 N8B JPBD-1 ISI-16 1 100% DIREE 100 B3.306 PRESSURIZER VESSEL N/A - B3.40 B3.506 STEAM CENERATORS N/A - - - - - - - B3.60 B3.706 IIEAT EXCllANGERS N/A -- - - - - - - B3.80 - UE C& 2E "8 u FORM 9 7-437 3 h
O O O
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MONilCELLO NUCLEAR GENERATING PLANT ' TABLE __ 5.1 1 Op 3 TEN YEAR INTERVAL - EXAMINATION
SUMMARY
PAGE IIEM COMPONENT OR SYSTEM IDENilFICATION DESCRIPTION NDE TOTAL EXAMiHAllON INSPECTION RUNNING REMARKS NO METHOD ITEMS AMOUNT & EXTENT , PERIOD % EXAMINATION CATEGORY B-F; PRES'iURE RETAINING DISSIMILAR METAL WELDS REACTOR VESSEL B5.1U N0ZZLE-TO-SAFE END WELDS WELD N0'S FIGURE 4 S , Vol. 25 llEAD VENT N7 IIVAF-2 ISI-15 1 100% ONE 33 IIEAD SPRAY N6A RilD -2 ISI-11D 1 100% 1WO 67 IIEAD SPARE N6B llSB F-2 ISI-14 1 100% TilREE 100 STANDBY LIQUID CPAF-2 ISI-17 l' 100* qwo 100 CONTROL N10 l CORE SPRAY NSA CSAF-2 ISI-6A 1 100% 111REE 100 CORE SPRAY NSB CSB F-2 ISI-6B 1 100% ONE 50 CRD RETURN N9 CRAF-2 ISI-10 1 100% ONS 100 RECIRC OUTLET N1A RCAF-2 ISI-13A 1 100% ONE 50 RECIRC OUTLET N1B RCBF-2 ISI-13B 1 100% 111REE 100 RECIRC INT.ET N2A RRAF-2 ISI-13D 1 100% ONE 10 N2D RRDF-2 ISI-13D 1 100% ONE 20 N2J RRJF-2 ISI-13C 1 100% ONE 30
. N211 RRilF-2 ISI-13C 1 100% 1WO 40 N2E RREF-2 ISI-13D 1 100% IMO 50 y' g N2G RRGF-2 ISI-13C 1 100% 1WO 60
[;l N2B RRBF-2 ISI-13D 1 100% TliREE 70 g; N2P RRFF-2 ISI-13C 1 100% 111REE 80 N@ N2C RRCF-2 ISI-13D 1 100% TilREE 90 m N2K RRKF-2 ISI-13C 1 100% 111REE 100 F OH M 3 7-41b F t
O O O
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l . 1 MONTICELLO NUCLEAR GENERATING PLANT TABLE 5.1 TEN YEAR INTERVAL.- EXAMINATION
SUMMARY
PAGE._' OF _3 ITEM COMPONENT OR SYSTEM IDENilflCATION DESCRtPilON NDE TOTAL FXAMINATION INSPECTION ku##NG REMARKS NO. METHOD ITEMS /MOUNi & EXTENT PERIOD % B5.10 (CONTINUED) WELD ID'S FIGURE 4 S,VOI 25 l JET PUMP INSTR N8A JPAF-2 ISI-16 1 100% ONC 50 N8B JPBF-2 ISI-16 1 100% TilREE 100 INSTRUMENT LINES N11A VIAF-2 ISI-18 1 100% ONE 25 N11B VIBF-2 ISI-18A 1 100% IWO 50 N12A VICF-2 ISI-19 1 100% TilREE 75 N12B VIDF-2 ISI-19 1 100% TilREE 100
~ $ B5.20 PRESSURIZER N/A - - - - - - -
B5.30 STEAM CENERATORS N/A - - - - - - - B5.40 IIEAT EXCllANGERS N/A - - -- - - - - PIPING 45.50 SAFE END WELDS ' CORE SPRAY A GP-90-7 'IU7-8"EF S,VOL 4 3 100% ONE 75 CSP-90-3 ISI-6A i. 100% Ti!REE 100 ' CS AF-14 CSAF-18 v :o CORE SPRAY B CSP-270-7 'IW11-8"EF S,VOL 4 2 100% ONE 50 2% CSP-270-9 ISI-6B 2 100% 111REE 100 R7 CSBF-12
$$o CSB F-16 w IIPCI-STEAM PSAF-2B PS18-8"Ef S,VOL 2 2 100% 'IVO 100 PSAF-2C ISI-7 FORM 9 7-4579
l - O O O .
'"" MOl4TICELLO NUCLEAR GENERATING PLANT ' TABLE 8.1 PAGE i OF 1EN YEAR INTERVAL - EXAMINATION
SUMMARY
1 IIIM DESCRiPilON NDE TOTAL EXAMINAllON ft4SPECTIOt4MJt#NG pgggggS COMPONENI OR SYSTEM IDENilFICATION NO. , METHOD ITEMS AMOUNT & EXTENT PEClOD % EXAMINATION CATECORY B-II; VESSEL SUPPORTS REACTOR VESSEL B8.10 INTEGRALLY WELDED ATTAClit!ENTS SUPPORT SKIRT llCAll-2 FIGURE 5 S 1 17 100% ONE 32 L-53' 18 100% TWO . 66 18 100% TilREE 100 STABILIZER LUCS LUGS 1-4 FIGURE 6 S 4 tu: LIEF NO. 51 7 - is B8.20 PRESSURIZER N/A - - - - - - - B8.30 STEAM GENERATORS N/A - - - - - - - B8.40 llEAT EXCilANGERS N/A - - - - - - - R Ef C ;i 30
~g u
FOHM 9 7-4 5 7 9 N _ _ . _ _ _ _ _ _ _ . _ _ . . _ . .
O a n v (J~ MONTICELLO NUCLEAR GENERATING PLANT TABLE 91 TEN YEAR INTERVAL - EXAMINATION
SUMMARY
PAGE 1 OF 11 HEM COMPONENI OR $YSTEM IDENilFICAllON DESCRIPilON NDE TOTAL EXAMINATION iNSPECilOtw RUNNING pgyApgg NO METHOD ITEMS AMOUNT & EXIENT PERIOD %
- EXAMINATION CATEGORY B-J;
- ASME SECTION XI PRESSURE RETAINING 1974 EDITION TilRL WELDS IN PIPING SUMMER 1975 ADDENDA USED FOR 89.10 NOMINAL PIPE SIZE DETERMING TiiE 4 IN. AND GREATER EXTENT OF EXAM-INATIONS.
n9.116 CIRCUMFERENTIAL AND 39.12
- LONGITUDINAL WELDS
- Tile LESSIR OF l 12 IN. OR 1 PIPE MAIN STEAM A BUTWELDS PS1-18"ED S,VOL 21 3~ 100% ONE 14 DIMIETER LENG171 7 ISI-1 NONE WO 14 FROM SCllEDULED U 3 100% TilREE 29 CIRC WELD INTER-SECTION WILL BE BUTTWELDS PSI-6"ED S,VOL 6 1 100% ONE 17 EXMlINED.
