ML20010B259

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To Inservice Insp & Testing Program
ML20010B259
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 07/31/1981
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML20010B256 List:
References
PROC-810731, NUDOCS 8108140277
Download: ML20010B259 (109)


Text

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i July 31, 1981 Revision No. 6 to Prairie Island ASME Code Section XI Inservice Inspection and Testing Program and Information Required for NRC Review of Requests for Relief from ASME Code Section XI Requirements, dated February 1, 1978 Remove the Following Insert the following Pages Revision No. 6 Pages Title Page Title Page iii & iv iii & iv 1.1.1-2 1.1.1-2 1.1.1-3 1.1.1-3 1.1.1-4 1.1.1-4 1.1.1-11 1.1.1-11 1.1.1-26 1.1.1-26 1.1.1-27 1.1.1-27 1.1.1-28 1.1.1-28 1.1.1-34 1.1.1-34 1.1.1-36 1.1.1-36 1.1.2-2 through 1.1.2-2 through 1.1.2-20 1.1.2-27 4

1.2-1 1.2-1 1.4-17 1.4-17 1.4-25 1.4-25 j

l 1.4-26 (deleted)

J 1.5-36 1.5-36 1.5-48 1.5-48

()

(deleted) 1.5-49 1.5-52 1.5-52 1.5-53 1.5-53 1.5-54 1.5-54 1.5-55 1.5-55 1.5-59 1.5-59 1.5-63 1.5-63 1.5-75 (new page) 1.5-76 (new page)

O B108140277 810731 8

PDR ADOCK 05000282 0

PDR I

e

. O Remove the Following Insert the Following Pages Revision No. 6 Pages 2.1.1-2.

2.1.1-2 2.1.1-3 2.1.1-3 2.1.1-5 2.1.1-5 2.1.1 2.1.1-8 2.1.1-9 2.1.1-9 2.1.1-11

.2.1.1-11 2.1.1-14 2.1.1-14 2.1.1-19 2.1.1-19 2.1.1-31 2.1.1-31 2.1.1-34 2.1.1-34 2.1.1-35 2.1.1-35 2.1.2-2 through 2.1.2-2 through 2.1.2-20 2.1.1-24 2.2 2.2-1 2.4-14 2,4-14 2.4-17 2.4-17 2.5-21 2.5-21 (deleted page) 2.5-22 2.5-28 2.5-28 2.5-33 2.5-33 (deleted page) 2.5-34 2.5-37 2.5-37 O

2.5-38 2.5-38 2.5-39 2.5-39 2.5-40 2.5-40 2.5-44 2.5-44 2.5-48 2.5-48 2.5-58 (new page) 2.5-59 (new page) 3-1 through 3-1 through 3-16' 3-8 Use the " Record of Revisions," pages iii and iv to verify your copy of the manual is complete 'and up-to-date following entry o' chis revision.

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i i

i NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEM GENERATING PLANT DOCKET NOS. 50-282 LICENSE NOS. DPR-42 i

50-306 DPR-60 AShc. CODE SECTION XI INSERVICE INSPECTION AND TESTING PROGRAM i

-AND l

INFORMATION REQUIRED FOR NRC REVIEW OF REQUESTS FOR RELIEF FROM ASME CODE SECTION XI REQUIREMENTS I

r i

i i

I t

SUBMITTED: February 1, 1978 REVISED: Revision 1 September 15, 1978 Revision 2 June 8, 1979

' Revision 3 September 19, 1979 Revision 4 April 17, 1980-Revision 5 September 3, 1980 Revision 6 l

July 31, 1981-

. ~.