ISI-1 NONE WO 17 1 100% TilREE 33 MAIN STEAM B BUTWELDS PS2-18"ED S,VOL 26 NONE ONE - ISI-2 4 100% WO 15 3 100% TliREE 27 BUTWELDS PS2-6"ED S,VOL 3 NONE ONE O ISI-2 1 100% WO 33 NONE TilREE 33 hf y; MAIN STEAM C BUTWELDS PS3-18"ED ISI-3 S,VOL 27 2 2 100% 100% ONE WO 7 15 mp 3' 100% TilREE 26 o w BUTWELDS PS3-6"ED S,VOL 3 1 100% ONE 33 ISI-3 NONE TWO 33 NONE TilREE 33 FOHM 97 4578
O O O . MONTICELLO NUCLEAR GENERATING PLANI ~ TABLE 91 TEN YEAR INTERVAL - EXAMINATION
SUMMARY
PAGE 2 OF 11 ITEM DESCRiPIlON N TAL XAMINA 1 INWC OhRUr#ANG RfMARKS COMPONENT OR SYSTEM IDENf61 CATION O B9.11E (CONTINUED) B9.12 MAIN STEAM D BUTWELDS PS4-18"ED S,VOL 24 2 100% ONE 8 ISI-4 1 100% 1WO 13 3 100% TilREE 25 BUTWELDS PS4-6"ED S,VOL 6 1 100% ONE 17 ISI-4 NONE WO 17 1 100% Ti!REE 33 FEEDWATER A BUTWELDS W2B-10"ED S,VOL 13 2 100% ONE 15
" ISI-5A NONE WO 15 1 100% TilREE 23 BUTWELDS W2B-14"ED S,VOL 12 NONE ONE -
ISI-5A 2 100% 1WO 17 1 100% TilREE 25 FEEDWATER B BUTWELDS W2B-10"ED S,VOL 11 NONE ONE - ISI-5A 2 100% WO 18 1 100% TilREE 27 FEEDWATER C BUTWELDS W2A-10"ED S,VOL 11 1 100% ONE 9 ISI-5B NONE WO 9
,g 1 100% TilREE 18 D$
qp FEEIMATER D BUTWELDS W2 A-10"ED S,VOL 13 2 100% ONE 15 mp ISI-5B NONE WO 15 D 1 100% TilREE 23 BUTWELDS W2A-14"ED S,VOL 12 2 100% ONE 17 ISI-5B 1 100% WO 17 NONE TilREE 25 FOHM 97-4579
Q ('~) . (> d . 9*1 h MONTICELLO NUCLEAR GENERATING PLANT ' TABLE PAGE 4 OF __J L_._ E TEN YEAR INTERVAL- EXAMINATION
SUMMARY
IIIM NDE TOTAL EXAMINAllON INSPECTIOr4 Rut ##NG REMARKS COMPONENT OR SYSTEM IDENilF6CAllON DESCRIPTION NO- METHOD ITEMS AMOUNi & EXTENT PERIOD % B9.116 (CONTINUED) B9.12 RilR W30 BUTWELDS W30-16"DB S,VOL 20 2 100% ONE 10 ISI-11C 2 100% WO 20 1 100% TilREE 25 BUTWELDS W30-18"DB S,VOL 2 NONE ONE O ISI-11C 1 100% WO 50 NONE TilREE 50
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[ RilR W36 BUTWELDS W36-4"ED S,VOL 22 NONE ONE - u ISI-11D 3 100% '1WO I 14 3 100% TilREE 27 RECIRC A BUTTWELDS REW13A-28" S,VOL 17 1 100% ONE 6 ISI-13A 2 100% WO 18 2 100% TIIREE 29 RECIRC B BUTWELDS REW13B-28" S,VOL 16 2 100% ONE 13 ISI-13B NONE WO 13 2 100% TilREE 25 RECIRC BYPASS A BUTWELDS REW24 -4" S,VOL 12 2 100% ONE 16 ISI-13AA NONE WO 16 l m, 1 100% TilREE 25 D$ qp RECIRC BYPASS B BUTWELDS REW25 -4" S,VOL 13 2 100% ONE 15 l gg p ISI-13BB 2 100% Wo 31 NONE TilREE 31 u RECIRC MANIFOLD BUTWELDS REW32-22" S,VOL 17 2 100% ONE 12 ISI-13C & 2 100% WO 18 ISI-13D 1 100% TilREE 29 FOHM 37 4578
o o o;- (E* " MONTICELLO NUCLEAR GENERAllNG PLANT [ TEN YEAR INTERVAL- EXAMINATION
SUMMARY
TABLE PAGE 6 91 OF 11__ ITEM NDE TOTAL EXAMINAllON INSPECilOr4 WNNING pgygpg$ COMPONENT OR SYSTEM IDENilFICAllON DESCRIPTION NO. METHOD llEMS AMOUNT & EXTENT PERIOD % B9.116 (CONTINUED) B9.12 RISER C BUTWELDS REW21-12" S,VOL 4 NONE ONE - ISI-13D NONE WO - NONE TilREE - RISER D BUTWELDS REW20-12" S,VOL 4 NONE ONE - ISI-13D NONE 1WO - NONE TilREE - 7 RISER E BUTTWELDS REW19-12" S,VOL 4 . NONE ONE - y ISI-13D NONE WO - NONE TllREE - IIEAD VENT BUTTWELD CLOSURE llD S,VOL 1 100% ONE i 100 l ISI-15 JET PUMP INSTR BUTWELDS N8A & N8B S,VOL 2 NONE ONE - ISI-16 NONE TWO - 1 100% TilREE 50 INSTRUMENT LINES BUT1 WELDS ll"DC i S,VOL 8 1 100% ONE 13 CONDENSIGG AND
- v. 23 FROM N11A6N11B ISI-18618A NONE WO 13 CONSTM1T llEAD D@ 1 100% TilREE 25 CilN1BERS t'O
$$" CRD SCRAM llDR 8" BUTWEl.DS CRD26A-8" S,VOL 6 1 100% ONE 17 CRD26B-8" 1 100% TWO 33 ISI-24A&B NONE TilREE 33 FOHM 37-4579
MONTICELLO NUCLEAR GENERATING PLANT ' TABLE 9.1 TEN YEAR INTERVAL - EXAMINATION
SUMMARY
PAGE 7__ OF 11 ITEM t4DE TOTAL EXAMINAllON ;NSPECilOtJ Rut #JitJC. pryApg5 COMPOtJENI OR SYSTEM IDENTIFICAllON DESCRIPTIOt4 NO METHOD ITEMS AMOUNI& EXTENT PERIOD % i B9.116 (CONTINUED) l 89.12 l GD SQW4 IIDR 6" BUPMrlIE CRD14A-6" S,v0L 17 tDIE OfE - G D148-6" 2 100% 'n o 12 ISI-24A&B 3 100% TREE 29 GD SQW4 IIDR 4" BUPIWEUE CRD13A-4" S,VOL 28 2 100% ONE 7 G D138-4" 2 100% 'INO 14 CRD15A-4" 3 100% 'nIREE 25 G D15B-4" ISI-24A&B
- SCRAM DISOIATCE BUPlWELm G D18-12" S,VOL 2 ,
IDE ONE - 4 VOLUt4E TANK ISI-24C NOTE 'n o - 1 100% 'nREE 50 39.20 tD4TNAL PIPE SIZE IESS 'IIIAN 4 IN. 39.21& CIRCU4FFRFNPIAL AND *'nIE LESSFR OF l 39.22 *IONGITUDINAL WET DS 12 IN. OR 1 PIPE RCIC-SI?W4 BUPIWELDS PS17-3"ED S 15 2 100% ONE 13 Dmn Kni ISI-12 tDE 'n o 13 2 100% 'IIIREE 27 CIf C WELD INTER-SILTION WILL BE STANDBY LIQUID BUPIWELOS Q12-1!3"EF I" S 3 NONE OtE - OONIROL ISI-22 1 100% 'IWO 33 N0tE 'IIREE 33 O gg PMIN STEAM BUPlWELLE PS15-3"ED S 10 2 100% ONE 20 gu OONDI7EATE LEAKOFF ISI-23 IDE 'n o 20 wg 1 100% '11REE 30 u FORM 9 7-4 57 8
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l G A 3__ $ g 1EN3N 1 I - I E . O 1 0 F O g g y g p 1DTM R E SO( EP NVA E DS 0 E W C Xli AB SI L 1 ULR E 1. )4 N L 1 CR1 - OP NO1TI P I CBVTA EE G BG L N 000 0 00
- 00 0 0 0 000 AA TP IN%
N 551 11
- 00 51 00 51
- 70 61 000 111 U
R N OD I E E E E E E E TO CI EOR EOR E E E E E ER EOR EOR EORI EOR PE SP NWi OT T l NWil OTT NWl i NWl i NWI NWi l N O1 T OIT O' l T OT T T % % % %% s: % %% % N 0 0 0 00 00 00 0 NE 0 0 0 00 00 00 0 OT IX 1 1 1 11 11 1 1 1 TE A N & Ii E E E E E E EE MN N N N N N N NN A U O O O O O O OO X O N N N N N N NN EM A
'l 1 2 11 11 21 1 LS AM T
OT TI E 2 2 2 2 3 1 D EO 34 34 34 34 34 34 O Y R DH NTE M SVV TT SVV TT SVV TT SVV TT SVV TT S VV TT N D D A O D E D D D E E E E E " M l i P " 0 4 M R I