~

MCORD OF REVISIONS Page No Revision No Page No Revision No 1.5-1 2

1.5-2 thru 1.5-5 1

lii 6

1.5-6 Original iv 6

I'S-7 I

1-1 4

1.5-7A 1

1.1.1-1 4

1.5-7B 2

1.1.1-2 thru 1.1.1-4 6

1.5-10 1

1.1.1-5 thru 1.1.1-6 Original 1

1.5-11 Original 1.1.1-7 1

1.5-12 1

1.1.1-8 thru 1.1.1-10 Original 1.5-12A 2

1.1.1-11 6

1.5-13 Original 1.1.1-12 thru 1.1.1-17 Original 1.5-14 Original 1.1.1-18 1

1.5-15 1

1.1.1-19 Original 1.5-15A 1

1.1.1-20 1

1.5-16 1

1.1.1-21 thru 1.1.1-25 Original 1.5-17 Crigtnal 1.1.1-26 thru 1.1.1-28 6

1.5-18 1

1.1.1-29 thru 1.1.1-33 Jriginal 1.5-18A 1

1.1.1-34 6

1.5-19 Original 1.1.1-35 Original 1.5-20 1

1.1.1-36 6

1.5-22 thru 1.5-23 Original-1.1.1-37 thru 1.1.1-39 Original 1.5-24 2

1.1.2-1 4

1.5-25 6

1.1.2-2 thru 1.1.2-27 6

1.5-27 thru 1.5-28 Origtnal 1.1.3-1 4

1.5-29 1

1.2-1 6

1.5-30 Original 1.3-1 4

1.5-31 thru 1.5-34 1

1.3-2 1

1.5-34A 1

1 4-1 4

1.5-35 Original

~

1.4-2 1

1.5-36 6

1.4-3 thru 1.4-4 7

1.5-37 thru 1.5-39 Origtr.a1 1.4-5 4

1.5-40 1

1.4-6 1

1.5-41 Ortgtnal l

1.4-7 thru 1.4-8 4

1.5-42 1

1.4-9 2

1.5-43 2

1.4-10 1

1.5-47 Original 1.4-11 thru 1.4-12 2

8 6

f 1.4-14 thru 1.4-15 2

9 1.5-51 Original 7

1.5-52 thru 1.5-55 6

1.4-18 4

thru 1.4-20 5-thru 1.5-58 Original 1.5-59 6

1.4-22 1

1.5-60 1

1 4-23 4

1.5-61 thru 1.5-62 Original 1$4-24thru1.4-34 1

1.5-63 6

1.5-64 thru 1.5-68 1

1.5-69 2

1.5-70 4

1.5-71 thru 1.5-72 1

1.5-73 2

O 1.5-74 4

V 1.5-75 inru 1.5-76 6

l 2.1 4

l 2.1.1-1 4

l 2.1.1-2 6

l Revision 6 l.

iii 7/31/81 l __ -., _.

\\.

RECORD OF REVISIONS

)

Page No Revision No Page No Revision No 2.5-10 thru 2.5-11 2

2.1.1-3 6

2.5-11A 2

2.1.1-4 1

2.5-12 1

2.1.1-5 6

2.5-13 Original 2.1.1-6 thru 2.1.1-7 Original 2.5-14 1

2.1.1-8 thru 2.1.1-9 6

2.5-15 thru 2.4-20 Original 2.1.1-10 Original 2.5-21 6

2.1.1-11 6

2.5-23 thru 2.5-24 Original 2.1.1-12 thru 2.1.1-13 Original-2.5-25 1

2.1.1-14 6

2.5-26 1

2.1.1-16 thru 2.1.1-18 Original 2.5-26A 1

2.1.1-19 6

2.5-27 Original 2.1.1-20 thru 2.1.1-25 Original 2.5-28 6

2.1.1-26 1

2.5-29 1

2.1.1-27 thru 2.1.1-30 Original 2.5-30 1

2.1.1-31 6

2.5-31 2

2.1.1-32 thru 2.1.1-33 Original 2.5-33 6

2.1.1-34 thru 2.1.1-35 6

2.5-34 1

2.1.1-38 3

2.5-35 1

2.1.1-39 thru 2.1.1-41 Original 2.5-36 Original 2.1.2-1 4

2.5-37 thru -1.5-40 6

2.1.2-2 thru 2.1.2-24 6

2.5-41 thru 2.5-43 Original 2.1.3-1 4

2.5-44 6

2.2-1 6

2.5-45 1

0 2.3.1 4

2.5-46'thru 2.5-47 Original 2.3.2 Original 2.5-48 6

2.4-1 4

2.5-49 thru 2.5-53 1

2.4-2 thru 2.4-4 2

2.5-54 4

2.4-5 4-2.5-55 thru 2.5-56 1

2.4-6 thru 2.4-7 1

2.5-57 4

2.4-8 thru 2.4-9 4

2.5-58 thru 2.3-59 6

2.4-10 thru 2.4-11 2

3-1 thru 3-8 6

2.4-12 thru 2.4-13 1

4-1 2

2.4-14 6

4-2 thru 4-4 Original 2.4-15 4

4-5 thru 4-6 2

2.4-16 1

4-7 thru 4-9 Original 2.4-17 6

4-10 thru 4-13 2

2.4-18 thru 2.4-28 1

4-14 thru 4-19 Original 2.5-1 2

4-20 thru 4-22 2

2.5-2 thru 2.5-4 1

4-23 Original 2.5-5 Original 4-24 2

2.5-6 1

4-25 thru 4-31 Original 2.5-6A 2

4-32 2

2.5-8 thru 2.5-9 Original 4-33 thru 4-39 Original 4-40 2

O iv Revision 6 7/31/31'

1 h

NORTHERN STATES POWER CO.

ORAIRIE ISLAND Lt!T 1 II TEN YEAR INffRVAL INSPECTICN

SUMMARY

I 5

M UOR ITDI:

REACTOR VE.sSEL Elw CCMOO."" OR SYSUN, IUTAL INSPEC-E Um OR NM.