"8 8 "8 "8 1A 1 A 1l 12 13 14 - 5 - 5 U C S - - - - - - - - B - B -
S E 1I 2I 3I 4I 2I 2I D SS SS SS TN PI PI PI SS PI WS FI WS F I N A O I L P T N A OI S S G NI N T A DR T T T T T T C DR DR DR DR DR TM I l fl EO DP EO DP EO DP EO DP EO DP EO DP RA A i N LP LP LP LP LP LP EX E D EU WS EU WS EU EU EU EU NE I WS WS WS WS E G- - RL l l AA C E S D A LV R N T CR M Y E A T UET E T R B A B N S O M , S A B C D & N S Y C E S D T A A OI R EP P E 0 R M M M M L O T M D 1 O A A A A R R L R A T U L . P E E E E E E EA I N C RP E 1 P T T T T T T CE E N N O P W 1 U S S S S A A TY I , B S W N O O P U L Y N N N N D M I P I t G L D T I I E E _ O EN M T A S I P N L N N A A I A I A E E MT O C N ; E 1 I P A R A E N M M M I I F F I 1 P F_ I G S O M - V P E T P A K R hm L T N l X O
- O A N E 0 9 _
E B F V I M C 7 5 7- 4 _ 0 7 1 3 M-O E M I N l O H I B O F 7d EdkO w U CS"
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s MONilCELLO NUCLEAR GENERATING PLANT TABLE 11 1 TEN YEAR INTERVAL - EXAMINATION
SUMMARY
PAGE 4 OF 5 ITEM COMPONENT OR SYSTEM IDENilFICAllOtt DESCR PilON NDE TOTAL EXAMINATION INSPECilON RUNNINC' REMARKS NO METHOD ITEMS AMOUNI & EXIENT PERIOD % B11.10 (CONTINUED) llEAD VENT LINE SUPPORTS V15-2"ED VT-3 2 1 100% ONE 50 ISI-15 VT-4 NONE WO 50 1 100% TilREE 100 BOTTOM llEAD DRAIN SUPPORTS REW31-2" VT-3 4 2 100% ONE 50 l ISI-21 VT-4 2 100% WO 100 NONE TilREE 100
- STANDBY LIQUID SUPPORTS CII2-11" 3 VT-3 2 1 100% ONE 50 d, CONTROL ISI-22 VT-4 I 100% WO 100
- NONE 111REE 100 CRD SCRAM SUPPORTS CRD26A-8"DB VT-3 14 4 100% ONE 29 IIEADER A CRD13A-4"DB VT-4 5 100% WO 64 CRD14A-6"DB 5 100% TilREE 100 CRD15A-4"DB ISI-24A CRD SCRAM $UPPORTS CRD26B-8"DB VT-3 15 5 100% ONE 33 IIEADER B CRD13B-4"DB VT-4 5 100% WO _ 67 CRD14B-6"DB 5 100% TilREE 100 CRD15B-4"DB ISI-24B UE CRD SCRAM llEADER SUPPORTS CRD16A-2"DB VT-3 18 4 100% ONE 33 Cd DISCl!ARGES A & B CRD16B-2"DB VT-4 7 100% WO 67 gh ISI-24 C&D 7 100% TilREE 100 a
w CRD SCRAM llEADER SUPPORTS CRD18-2"DB VT-3 1 1 100% ONE 100 DRAIN ISI-24C VT-4 NONE WO 100 NONE TilREE 100 FOHM 9 7 457 8
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i MONTICLbc NUCLEAR GENERATING PLANT TABLE IL1 TEN YEAR INTERVAL- EXAMINATION
SUMMARY
PAGE _L__ OF ? l IIIM COMPONENT OR $YSTEM IDENilflCATION DESCRIPilON NDE TOTAL EXAMINATION INSPECTIOtJ RUNNINC pgyAgg$ NO. METHOD liEMS AMOUNT & EXTENT PERIOD % EXAMINATION CATECORY B-N-1, INTERIOR OF REACTOR VESSEL, B-N-2, INTEGRALLY WELDED CORE SUPPORT STRUCTURES AND INTERIOR ATTACllMENTS TO REACTOR VESSELS; B-N-3, RE!!OVABLE CORE SUPPORT . STRUCTURES REACTOR VESSEL il- 13.10 VESSEL INTERIOR SPACE ABOVE AND BELOW VT-3 - VISUALLY ONE 100 8' Tile REACTOR CORE TIIAT ACCESSIBLE AREAS IMO 100 IS MADE ACCESSIBLE FOR TilREE 100 EXAMIt3ATION BY Tile REMOVAL OF COMPONENTS DURING NORMAL REFUELING OUTAGES. FEEDWATER SPARCERS VT-3 - 100% OF Tile ACCEt -
- 100 *100% ACCESSIBLE SIBLE FEEDWATER OF ALL 4 N0ZZLES SPARGER SYSTEM AT INTERVALS NOT AND N0ZZLE INNER TO EXCEED EVERY RADIUS AREA OTilER REFUELING OUTAGE (NRC LETTEI Rg TO MR. MAYER, g$ DATED 8-27-81)
Dl1 "8 W F ORM 3 7-4 57 9
MONTICELLO NUCLEAR GENERAllNG PLANT ' TABLE __lL1
! f TEN YEAR INTERVAL- EXAMINATION
SUMMARY
PAGE 2 OF 2 IIEM COMPONENT OR SYSTEM IDENitfICATION DESCRIPilON NDE TOTAL EXAMINATION INSPECTIONRUNNING REMARKS NO. METHOD ITEMS AMOUNT & EXIENT PERIOD % B13.10 CONT'D CORE SPRAY SPARGERS VT-3 - 100% OF Tile ACCES: -
- 100 *100% ACCESSIBLE IBLE CORE SPRAY OF ALL CORE SPRAY SPARGER SYSTEM SPARCER AND PIPIN ;
AT EACll REFUELINC OUTAGE (IE BULLE1 lN 80-13) B13.20 INTERIOR ATTACilMENTS & ALL ATTACllMENTS AND VT-1 - VISUALLY ONE 100 B13.30 CORE SUPPORT STRUCTURES CORE SUPPORT STRUCTURES ACCESSIBI,E WELDS 114 0 100 AND SURFACES TilREE 100 7 N> REACTOR VESSEL (PWR) 313.30 CORE SUPPORT STRUCTURE N/A - - - - - R E' G1 DE "8 v FORM 974579
O O O
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TABLE 14 1 Eb[ #Y " TEN MONTICELLO NUCLEAR YEAR INTERVAL - EXAMINATION GENERATING PLANT '
SUMMARY
PAGE I OF 1 IIEta COMPOtJEt4I OR SYSTEM IDENilFICAllON DESCRIPilOt1 NDE TOTAL EXAMINAllON INSPECTIOtJM4t#NC' REMARKS NO- METHOD ITEMS AMOUNT & fXIENT PERIOD % EXAMINATION CATECORY B-0, PRESSURE RETAINING 11 ELDS IN CONTROL ROD IIOUSINGS REACTOR VESSEL 314.10 IJELDS IN CRD ll0USING ll0USING FIGURE I S,VOL *121 1 100% ONE 4 *24 PERIPIIERAL WELDS 1 100% TWO 8 Il0USINGS 1 100% TIIREE 13 INCLUDES UPPER AND LOWER WELDS
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7 i I I g ro ;1 n
"8 w
F O st M 97 4571
O O - O _ MONilCELLO NUCLEAR GENERAllNG PLANT TABLE 2.10 TEN YEAR INTERVAL - EXAMINATION
SUMMARY
PAGE I OF 1 ITEM COMPONENIOR SYSTEM IDENilflCATION DESCRIPilON NDE TOTAL EXAMINATION INSPECTION RUNNING REMARKS NO. METHOD ITEMS AMOUNi& EXTENT .FIRIOD % EXAMINATION CATEGORY C-B, PRESSURE RETAINING N0ZZLE WELOS IN VESSELS C2.10 N0ZZLES IN VESSELS 1/2 in. NONE -- -- -- -- -- -- -- OR LESS IN NOMINAL TillCKNESS
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[ C2.20 N0Z7.LES IN VESSELS OVER e 1/2 in. IN NOMINAL TIIICK-NESS , RilR llEAT EXCIIANGERS E-200A N3 & N4 WELDS 768 *S,Vol. 2 1 100% ONE 25
- SUPPLEMENTED BY ISI-50 1 100% TWO 50 SURFACE EXAMINA-E-2003 N3 & N4 WELDS 7&8 l