CAn-AND DESCkIPTION OF NO.PER IDDTIFICATIN N NATIm Tim RDfARKS E

muy T1TN TO BF FXAMTNFD TTIN N AND N T N

E PERIOD j

Bl.1 B-A LONCIMDINAL AND CTRCtNFEREM-REQUIRES THE REMOVAL TIAL SHELL WELDS IN CORE OF CORE BARREL RECION LONGITUDINAL WELDS NONE 4

CIRCUMFERENTIAL WELDS 1

U.T.

WELD No. 3 21 FEET (MIN.)

THREE LOWER SHELL ASSEMBLY 50 RELIEF No. 55 (ISI-48)

TO INTERMEDIATE WELD Bl.2 B-B LONCITUDINAL AND CIRCUMFEREN-REQUIRES THE REMOVAL TL4L WELDS IN SHELL (OlHER OF CORE BARREL DIAN THOSE OF CATECORY B-A AND B-C) AND MERIDIONAL AND f

CIRCUMFERENTIAL SEAM WELDS f

IN BOITOM HEAD AND CLOSURE y

HEAD (OntER DIAN THOSE OF fo CATECORY B-C)

J LONGITUDINAL WELDS NONE MERIDIONAL WELDS NONE CIRCUMFERENTIAL WELDS 3

U.T.

WELD No.2 25 INQInS (MIN.)

DIREE UFFER SHELL ASSEMBLY 5

RELIEF No. 55 (ISI-48)

M LOWER SFLL ASSEM-BLY WELD No.4 25 INQIES (MIN.)

THREE l LOWER TRANSITION HEAD 5

(IS7-48)

TO SHELL WELD WEIb No. 5 25 INCHES (MIN.)

THREE b ITOM HEAD RING TO 5

(ISI-48)

LOWER TRANSITION HEAD WELD Bl.3 B-C VESSEL-M-FLANCE AND HFAD-M-l FIANr,E CIRCUMFERENTIAL WELDS kELIEF No. 55 VESSEL TO FIANCE 1

U.T.

WELD NO.1 CLOCKWISE,14 FT ONE VESSEL FIANGE 33 (ISI-48)

(MIN.)

3m CLOC10ilSE,12 FT.

IWO VESSEL FIANCE 62 M

(MIN.)

  • Q CLOCKWISE,16 FT.

DIREE VESSEL FIANGE 100 (MIN.)

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2 NORTHERN STATES POWER CO.

DRAIRIE !SLAND Lt!T 1 TM 1.1 TEN vE44 INTERVAL I N S.eE C T I ON SUMMAR, PAGE 2 OF s

M UOR IIIM:

REACTOR VESSEL EXAM.

C04'ONENT OR SYSTDf, 10TAL INSPrf'-

CATE.

AND DESCRIPTION OF NO.PER IDINTIFICATION EXAMINATI N IDCATION OR RNIM TION ITD.

mW TTDf10 BF FU MINFD TTBf

  1. 11NT AND EX11NT prRinn FSIIM MM h

HEAD TO Eu NCE 1

U.T.

WELD NO. 6 CLOCIGilSE. 14 ONE HEAD FIANCE 33 (ISI-49)

FEET (MIN.)

CLOCKWISE, 14 TWO HEAD FIANGE 66 FEET (MIN.)

CLOCKWISP, 14 THREE HEAD FIANGE 100 FEET (MIN.)

81.4 B-D PRIMARY NOZZLE-TO-VESSEL RELIEF NO. 55 WELDS AND N0ZZLE INSIDE

. MDIUSED INSPECTION OF INLET N0ZZLES AND SI p

REACTOR CORE C00!MT N0ZZLES RAJIRES L

N0ZZLES REPOVAL OF CORE p

BARREL OU17.ET N0ZZLES 2

U.T.

RCC-A-1(ISI-50:

1 WELD (1001)

ONE 1808 (29-RC-1A) 25 RCC-B-1(ISI-50:

1 WELD (1001)

TWO

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(29-ku-18) 50 I~

' N0ZZLES 2

U.T.

RCC-A-14(ISI-5( ) 1 WELD (1001)

THREE 120' (27.5-RC-3A) 75 RCC-B-14(ISI-5( ) 1 WELD (1001)

THREE 300 (27.5-RC-38) 100 SA's e.

4JECTION N0ZZLES 2

U.T.

LOOP A(ISI-30) 1 WELD (1001)

THREE (4.RC-14A) 50 RELIEF NO. 64

)

2600 LOOP B(ISI-30) 1 WELD (100%)

IHREE 800 (4.dC-14B) 100 Bl.S B-E VESSEL PENETRATIONS. INCLU-DING CONTROL ROD DRIVE AND INSTRUMENTATION PENETRATIONS CONTROL ROD PENETRATIONS 40 V

3 PENETRATIONS ONE TOP OF REACTOR 9

PLANT OPERATIONS (MIN.)