*S , Vol. 2 1 100% TWO 75 TIONS 1 100% Tl!REE 100 (D
0;i AE "8 m FORM 3 7 457 9
o:- o o . . MONilCELLO NUCLEAR GENERATING PLANT ' TABLE 3.10
- TEN YEAR INTERVAL- EXAMINATION
SUMMARY
PAGE 1 OF 10 ITEM COMPONENT OR SYSTEM IDENT:FICATION DESCRiPilON f4DE TOTAL EXAMINATION iNSPECilOfJRUNr#NG REMARKS NO. METHOD 11 EMS AMOUNT & EXTENT .PER'OD % EXAMINATION CATECORY C-C AND C-E, SUPPORT MEMBERS C3.10 INTEGRALLY WELDED SUPPORT ATTACllMENTS RilR llEAT EXCIIANGERS (6) (3) (100%) (100) MULTIPLE VESSELS E-200A WELDED E-200A S 3 Jl 100% ONE 33 SUPPORTS ISI-50 1 100% TWO 67 l [ E-2008 E-200B S 3 *1 100% TilREE 100 , o C3.20 COMPONENT SUPPORTS RIIR llEAT EXCliANGERS E-200A SUPPORTS E-200A VT-3 3 2 100% ONE 33 ISI-50 1 100% TWO 50- l E-200B SUPPORTS E-200B VT-3 3 1 100% TWO 67 2 100% TIIREE 100 C3.30 IUPPORTS-MECllANICAL AND NONE -- -- -- -- -- -- -- lYDRAULIC UE sa "8 m DOHM 97-4579
1 lj , ) ]ll11 l g l l E L B EG A 3 i N) SC l 2 0 S TI 4NI 1 R K D - OL . A SNTI P O F M EOVTP N 0 O E DP( AA US N F 1 R LE0I E E 3, C R 6. A NR MR E I L I O3Xl i E 4
- CCEW R EE G BG L
N 00 0 0 0 0 0 0 AA TP IN% N 00 0 500 370 370 370 370 U - 11 - - 1 251 361 361 361 361 R N OD E E E E E E E lO i CI E E E E E E E ER EOR EOR EOR EOR EOR eor EOR OWiNWlT N N N NWl l PE OWiT N N l OWT l l SP N 4 T O i i OWiT owlT i O i T T 0 0 000 000 000 000 000 N 0 0 000 000 000 000 000 NE 1 1 111 111 111 OT 111 111 l lE X A N & I I E E EE MN U N N NN A O O OO X O N N NN EM A 1 1 11 2 222 222 222 222 LS
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- T- T TT TT TT VV VV VV VV VV M
Y R E E EEE N G G GGG D D D D A " " " M O l i P "0 13 6 13 20"2 1114 E
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o o o :- .. MONTICELLO NUCLEAR GENERATING PLANT ~ TABLE __ 3.10 - TEN YEAR INTERVAL - EXAMINATION
SUMMARY
PAGE 5 op 10 11EM NDE TOTAL EXAMit.ATION .NSPECTIOfJ rut #aNG pgygpg$ COMPONENT OR SYSTEM IDENilflCATION DESCRIPilON NO. METHOD ITEMS AMOUh'& EXTENT , PERIOD % C3.50 CONTINUED SUPPLY TO STEMI SUPPORTS PS11-6"ED VT-3 3 2 100% CNE 29 SEAL SYSTEM PS12-6"ED VT-4 1 2 100% 1WO 57 PS13-6"ED 2 3 100% TilREE 100 PS14-6"ED 1 ISI-30 7 SUPPORTS PS7-10"ED VT-3 9 3 100% ONE 27 PS7-8"ED VT-4 2 3 100% TWO 55
, ISI-30 11 5 100% T11REE 100 Oi # MAIN STEMt SUPPORTS PS30-18"EDb VT-3 NONE 3 ONE -
EQUALIZER llDR ISI-30A VT-4 2 100% 1MO 67 1 100% TilREE 100 IIPCI WATER SUPPORTS 1W3-12"ED VT-3 17 6 100% ONE 35 DISCilARGE ISI-31 VT-4 6 100% 1WO 71 5 100% Till2E 100 IIPCI WATER SUPPORTS 1W1-14"llE VT-3 4 NONE ONE - SUCTION ISI-31A VT-4 2 100% 1MO 50 2 100% TilREE 100 llPCI STEMI SUPPORTS PS18-8"ED VT-3 13 3 100% ONE 23 m, ISI-32 VT-4 5 100% IWO 62 3@ 5 100% TilREE 100 t' $7D IIPCI STEMI SUPPORTS RS2-16"!!E VT-3 6 2 100% ONE 33 DISCliARGE ISI-33 VT-4 4 100% IWO 100 l w NONE TilREE 100 WORM $ 1 ASIS
' l 0
1 g g F A O y g g p 7 3__ 7 EE G L BG N I 0 1 20 000 700 00 00 0
- - 10 5O0 850 0 0 00 000
- 00 000 0
AA TP N% N 361 51 1 61 1 2S1 371 1 1 1 1 1
- - 0 1
U R t OD E E E E E E E E E lO i E E E E E E E E E CI ER E O P. EOR EOR EOR EOR EOR EOR EOR EOR PE NWl i NWi l NWil NWi l NWi l NWi l NWi l NWi l NWi l SP OTT OTT OTT OTT OTT OTT OTT OTT OTT N i T 000 00 00 0 000 000 0 0 0 N 000 00 00 0 000 000 0 0 0 Nf 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 OT l X lE A & E E EE E E E E EE N IT N ,N NN N N N N NN MN O O OO O O O O OO A U N N NN N N N N NN X O EM 556 22 21 3 A 1 1 2 332 1 1 4 LS TAM 6 OT TI E 1 4 3 3 4 8 1 1 4 D EO 34 34 34 34 34 34 34 34 34 DH - - - - - - - - - - - - - - - - - - NTE TT TT TT TT TT TT TT TT TT M VV VV VV VV VV VV VV VV VV Y E E E R I I l E E E E B I A N I G G G D I
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- EA I I N l I CE E N
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T IT Y. E C N O U, I ' U D P S f D S o O EN M E U R R g MT O C N l l lR R i I iR iR iR lR T N O 9 C 7 5 4 7 0 B M.O 5 E . M T i N 3 R C O F
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MONTICELLO NUCLEAR GENERATING PLANT' TABLE __ 3.10 TEN YEAR INTERVAL - EXAMINATION
SUMMARY
PAGE _9 Op 10 ifEM COMPONENT OR SYSTEM IDENilFICATION DESCRIPilON NDE TOTAL EXAMINAllON INSPECTION RUNNING REMARKS NO. METHOD ITEMS AMOUNT & EXTENT PERIOD % C3.60
- SUPPORTS - MEQlANICAL * - - - - - - -
- INCLUDED UNDER AND llYDRAULIC C3.40 & C3.50 PUMPS C3.70
- INTEGRALLY WELDED
- INCLUDES Tile SUPPORT ATTAQlMENTS CORRESPONDING C3.80 (VT-3)
RilR PUMPS WELDED P-202A S 4 1 100% 1WO 50 EXAMINATIONS r SUPPORTS P-202B VT-3 1 100% TilREE 100 j, P-202C i 100% IWO 75
- P-202D 1 100% ONE 25 ISI-48 CORE SPRAY PUMPS WELDED 14-1A S 2 1 100% THREE 100 SUPPORTS 14-1B VT-3 1 100% ONE 50 ISI-49 I C3.80 COMPONENT SUPPORTS IIPCI TURBINE & PUMPS SUPPORTS TURBINE VT-3 11 3 100% ONE 27 DVS PUMP 3 100% 1WO 55 DVMX PUMP 5 100% TilREE 100 ISI-45 &
ISI-46 D$ Nr RCIC TURBINE & PUMP SUPPORTS TURBINE VT-3 4 1 100% ONE 25 N$ PUMP 1 100% 1MO 50 "o ISI-47 2 100% TilREE 100 l l FOHM 3 7-4S7 8
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TABLE 5.10 PgQ"&[ft MONilCELLO NUCLEAR GENERAllNG PLANT 2 op 8 4 ./ TEN YEAR INTERVAL - EXAMINATION
SUMMARY
PAGE EXAM,t4 Allot 4 AMO'Jtdi IIEM COMPOt4Et4T OR SYSTEM IDENilFICAi!Ott DESCihPTIOt4 t.1EI D MS % 40 YR 10 YR E
- '5.116 (40YR) REQUIRED %
.10YR RUNNING %
'5.12 (CONTINUED)