3 PENETRATIONS IWO VESSEL CLOSURE HEAD 15 (MIN.)

4 PENEIRATIONS THREE 25 (MIN.)

INSTRUMENTATION PENETRATIONS 36 V

3 PENETRATIONS ONE UPOER REACTOR VESSEL o

. 4 OPERATIONS h

(MIN.)

3 3 PENETRATIONS TV1 EOTTOM HEAD 17 cm w (MIN.)

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i NORTHERN STATES POWER CO.

TABLE 1.4 DRA!RIE ISLAND Ut!!T 1 I%GE 13 OF 19 TEN FEAR INTERVAL INSPECTION

SUMMARY

MUOR 111N: PIPING PRESSURE BOUNDARY EXAM O}!PONENT OR SYSlT)f, 10TAL INSPEC-OR ME-CAN AND DESCRIPTION OF M).PER IDENTIFICATION NNIN TION RDIARKS IU UN MM mW T1TN 10 PE FXAMTTI)

TTTM

  1. M AND N prRTon B4.9 B-K-1 (Continued)

I SEAL INJECTION 3

UT WZLDED SUPPORTS 1-SUPPORT 100%

THREE EL 695' (2-VC-21A)

LOOP A-2" (1.5-VC-21A)

ISI-11 SAFETY INJECTION - HICH HEAD 1

UT WEIDED SUPPORTS CUBICLE B (2-St-35B) 1 LOOP B-2"

{

151-24 LETDOWN LINE - CVCS 1

UT WELDED SUPPORTS EL 695' (2-RC-12)

LOOP B-2" ISI-26 t

SEAL INJECTION 3

UT WELDED SUPPORTS 1-SUPPORT 100%

THREE CUBICLE B (2-VC-21B) 26 1

M LOOP B-2" ISI-27 w

CUBICLE A (2-RC-8A) k RESIDUAL TEMPERATURE DETECTON 1

UT JEIDED SUFFORT TAKE OFF - COLD LEG LOOP A-2" ISI-7 B4.10 B-K-2 SUPPORT COMPONENTS (NON-WELDED)

REACTOR CORE C00! ANT 4

V SUPPORTS 1-SUPPORT 100%

ONE CUBICLE A -(31-RC-2A) 25 NOTE: 2 RESTRAINTS ADDED LOOP A-31"&27.51-SUPPORT 100%

THREE CUBICLE A (31-RC-2A) 50 1980 OUTAGE I

ISI-12 1-SUPPORT 1001 THREE SANDPLUG (27.5-RC-3A) 75 (12-RC-16A)

SUPPORTS ACCUMULATOR DISCHARGE NONE' IDOP A-12" I

ISI-2 4

RESIDUAL HEAT REMOVAL-TAKE OFF 16 V

SUPPORTS 4-SUPPORTS 100%

ONE EL 695',711 (8-RC-15A) 25 140P A-8" 6-SUPPORTS 100%

TWO EL 695' CUBICLE A 63 I

ISI-3 6-SUPPORIS 100%

111REE EL 695' (8-RH-1A) 100 (6-RC-138)

SAFETY INJECTION-HICH HEAD NONE SUPPORTS LOOP A-6" 1

P ISI-4

$h i

3$

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O NORTHERN STATES POWER CO.

TABE 1.4 DRA!RIE !SLAND Uf!IT 1 PAGE 14 0F 19 TEN YEAR INTERVAL INSPECTION

SUMMARY

MVOR I11N: PIPING PRESSURE BOUNDARY E14L 03tPOND.T OR SYSTD4, TUIAL INSPEC-II1 CATION OR RthNINI-CATE.

AND DESCRIPTION OF

!O.PER IDIhTIFICATION NETim TION g

SYSTEM NtNBER PERCDu ITIN YTTM 10 BF TNAMTNTD TTTN

  1. 1XNT AND EX11AT pntion mW B4.10 B-K-2 (Continued)

(NON-WEIDED)

SPRAT TO PRESSURIZER 11 V

SUPPORTS 4-SUPPORTS 100%

ONE EL 702', CUBICLE B 36 BRANCH A-3" (3-RC-5)

ISI-5 3-SUPPORTS 100%

WO CUBICLE A, 702' 64 (3-RC-5) 4-SUPPORTS 100%

THREE EL 702' (3-RC-5) 100 RESISTANCE TEMPERATURE DETECTOR-REWRN 2

V SUPPORTS 1-SUPPORT 100%

WO CUBICLE A (3-RC-6A) 50 LOOP A-3" 1-SUPPORT 100%

DIREE CUBICLE A (3-RC-6A) 100 ISI-6 RESISTANCE TEMPERAIURE 5

V SUPPORTS 1-SUPPORT 100%

ONE CUBICLE A (2-RC-8A) 20 DETECTOR-TAKE OPP LOOP A-2" 2-SUPPORTS 100%

WO CUBICLE A (2-RC-8A) 60 (COLD LEC)