(10) (5) (1) (100) MULTIPLE STREMIS W14B-20"IIE CIRC WELDS ISI-40 S' 5 3 1 ONE 20 W14A-20"ilE 20" X .375" ISI-42 S 5 2 - - - (28) (7) (2) (100) MULTIPLE STREMIS W16-14"IIE CIRC WELDS ISI-40 S 7 2 1 WO 14 W18-14"llE 14" X .375" S 7 1 - - - W15-14"IIE ISI-42 S 7 2 - - - W17-18"IIE S 7 , 2 1 '111REE 29 7
$ RIIR DISCliARGE A&B (37) (19) (5) (100) MULTIPLE STREMIS W29-10"GE CIRC WELDS ISI-41 S 18 9 2 WO 11 W19-10"GE 10" X .365" ISI-43 S 19 10 1 WO 16 2 TilREE 26
, (19) (10) (3) (100) MULTIPLE STREMIS W29-14"GE CIRC WELDS ISI-41 S 7 4 1 ONE 10 W19-14"GE 14" X .375" ISI-43 S 12 6 2 WO 30 (67) (34) (9) (100) MULTIPLE STREAMS W30-14"GE CIRC WELDS ISI-41 S 38 19 2 ONE 6 14" X .375" 3 WO 15 W20- 14"C C ISI-43 S 29 15 2 WO 24 w, 2 TilREE 26 D0 R2; (8) (4) (1) (100) MULTIPLE STREMIS
$p W30-16"CE CIRC UELDS ISI-41 S 4 2 1 WO 50 TW20-16"GE 16" X .375" ISI-43 S 4 2 1 ONE 25 l (5) (1) (100) SINGLE STREM1 W22-14"GE CIRC WELDS ISI-43 S 5 5 1 ONE 20 14" X .375" FORM 11' 4579
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. MONilCELLO NUCLEAR GENERATING PLANT TABLE _ 5.10 -
PAGE 6 _ op 8 TEN YEAR INTERVAL. - EXAMINATION
SUMMARY
EXAMINAllON AMOUNT IIIM DESCR6 prion N TAL N EC IOrd REMARKS COMPONENI OR SYSTEM IDEHilflCAllON
.:5.216 (CONTINUED) (40YR) REQUIRED %
.:5.22 10YR RUNNING %
SUPPLY TO STEMI SEAL SYSTEl! (7) (2) (100) SINGLE STREMI PS7-8"ED CIRC WELDS ISI-30 S,VOL 7 7 2 ONE 29 8" X .593" (18) (5) (100) SINGLE STREMI PS7-10"ED CIRC WELDS ISI-30 S,VOL 18 18 3 WO 17 10" X .593" 2 TIIREE 28 7 ftAIN STEMI
$ EQUALIZER !!DR (21) (5) (100) SINGLE STREMI PS30-18"EDB CIRC WELDS ISI-30A 3,VOL 21 21 2 ONE 10 l 18" X .937" 1 WO 14 2 111REE 24 10" DRIPLEG '
CIRC WELDS ISI-30A I,VOL 2 2 - - - SINGLE STREM1 l 10" X .594" FEEDWATER A&B (8) (4) (1) (100) }!ULTIPLE STREMtS FW2 A-14"ED CIRC WELDS ISI-37 s,VOL 4 2 1 ONE 25 FW2B-14"ED 14" X .937" 4 2 - - - RilR DISCIIARGE A&B (6) (3) (1) (100) IIULTIPLE STREA!!S w, W30-16"DB CIRC WELDS ISI-41 S,VOL 3 1 - - - 3@ W20-16"DB 16" X .843" ISI-43 S,VOL 3 2 1 WO 33 %0 mp (' 75 CATECORY C-G) D llPCI WATER DISCilARGE CIRC WELDS (47) (24) (6) (51) SINGLE STREMt
" W3-12" ED 12" X .687" ISI-31 S,VOL 7 3 1 ONE 4 12" X .843" i,VOL 38 20 2 ONE 12 3 WO 25 8" X .594" 3,VOL 2 1 1 TilREE 29 FORM 974579 .
) SECTION 2 PRESSURE TESTING PROGRAM ' ~/
ASME Section XI Pressure Testing Proeram ASME Code Edition and Addenda: I?77 Edition through and including Summer 1978 Addenda Program Period: June 30, 1981 through June 29, 1991 APPLICABLE ASME TEST TEST CODE CIASS TYPE FREQUENCY REQUEST FOR RELIEF 1 Leakage Refueling 30, 46 (Quality Group A) Hydrostatic 10 years 30, 46, 48 2 Functional 31h years 30, 31, 46 (Quality Group B) Hydrostatic 10 years 30, 31, 46 Inservice 3 LG years 30, 46 3 Functional 3 LG years 30, 46 (Quality Group C) Hydrostatic 10 years 30, 46, 49 Except as noted in the Requests for Relief, pressure tests will conform to IWA-5000, IWB-5000, IWC-5000, and IWD-5000. ASME Code Class boundaries are shown on the figures in Section 6. These figures do not include small instrument, leak test, vent, and drain lines. O l 21 Revision 3 5/12/82 l
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FSAR Valve Valve Applicable ASME Valve Test Request System thsnber No. Description _ Code Class Category _ Frequency Test For Relief C csIQ Exercise R1 Ri 91-1 27B Ri Inlet Check Valve 2 C CSIQ Exercise JJ R1 91-2 27A Rf Inlet Check Valve 2 A, C RR RR ^ 8, 50 IM R194 -1 96B Outboard Isolation 1 A, C RR RR 8, 50 FW IM 94-2 96A Outboard Isolation 1
~
8, 50 Ri FW 97-1 28B Inboard Isolation 1 A, C RR RR A, C RR 8, 50 R1 FW 97-2 28A Inboard Isolation 1 RR Recirc CV-2790 39 Rx Water Sample Isolatic a 2 A Q Full Stroke-Tii te 10, 28, 50 Recirc CV-2791 40 Rx Water Sample Isolati(-a 2 A Q Full Stroke-Tii :e 10, 28, 50 Recirc FD-2-43! 43A Recirc Suction 1 B CSIQ Full Stroke-Tii ;e 28 Recirc FO- 2-4 31 43B Recirc Suction 1 B CSIQ Full Stroke-Tire 28 Recirc FO-2-53/ 53A Recirc Discharge 1 B CSIQ Full Stroke-Tii .e 28 Recirc FD-2-531 53B Recirc. Discharge 1 B CSIQ Full Stroke-Tii e 23 vi:n ?@ Recirc FD-2-54/ 54A Recirc Disch. Bypass 1 B Q Full Stroke-Tii ie 23 $ Recirc Disch. Bypass Full Stroke-Tir ,e 28 5o Recirc FD- 2 ,541 54B 1 B Q u liccirc FO-2-65; 65B Recirc Loop Crosstie 1 B CSIQ Full Strcke-Tii ;e 28 Recirc 1D-2-651 65A Recirc 1.oop Crosstie 1 B CSIQ Full Stroke-Tii te 28
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FSAR Valve Valve Applicable ASME Valve Test Request System tinber 11o . Description Code Class Categog Frequency Test For Relief IU R RIR-21 29 Rx 11ead C1g Check 1 C CSIQ Exercise RIH 1 RIR-8-1 19A RilR Min Flow Check 2 C llR IUt 7 RIR F0-1988 FD-15A Shutdown C1g Suction 2 B CSIQ Full Stroke-Tinia 28 RIDI tD-1989 FD-15B Shutdown C1g Suction 2 B CS1Q Full Stroke-Tinu 28 Full Stroke-Tima 28, 50 { RlR FD-2006 FD-39A Disch to Torus 2 A - Q RIR FD-2007 FD-39B Disch to Torus 2 A Q Full Stroke-Tima 28, 50 RIR FD-2008 PD-34A Torus Clg Inlet 2 A Q Full Stroke-Tim: 28, 50 RIR hD-2009 FD-34B Tonts C1g Inlet 2 A Q Full Stroke-Tima 28, So IU R FD-2010 FO-38A Torus Spray 2 A Q Full Stroke-Tim 28, 50 Torus Spray 2 A Full Stroke-Tima 28, 50 IU Dt , bD