ISI-7 2-SUPPORTS 100%

DIREE CUBICLE A (2-RC-8A) 100 P

RESISTANCE TEMPERATURE 4

V SUPPORTS 1-SUPPORT 100%

ONE CUBICLE A (2-RC-7A) 25 I

DETECTOR-TAKE OPP - LOOP A LOOP A-2" 1-SUPPORT 100%

WO CUBICLE A (2-RC-7A) 50 (HOT LEX:)

ISI-8 2-SUPPORTS 100%

DIRE 6 CUBICLE A (2-RC-7A) 100 SAFETY INJECTION - HIGH HEAD 1

V SUPPORTS 1-SUPPORT 100%

THREE j CUBICLE A (2-S1-35A) 100 LOOP A-2" ISI-9 DRAIN LINE CN CROSSOVER g

3 V

SUPPORTS 1-SUPPORT 100%

ONE EL 695' (2-RC-10A) 33 LOOP A-2" 1-SUPPORT 100%

WO EL 695' (2-RC-10A) 66 ISI-10 1-SUPPORT 100%

DIREE EL 695' (2-RC-11A) 100 SEAL INJECTION 19 V

SUPPORTS 6-SUPPORTS 100%

ONE EL 695' (2-vC-21A) 32 LOOP A-2" & 1%"

6-SUPPORTS 100%

WO CUBICLE A, EL 695' 63 ISI-11 7-SUPPORTS 100%

THREE EL 695', 711'(2-VC-21A) 100 REACTOR CORE COOIANT 4

V SUPPORTS 1-SUPPORT 100%

DC CUBICLE B (31-RC-28) 25 NOTE: 2 RESTRAINTS ADDED LOOP B-31"&27.5' 1-SUPPORT 100%

THREE CUBICLE B (31-RC-28) 50 1980 OUTAGE ISI-13 1-SUPPORT 100%

THREE SANDPLUG (27.5-RC-38) 75 2=3

=~8 a,

%. EM

O O

O NORTHERN STATES POWER CO.

TABLE 1.4 ORA!RIE ISLAND UNIT 1 PAGE 15 0F 19 i

TEN VEmp INTERVAL INSPECTION

SUMMARY

MMOR IlDl: PIPING PRESSURE BOUNDARY I

EXAM.

(D6' MENT OR JSTDf, 1UTAL INSPiJ-N IN N E

CATE.

AND DESCR!PTIm OF M).PER IDDTTIFICATION MINATIm TICE nuw1KS SYSIDI NtNBER PERCDT' 1101 MEllm-AMXNT AND EX1TXT mm m

yg mpyEWTM TM B4.10 8-K-2 (Continued)

ACCUMUIATOR DISmARCE 1

V SUPPORTS 1-SUPPORT 100%

ONE EL 695' (12-RC-168) 100 LOOP B-12" (12-St-278)

ISI-17 RESIDUAL HEAT REMOVAL-RETURN 4

V SUPPORTS 1-SUPPORT 100%

ONE EL 695' (10-51-26) 25 LOOP B-10" 1-SUPPORTS 100%

WO EL 695' (10-St-26) 50 ISI-18 2-SUPPORTS 100%

THREE EL 695' (10-S1-26) 100 RESIDUAL HEAT RDt0 VAL -

TAKE OFF 11 V

SUPPORTS 3-SUPPORTS 100%

ONE EL 695' (8-RH-15) 27 LOOP B - 8" 4-SUPPORTS 100%

WO EL 695', CUBICLE B 64 ISI - 19 4-SUPPORTS 100%

THREE EL 695' (8-RC-158) 100 (6-RC-13D)

SAFETY INJECTION-HIGH HEAD -

NONE SUPPORTS LOOP B-6" ISI-20 w

'w SPRAY TO PRESSURIZER 10 V

SUPPORTS 3-SUPPORTS 100%

ONE CUBICLE B (3-RC-5) 30 g

SRANCH B-3" 3-SUPPORTS 100%

WO CUBICLE B (3-RC-5) 60 l

ISI-5 4-SUPPORTS 100%

THREE CUBICLE B (3-RC-5) 100 RESISTANCE TEMPERATURE 2

V SUPPORTS 1-SUPPORT 100%

WO CUBICLE B (3-RC-6B) 50 l

DETECTOR - RETURN LOOP B-3" 1-SUPPORT 100%

THREE CUBICLE B (3-RC-65) 100 ISI-21 RESISTAMCf TEMPERATUkE 5

V SUPPORTS 1-SUPPORT 100%

ONE CUBICLE B

.(2-RC-88) 20 DETECTOR-T #F OFF LOOP B-2" 2-SUPPORTS 100%

WO CUBICLE B (2-RC-88) 50 (COLD LEC)

ISI-22 2-SUPPORTS 100%

THREE CUBICLE B (2-RC-85) 100 RESISTANCE TEMPERATURE 5

Y SUPPORTS 1-SUPPORT 100%

ONE CUBICLE B (2-RC-78) 20 DETECTOR-TAKE OFF LDOP B-2" 2-SUPPORTS 100%

WO CUBICLE B (2-RC-75) 60 (HOT LEC)

ISI-23 2-SUPPORTS 100%

THREE CUBICLE B (2-RC-78) 100 SAFETY INJECTION - HICE HEAD 2

V SUPPORTS 1-SUPPORT 100%

ONE CUBICLE B (2-51-355 )

50 LOOP B-2" 1-SUPPORT 100%

THRZE CUBICLE B (2-SI-358 )

100

[SI-24 DRAIN LINE ON CROSSOVER 1

V SUPPORTS 1-SUPPORT 100%

Wo CUBICLE B (2-RC-108) 100 y,

LOOP B-2" g

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TABLE 2.1.2 j

PRAIRIE ISLAND LNIT I PALI 1

0F 1

TDI YEAR I.NTRVAL INSPECTIm SLM4ARY MAJOR ITTM: PRESSURE VESSELS - ACCUMULATORS 4

EXAM GMm1NT OR SYS11N, ACO3-INSPECTIm 1

SUB CATE-AND DESCRIPTION OF NDE TUTAL IBLE 40 YR.

10 YR.

(40 YEAR)

PERIOD 77g ITM (DRY ITIN 10 BE EXAMINED WTIKI15 IIIMS e

EXAM EXAM j

(10 YR.)

i j

C1.1 C-A CIRCUMFERENTIAL BUTT WELDS

.i ACCUMULATOR No. 11 UT 4

4 2

1 CONTAINMENT ISI-86 (MULTIPLE STREAMS)

}

ACCUMULATOR No. 12 UT 4

4 2

CONTAINMENT ISI-86 i

j No. 11 WELD 2 UT 20%

20%

SHELL TO HEAD EXAMINATION OF j

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20 %

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1 1

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12-SI-29A ISI-96 i

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C1.3 C-C INTECRALLY WELDED SUPPORTS ACCUMULATOR No. 11 S

1 1

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1 1

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CONTAINMENT, MANWAY BOLTS ISI-86 (MULTIPLE STREAMS)

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I IMUM ON 10% OF j

THE BOLTS ON i

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NOR11ERN STATES POWER (I).

TABIE 2.1.3 PRAIRIE ISIAND LNIT I l

PAGE 1

OF 1

HN YEAR INIERVAL INSPECTION SLMIARY 2

MAJOR 11DI: P:tESSURE VESSELS - RHR HEAT EXCHANCERS l

11V4 OLM'ONENT OR SYSnN, ACCES-INSPECTION M

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RHR PIT 151-93 (MULTIPLE STREAMS)

RHR HEAT EXCHANGER No. 12 UT 2

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RHR PIT 1S1-93 Ka. 11 WELD 3 UT INLET EL666' i

No. 11 WELD 4 UT 1

100%

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TANI 2.2.1 i

PRAIRIE ISIAND LNIT 1 PAGE 1

OF 5

1IN YEAR INIERVAL INSPECTIm SlM4ARY MAJOR ITIN:

PIPING - CIRCUMFERENTIAL BUTT WELDS 1

1 i

EXAM QMUINT OR SYSnN, KQS-INSPECTIm (40 YR.)

SUB CATE-AND DESCRIPTION OF NDE E AL IBLE 40 YR.

10 YR.

PERIOD MTION EM N

I IIM CORY ITIN 10 BE EXAMINED MET 10DS ITIMI I1TMs N

N (10 YR.)

RELIEF NO. 46 C2.1 C-G CIRCUMFERENTIAL BUTT WELDS U.T.

RELIEF No. 50 RELIEF No. 56 1

l MAIN STEAM A I

32-MS-1 U.T.

I 1

1 0

(50%)

EL 795' GENERATOR 11 ISt-51A (MULTIPLE MAIN STEAM B STREAMS) j 32-MS-2 U.T.

I 1

0 0

EL 795' GENERATOR 12 ISI-68A 1

l MAIN STEAM A 4

30-MS-1 U.T.

7 5

2 1

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EL 795' TO EL 726' ISI-51A (MULTIPLE i

MAIN STEAM B STREAMS) 30-MS-2 U.T.

9 6

2 0

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EL 726' THRU PENET. 6A ISI-51A,51B TM I

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31-MS-2 U.T.

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EL 726' 111RU PENET.6B IS I-68A,688 u

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MAIN STEAM A l

RELIEF HDR 30-MS-1 U.T.

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(50%)

EL 739' RELIEF HDR.A ISI-518 gpg MAIN STEAM B II I

RELIEF HDR 30-MS-2 U.T.