-2011 FD-38B Q RIR FD-2012 FD-27A LPCI Injection 2 B Q Full Stroke-Tima 28 e IU R 10-2013 LD-27B LPCI Injection 2 B Q Full Stroke-Tim: 28 N a luut FD-2014 bD-25A LPCI Injection 1 A Q Full Stroke-Tim; 28 Full Stroke-Tim 3 w R]IR tD-2015 PD-25B 1.PCI Injection 1 A .Q 28
,o A A FSAR Valve Valve Applicable ASME Valve Test System Request Number No. Description -
Code Class Category Fregu_ency Test For Relief IIPCI h0-2068 hD-19 Pump Discharge Isol 2 B Q Full Stroke-Time 28 IIPCI A0-23-It AO-18 C1g Wtr Disch Check 2 C Q Exercise IPCI h0-2071 FO-21 Test return to CST 2 B Q Full Stroke-Tin- 28 IPCI FD-2067 h0-20 Coolant Ptrnp Disch. 2 B Q Full Stroke-Tin 28 IIPCI CV-2065 41 Min Flow Bypass 2 Is Full Struke-Tin 28 Q IIPCI IPCI-42 62 Min Flow Bypass Check 2 C RR RR 7 w IIPCI RV-2064 34 Relief Valve 2 C IhV-3510 Setpoint IIPCI IPCI- 32 32 CST Suction Check 2 C Q Exercise IIPCI h0-2063 FO-17 CST Suction 2 B Q Full Stroke-Tit e 28 IIPCI h0-2062 h0-57' Torus Suction 2 B Q Full Stroke-Tire 28 IIPCI IPCI-31 61 Tonis Suction Check 2 C CSIQ Exercise IPCI h0-2061 h0- 58 Tonis Suction 2 B Full Stroke-Tire 28 Q
!!PCI h0-2034 FO-15 Steam Supply Isolation 1 A Full Stroke-Tis c 28, 50 Q
IPCI FD-2035 FD-16 Steam Outboard Isolatior 1 A Full Stroke-Til e 28,50 Q U IPCI 50-2036 50-14 Turbine Steam Supply 2 B Full Stroke-Tit e 28 M Q M IIPCI 10-7 10 Turbine Stop Valve 2 B Q Full Stroke 10 "O w IIPCI 10-8 ID Turbine Control Valve 2 B Q Full Stroke-Ti: e 28 IIPCI IIPCI-60 None O * ' V cu B k
FSAR Valve Valve Applicable ASME Valve Test System Request Nu:nber . No. Description Code Class Category Frequency Test For Relief Cooling Water Exempt per IIPCI PCV-349.: PCV-50 Supply Coat. 2 B NR IWV-1200a Cooling Water ID'CI IIPCI-20 131 Return Check 2 C Q Exercise IIPCI ID'CI- 14 56 Ex. Line Drain Pot Check 2 A, C CSIQ Exercise 50 i f"CI IIPCI-15 45 Ex. Line Drain Pot Check 2 C RR RR 7 IIPCI IIPCI-9 65 Turbine Ex. Line Check 2 A, C Q Exercise 50 ID'CI IIICI-10 12 Ex. Line Stop Check 2 C Q Exercise { IIPCI IIPCI- 65 None Vac. Ekr Check 2 C CSIQ Exercise ID'CI IDCI-71 None Vac. Ilkr Check 2 C CSlQ Exercise I D'CI PSD-203f; None Ex. Line Rupture Disc 2 D NR RCIC ID-2096 70-2096 Cooling flater to Cond. 2 B Q Full Stroke-Time. 28 RCIC RV-2097 RV-2097 Relief Valve 3 C IhV-351( Setpoint RCIC RCIC-14 None Condenser Cond Pump Disc 2 C Exercise i Q v' :o DQ RCIC RCIC-17 None Vac Pump Disch Check 2 C RR RR 7 Z7
$g RCIC RCIC-9 None Turbine Exhaust Check 2 A,C Q Exercise ,
50 a w RCIC RCIC-10 None Steam Exh Stop Check 2 C Q Exercise RCIC RCIC-57 None Vac Brkr Check 2 C CSIQ Exercise RCIC RCIC-59 None Vac Brkr Check 2 C CSIQ Exercise RCIC PSD-2080 PSD-2080 Rupture Disc 2 D PR
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wJ q FSAR Valve Valve Applicable ASME Valve Test Request System ihnber tb. Description Code Class Category _ Frequency Test For Relief RCIC ID-2075 60-2075 Steam Supply isolation 1 A Q Full Stroke-Tim 28, 50 RCIC 10-2076 10-2076 Steam Supply Isolation 1 A Q Full Stroke-Tin 28, 50 RCIC FD-2078 10-2078 Steam Supply to Turbine 2 B Q Full Stroke-Tim 28 TEIC RCIC-7 tbne Throttle Trip Valve 2 B Q Full Stroke 10 RCIC Governing NR xemPC Per RCIC 10 tbne 2 B IWV-1200n PCV-2092 PCV-2092 Conder.ser Press Cont 2 - B NR ***EE P"# RCIC- ItJV 1 ?nfb y RCIC RCIC-16 lbne i Vac Pump Disch Check 2 A, C csIQ Exercise 50 h RCIC 50-2100 FD-2100 Inboard Torus Suction 2 B Q Full Stroke-Timt 28 RCIC RCIC-31 tJone Check Valve to Torus 2 C csIQ Exercise ICIC FO-2101 FD-2101 Outboard Torus Suction 2 B Q Full Stroke-Tin 28 RCIC RCIC-41 tbne Check Valve to CST 2 C Q F_xercise RCIC FO-2102 }D-2102 CST Suction 2 B Q Full Stroke-Tin 28 RCIC RV-2103 RV-2103 2 C- thV-351( Setpoint Q Suction Line Relief y itCIC CV-2104 CV-2104 blin Flow Bypass 2 B Q Full Stroke-Tim 28 RR RrIC RCIC-37 None !!in Flow Dypass Check 2 C RR RR 7 lSE - D RCIC ?D-2106 50-2106 Pump Discharge 2 B Q Full Sticke-Tia 23 w RCIC iD-2107 FD-2107 Pump Discharge 2 8, Q Full Stroke-Tim 23 RCIC A0-13-22 A0-13-22 Pump Disch Check 2 C CSIQ Exercise
O O O . FSAR Valve Valve Applicable AShfE Valve Test Request System Number No. Description Code Class Category Frequency Test For Relief CRD CV-3-32A CV-32A Scram Disch Voltne Vent 1 B Q Full Stroke-Tim: 28 CV-3-32B Scram Disch Volume Vent CRD CV-32B 1 B Q Full Stroke-Tim 28 CRD CV-3-33 CV-33 Scram Disch Volume Drain 1 B Q Full Stroke-Tim 28 scram Ulsch voltne CRD RV-3-34 34 Relief Valve 2 C IWV-3510 Setpoint CRD CRD-114 114 Scram Riser Check 2 C RR RR 9 Acctnulator Charging CRD CRD-115 115 Water Check 2 C . CSIQ Exercise o CRD CRD-138 138 Cooling Water Check 2 C RR RR 52 CRD CV-126 CV-126 Inlet Scram Valve 1 B RR RR 9 CRD CV-127 CV-127 Outlet Scram Valve 2 B RR RR 9
%'E' RIE SW CV-1728 CV-1728 RIE SW Control Valve 3 3 B Q Full Stroke-Tim: 28 C1 2E IUIR SW CV-1729 CV-1729 RIR SW Control Valve 3 B Q Full Stroke-Tim 28 "8 RIR-SW RIR-SW RIR SW Pump u RIR SW 1-1 1-1 Disch Check 3 C Q Exercise IUIR-SW RIR-SW RilR SW Pump RilR SW 1-2 1-2 Disch Check 3 C Q Exercise