6 5

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THREE EL 759' RELIEF HDR.B 1S1-68B

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MAIN STEAM A l

6-MS-1 U.T.

6 4

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EL 739' AUI. BLDG.

ISI-51B INCLUDES 1 5' JOINT j

i MAIN STEAM B 6-MS-2 U.T.

6 4

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ONE EL 759' AUX. BLDG.

ISI-68B 3

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16-W-13 U.T.

18 18 5

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EL 770' CONTAINMENT ISI-52A (LINES l

t 16-N-12 U.T.

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FEEDWATER B (ENCAPSUIATED)

Zh l%-

16-FW-16 U.T.

16 2

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TABLE 2.2.1 PRAIRIE ISIAND INIT 1 PMI 4

0F 5

1EN YEAR INIERVAL INSPECTIN StM4ARY MAJOR ITD4: PIPING - CIRCLHFERENTIAL BUTT WELDS EXAM QMMENT OR SYS11N, ACCES-INSPECTIN SUB CA1E-AND DESC3tIPTIm 0F NDE TUTAL IBLE 40 YR.

10 YR.

(40 TR.)

PERIOD IDCATIN RD4 ARKS 1134 CDRY IID4 10 BE EXAMINED ML'IIEDS IlUS ITIM; EXM4 EXAM T

(10 YR.)

C2.1 C-C ACCLHUIATOR DISGARGE LINES i

12-SI-28A U.T.

5 5

1 1

ONE (571)

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2 2

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7 7

2 (551)

EL 704' CONTAINMENT ISI-85 (MULTIPLE 12-S1-29B U.T.

4 4

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C2.1 C-F RESIDUAL HEAT REMOVAL SUCTION j

12-RH-5A U.T.

13 13 7

1 Two (100%)

EL 672' RnR ROOM ISI-53 (HULTIPLE THREE EL 672' RHR ROOM ISI-53 STREAMS) 12-RH-58 U.T.

13 13 6

2 Iv0 EL 672 RHR ROOM ISI-76 i

8-RH-5A U.T.

2 2

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3 3

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8-RH-4A U.T.

8 8

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EL 687' RHR ROOM ISI-53 (MULTIPLE l

8-RH-4B U.T.

4 4

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20 20 20 5

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AUX. BLDG.

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4 4

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12 12 6

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13 13 7

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8-RH-9A U.T.

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14 14 7

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TABm 2.2.2 PRAIRIE ISIAND INIT I PAGE 1

0F 4

j TEN YEAR INIMAL INSPECTION SIM1ARY MAJOR ITIN: PIPING - LONGITUDINAL WELD JOINTS j

IN FIIIING5 EXAM OMMENT OR SYSHN, ACCES-LNSPILTIW M

Calli-AND DESCRIPTION OF M

ME IBg 40 YR.

10 YR.

(40 YR.)

M OD TION EM ITm 00RY 111N 10 BE N ME11EES 11DG 11T m EXAM EXAM N

00 YR.)

C2.2 C-G LONf;InfDINAL WELD JOINTS RELIEF NO. 46 IN FITTINGS RELIEF No. 56 MAIN STEAM A 32-MS-1 U.T.

I 1

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ASME Section XI Pressure Testing Program - Unit No. 1 and Common Components A %I Code Edition and Addenda: 1974 EdLtion through and including Sunener 1975 Addenda Icogram Period: April 16, 1977 to Dece:aber 16, 1983 The system Code Class boundaries are established on the att ched ASME Code Classification Drawings, Sheets 2 through 40.

The Pressure Test Program for the Class 1, 2, and 3 systems le as fe~~ -s ASME TEST TEST TEST SPECIFICATION REQUEST FOR RELIEF CODE CLASS TYPE FREQUENCY Leakage Refueling IWB-5210(a).

  1. 20, #60 IWB-5221 IWA-5000 g

1

  • w 1

Hydrostatic 10 years IWB-5210(b)

  1. 20 IWB-5222 IWA-5000 2

Pressstre Test 3.1/3 years IWC-2412

  1. 19, #20, #29 IWC-2510 IWC-5210 2

Hydrostatic Test 10 years IWC-2412

  1. 19, #20, #29 IWC-2510 IWC-5210 458 3

Pressure 10 years IWD-2410 (b)

  1. 20, #28, #30, #31 WE CG 55=

I f

f'",

(

%/

k.)