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FSAR Valve Valve Applicable ASE Valve Test Request - System Ntrber No. Description Code Class Category Frequency Test For Relief Primary Containm A0-2896 None Torus Vent Isolation ? A O Pull Rrrnko-Tir o 28. 50 Primary Containm CV-2384 None Torus Vent Isolation 7 A n Pnii s t rnt.n-Tie ., 29, Sn Primary Containm CV-2385 None Drywell Vent Isolation 2 A 0 Pull Stroke-Tin e 28 50 Primary Containm CV-3267 None Torus N9 Makeup Iso 2 A Q Pull Stroke-Tio e 28, 50 Primary Containm CV-3268 None Drywell N? Makeup Iso 2 A 0 Pull Stroke-Tio e 28. 50 Primary Containm CV-3269 None Cont N9 Makeup Iso 2 A O Pull s t rnk o-T i r > 9R sn Primary y Concainm SV-3307 None Drywell 02 Analy Iso 2 A 0 Pull St roke-Tin e 28, 50
- t' rima ry Containm 3V-3308 None Drywell 02 Analy Iso 2 A Q Pull Stroke-Tin e 28, 50 l'r lma ry Containm CV-3311 None Drywell O? Analy Iso 2 A O Pu l l Rrrnko-Tir o ?R_ 50 Primary containm CV-3312 None Drywell 09 Analy Iso 2 A O Pull gernko Tir o 9R, sn Primary lontainm '.V-3 313 None Drywell 09 Analy Iso 2 A O Pu l l S t ro k o-T i r o ?R- 50 Primary
'on ta i nm ::V-3314 None Drywell 09 Analv Iso 2 A O Pull Rrrnko-Tir o ?R 50 Primary Containm ::V-7436 None M2 Pumpback Isolation 2 A IWV-3416 fxercise 50 Primary u :a containm ::V-7437 None N2 Pnmnhack Isointion 7 A IWV-3416 Exercise 50 D@ Prima ry Q Pull Stroke-Tio e 28 50 M7 Containm ::V-744 0 Nono Torus to Drywell N,~ Iso 7 A
$oD Prima See t'ont to
-:xe rci se 50 Conta[Em )WV-8-1 None Torus Vac Bkr 2 A. C O
" Primary Sec Cont to .
Containm DWV-8-2 None Torus Vac Bkr 2 A, C 0 Exercise 50
(3 O O . V U k.) , FSAR Valve Valve Applicable ASME Valve Test Request - System Number No. Description Code Class Category Frequency Test For Relief Primary Containm SV-4001A None CMI System Iso 2 A Q Full Stroke-Tiire 28, 50 primary Containm SV-4001B None CMI System Iso 2 A O Full Stroke-Tii ie 28, 50 Primary containm SV-4002A None CAM System Iso 2 A Q Full Stroke-Tii ie 28, 50 Primary Containm SV-4002B None CAM System Iso 2 A Q Full Stroke-Titie 28, 50 Primary . Containm SV-4003A None CAFI System Iso 2 A Q Full Stroke-Tii ie 28, 50 Primary Containm SV-4003B None CAM System Iso 2 A O Full Rrrnko-Tir :0 ?R 90 Primary Containm SV-4004A None CAM System Iso 2 A Q Full Stroke-Tii ie 28, 50 y Primary g Containm SV-4004B None CAM System Iso 2 . A Q Full Stroke-Titie 28, 50 Primary Containm SV-4005A None CAM System Iso 2 A 0 Ful1 Stroke-Til.e 28, 50 Primary Contains SV-4005B None CA!! System Iso 2 A Q Full Stroke-Tii te 28, 50 Primary Containm SV-4020A None CAPI System Iso 2 A O Full Stroke-Tii ie 28, 50 Primary Containm SV-4020B None' CAM System Iso 2 A Q Full Stroke-Ti: ie 28, 50 l UE C;i sii "8 m
(A V) (r w O) (w l FSAR . Valve Valve Applicaile ASME Valve Test Request System Number No. Description Code Class Category Frequency Test For Relief RX INST. X-52B None Excess Flow Check Valve 1 A, C RR RR 39 RX INST. X-52C None Excess Flow Gieck Valve 1 A, C RR RR 39 RX INST. X-52D None Excess Flow Gieck Valve 1 A, C _RR RR 39 RX INST. X-52E None Excess Flow Check Valve 1 A, C RR RR 39 RX INST. X-52F None Excess Flow Gieck Valve 1 A, C RR RR 39 RX INST. X-28F None Excess Flow Oteck Valve 2 A, C RR RR 40 Cond Serv y System DM-58 None Drywel1 Demin Wtr Tso 2 .A IWV-3416 Exercise 50 RBCCW MO-1426 MO-1426 Drywell RBCCW Isolation 2 A CSIQ Full Stroke-Tii ie 28, 50 RBCCW RBCC-15 None Drywell RBCCW Isolation 2 A. C RR RR 6, 50 RWCU' M0-2397 MO-2397 Piimn Sinction Isolation I A 9 Full S t roke-Titie 28, 50 RWCU MO-2398 MO-2398' p,,m n q,,cennn Tcnineinn 1 Q Pull Stroke-Tii ,e A 28 50 Liquid Radwaste A0-25411 None Drywell Floor Drn Smp Iso 2 A Pul l St roke-Tli ie 28, 50 Q Liquid Radwaste A0-25411! None Drywell Floor Drn Smp Iso 2 A Q Pull Stroke-Ti ae 28. 50 Liquid Radwaste A0-2561A None
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Drywell Equ'ip Sump Iso 2 A O Pull Stroke-Ti ng 28 50 Liquid Radwaste A0-25611! None Drvwell Eaulo Sump Iso 2 A Q ,,, , 3 3 y , ,m t n T i > ,n 28. 50 RE Fuel Poo:
- g$ Cl g & C1, PC-20-1 None Fuel Storage Pool Check 3 C RR RR Nm 7 Fuel Poo:
$f Cle & C1 p Comp PC-20-2 None Fuel Storage Pool Check 3 C RR RR 7 Air CV-1478 CV-1478 Drywell Comp Air Iso 2 A CSIQ l'ull Stroke-Tiiie 28, 50 Comp Air CV-7956 Nono Torus Inst Air Tso 2 A O 'ull Stroke-Tit .e 28. 50 Comp Air AS-39 None Service Air Iso 2 A IWV-3416 Exercise 50
SECTION 4 REQUESTS FOR RELIEF FROM ASFE CODE SECTION XI O v REQUIREMENTS DETERMIIED TO BE IMPRACTICiL This Section contains Requests for Relief from those ASFE Code Section XI requirements which are impractical to implement on the Monticello Nuclear Generating Plant. Requests for Relief are numbered consecutively. Requests submitted in earlier ASFE Code Section XI Inservice Inspection and Testing Program descriptions have, where possible, been carried over to this program with their original identification numbers. ASME Code changes or NRC review may result in the deletion of a particular Request for Relief. The following Monticello Requests have been deleted: 4 29
. 11 32 12 33 14 ' 34 11 35 19 1 36 20 37 21 38
, 22 43 25 Os The following Requests for Relief are.new or substantially revised from those contained in the ASFE Code Section XI Inservice Inspection and Testing Program used for the first ten year interval:
7 24 9 41 15 42 16 44 18 45 19 46 23 47 48 49 50 51 52 O - Revision 3 5/12/82
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- 7. RFQJEST FOR RELIEF o o.- ..
Applicable A9fE Valve Component Function Code Class Category SW-101 Prevent flow of emergency service water 3 C SW-102 into the normal service water system 3 C when the emergency service water system SW-103 is operating. 3 C SW-104 3 C ESW-4-1 Prevent reversal of flow into redundant 3 C ESW-4-2 emergency service water line. 3 C RilR 8-1 Prevent reversal of flow into RilR 2 c RilR 8-2 Pump Discharge Line. 2 C I IIPCI-42 Prevent reversal of flow from 2 c gpgy_35 Torus into IIPCI System. . 2 C RCIC-17 Prevent Reversal of Flow from the 2 C
' RCIC-37 Torus Into the RCIC System.
2 C SW-21-1 Prevent Reversal of Normal Cooling 3 C SW-21-2 Flow Into the Service Water System. ' 3 C SW-16 Prevent Reversal of Flow From 3 p' Emergency Service Water System Into Service Water System. 3 SW-18 PC-20-1 Prevent siphoning of Water From 3 C w, Fuel Storage Pool Into Fuel Pool D@ .PC-20-2 Cleanup System. 3 C3 Y$ J Code Requirement lS { These valves will not be tested as required by IhV-3520. Basis There is no means available to verify that the disc travels promptly to the seat on cessation or reversal of flow for normally open valves or that the disc moves promptly away from the seat when the closing differential is removed and flow thruugh the valve is initiated for normally closed valves.
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- 7. RFfMEST RR RELIEF (Cont'd.)
Alternate Testing The systems in which these valves are located will be functionally tested on a periodic basis to demonstrate proper operation. Schedule For Inplementation 4 NA i e . 4 u :o
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- 9. RffMEST IOR REl.IEF o o.- ,,
Applicable ASE Valve C mponent Function Code Class Category CRD-114 Prevent scram discharge flow from 2 C flowing back into the CRD during a scram. CV-126 Provide scram accumulator pressure 1 B to the botto.m of the control rod drive piston during a scraa. CV-127 Exhaust scram discharge water from 2 B the top of the control rod drive piston during a scram. Code Requirement
- , These valves will not be tested as required by IW-3410 and IW-3520.
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Basis The above listed valves are located on each of the 121 hydraulic control units. 'Ihere is no practical method of testing these valves in accordance with Section XI requirements. There is no instmmentation installed to verify proper seating of the check valves and the control valves operate too rapidly to measure stroke time. Technical Specifications require all control rods to be scram tested once per operating cycle. These valves are all exercised one full cycle during a scram. Proper operation of these valves and the safety function of the control rod drive system are verified by the scram testing. 1 Alternate Testing See lkisis Schedule For Implmentation
- v. :n 3% February 28, 1978 2T -
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- 16. REQUEST FOR RELIEF COMPONENT or ITEM CODE PROGRAM CODE EXAM CLASS TABLE ITEM CATEGORY REACTOR VESSEL Circumferential Welds I 1.1 Bl.11 B-A VCBA-2, VCBB-3 Longitudinal Welds I 1.1 Bl.12 B-A VLBA-1, VLBA-2 CODE REQUIREMENT Perform a volumetric # damination of one circumferential and one 1ongitudinal beltline region weld.
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BASIS The examination of the circumferential and longitudinal weld will not be performed. The Monticello RPV was constructed with a 2' - 3 h" thick biological shield wall surrounding it, with the exception of the top (8) eight feet. Between this wall and the reactor vessel shell is a space of approximately 1 foot that houses the 'thennal insulation, mirror insulation. The only access areas to the reactor vessel are: 1. at the top (8) eight feet above the biological shield wall;
- 2. through opening in the wall at each nozzle location and two inspection ports below the skirt weld, and;
- 3. from the vessel inside diameter.
The area above the biological shield wall and at the nozzle openings is further obstructed by non-recovable insulation. A good portion of the vessel insulation was not designed to be removed and therefore it was vi x installed prior to the installation of the piping, electrical conduits, duct work, etc.
~a t;$. A very thorough review was performed, using drawings, sketches, previous examination reports, to try and Es 0 locate weld areas that possibly could be inspected. It was concluded that some of the welds are close "8 enough to nozzle openings for performing the examinations. Each of the welds that were examined were ,
w sketched to show the examination amount, extent and location.
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- 16. REQUEST FOR RELIEF (continued)
The examination areas and amounts shown in Table 1.1 were scheduled from the drawings, sketches and examination report reviews. As additional areas of welds, other than beltline region, are examined the specific amount and extent given in Table 1.1 will be changed to reflect the actual measurements. ALTERNATIVE Due to the inaccessibility of the circumferential and longitudinal beltline region welds (VCBA-2, VCBB-3, VLBA-1 and VLBA-2), all of the accessible areas on the remaining circumferential and longi-tudinal welds will be examined. SCHEDULED FOR IMPLEMEllTATI0tl June 30,1981
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- 51. REQUEST ;;. RELIEF COMPONENT or ITEM CODE PROGRAM CODE EXAM CLASS TABLE ITEM CATEGORY REACTOR VESSEL Stabilizer Brackets I 8.1 88.10 B - 11 CODE REQUIREMENT Perform a volumetric or surface examination of 100% of the length of weld.
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- The examination of the stabilizer brackets will not be performed. The area around the stabilizer brackets is obstructed by non-removable insulation, ventilation and electrical duct work between the dry well wall and reactor vessel.
These brackets are actually not part of the vessel supporting system, but are designed to stabilize the reactor vessel against. jet force loading (LOCA's) and/or seismic loads. The stabilizer brackets are designed to allow thermal movement without restraint, and therefore there are no loadings at the vessel as the result of operations. ALTERNATIVE Due to the inaccessibility and design criteria of the stabilizer brackets, inspection of these brackets will be conducted if the brackets experience design inads. 2: @ (({ NO SCllEDULED FOR IMPLEMENTATION [ June 30, 1981
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- 52. REQUEST FOR RELIEF Applicable Valve l Component Function ASME Code Class Category
. Prevent scram accumulator pressure CRD-138 from discharging into CRD cooling 2 C water circuit during a scram Code Requirement These valves will not be tested within the f requency requirements of IW - 3520.
Basis v~ The above listed valve is located on each of the 121 hydraulic control units. These valves can be tested to verify proper seating only during control rod drive dif ferential pressure testing (CRD D/P). The CRD D/P testing is done only during refueling outages due to the extensive instrumentation required to be set I up and due to the number of control rod drives that have to be tested. Alternate Testing Testing will be completed during refueling outages only. Schedule For Implementation y September 4, 1982 (Refueling Outage) l5E a La
V- 1 To:g Diractor of Nuclear Reactor R gulation Date: May 12. 1982 r~Q U S Nucicar Regulatory Commission Washington, DC 20555 Licensing Fee Determination Fee Type: Facility License Amendment Required Approval y Materials License Application Materials License Renewal Other (Description ) Licensee: Northern States Power Company Plant: Monticello Nuclear Generating Plant Docket No. 50 263 License No. DPR- 22 Materials License No. 50- DPR-Date and subject of Licensing Request: Information Required For NRC Review of Inservice Inspection and Testing Program and Requests for Relief from ASME Code Section XI Requirements. License Amendment or Approval Class: III Fee: $4.000.00 Class: Fee: Materials License Category: Fee: Total Fee Enclosed: $4,000.00 Basis f or determination of f ee class: This is a revision of the Monticello Nuclear Generating Plant ASME Code Section XI Inservice Inspection and Testing Plant. It is being submitted in accordance with 10 CFR Part 50, Section
- 50. 55a (g)(5) . Commission review of Code requirements we have found to be impractical is required.
This is a required approval involving a single safety issue. Standards of acceptability have been clearly identified by NRC Staff positions. I
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- Prepared by: Nuclear Support Services Department t Northern States Power Company 414 Nicollet Mall - Sth Floor
* , Minneapolis, 501 55401 (612) 330-6763 cc: NSS File l}}