ASME CODE VALVES i

SYS FLO'4 DIA. RAM VALVE NC f f MS NC DECCRIPTION VLV CAT TEST PROC REQUEST FOR RELIEF pg g

..A i

B SP-1099 E

CS MS NF-39218 CV-31099 15 tso MS NF-39218 CV-3109>

If 11 LOOP A MN SIM HDR B

SP-1099 E

CS ISOL B

SP-1102 E

M MS NF-39218 MV-32264 15 p y MS NF-39218 RS-21-1 15 SAFETY VLV SM GEN 11 C

SP-1049 SP SY MS NF-39218 RS-21-2 SAFETY VLV SM GEN 11 C

SP-1049 SP SY MS NF-39218 RS-21-3 15 SAFETY VLV S M GEN 11 C

SP-1049 SP SY MS NF-39218 RS-21-4 15 SAFETY VALVE SIM GEN 11 C

SP-1049 SP SY

'h MS NF-39218 RS-21-5 15 SAFETY VALVE SM GEN 11 C

S*-1049 SP SY u

MS

s7-39218 RS-21-6 15 SAFETY VALVE SIM GEN 12 C

SP-1049 SP SY MS TNF-39218 RS-21-7 15 SAFETY VALVE SIM GEN 12 C

SP-lO49 SP SY MS NF-39218 RS-21-8 15 SAFETY VALVE SIM GEN 12 C

SP-1049 SP SY MS NF-39218 RS-21-9 15 SAFETY VALVE STM GEN 12 C

SP-1049 SP SY MS NF-39218 RS-21-10 15 SAFETY VALVE SM GEN,12 C

SP-1049 SP 5'Y U

l MS NF-39218 RS-15-1 15 C

SP-1103 E

R

  1. 5 P CHE K MS NF-39218 RS-15-2 15 C

SP-1103 E

R

  1. 5 F PUMP HE C, m a-g

=

k

O O

O

19. REQUEST FOR RELIEF PAGE OF ASME COMPONENT FUNCTION Code Viv Class Cat ALL CLASS 2 COMPONENTS PRESSURE RETAINING 2

CODE REQUIREMENT The system pressure tests will not be conducted as required by the 1974 Edition throu3h and including the Summer 1975 Addenda of the ASME XI Code.

BASIS The 1974 Edition Summer 1975 Addenda does not address examination frequency or pressure requirements for Class 2 systems.

7 ALTERNATE INSPECTION (TESTING)

T D',

All components will be pressure tested in accordance eith 1977. Edition through and including the Summer 1978 Addenda of the ASME Section XI Code with exceptions as listed below.

EXCEPTIONS k

1.

The examination method for the IWC-5221 & IWC-5222 Test will be in accordance with the 1974 Ed d

through 1975 Summer Addenda.

@o 2.

For those Class 2 systems which are in continuous operation.ind where no

[

the in service operation pressure shall be the test pressure.

vs SCHEDULE FOR IMPLEMENTATION

'v, E

January 1. 1982 d

Og is:

""R a.

O O

b

29. REQUEST FOR RELIEF

~

ASME COMPONENT FUNCTION ccde Viv Class rat Safety Injection Piping unisolable from Class 1 Pressure Retaining 2

piping (Sheet 8)

Reactor Coolant System Piping 3/4" & smaller that is unisolable from Class 1 Piping (Sheet 2)

Pressure retaining 2

Residual Heat Removal System piping unisolable from Class 1 piping (Sheet 8)

Pressure retaining 2

RCP Seal Injection piping 3/4" & smaller that is unisolable from Class 1 Piping (Sheet 4)

Pressure retaining 2

RCP Seal Return piping unisolable from Class 1 (Sheet 4)

Pressure retaining 2

Charging Line piping unisolable from Class 1 (Sheet 4)

Pressure retaining 2

t*

Sample System piping unisolable from Class 1 hp (Sheet 2)

-Pressure retaining 2

CODE REQUIREMENT Portions of the Class 2 piping will not be tested at the pressures required by IWC-5000.

BASIS The piping is not isolable from the Class 1 piping.

I ALTERNATE INSPECTION (TESTING)

The piping will be tested to the Class I requirements, i.e.:

1

~ N2 1.

The unisolated portions of the Class 2 piping will be visually examined for evidence of' leakage at the IETQ system nominal operating pressure in accordance with the requirement of IWB-5221. This inspection will

0!G be performed prior to startup following each reactor refueling outage.

2.

The unisolated portion of the Class 2 piping will be hydrostatically tested when the Class 1 piping is tested.

i as SCHEDULE FOR IMPLEMENTATION January 1, 1982

O O

h/J. REOUEST FOR PELIEF ASME

  1. .e Viv COMPONENT FUNCTIO 4
',1r,s Cat l't, 22 Diesel Cooling Water Pump Remove heat from components that must function 3

during accident conditions.

CODE REQUIREMENT Inlet pressure will not I,? used to evaluate the condition of the pump as required by IWP-3110 and 3210.

1 BASIS 1

The pump suction is located in the cooling water intake bay and suction pressure indication is not available.

1 ALTERNATE INSPECTION (TESTING)

Intake bay level will be factored into the differential pressure data used in the pump test.

4 SCIEDULE FOR IMPLEMENTATION 4

." April 16, 1977 y

g 4

1 9

i i

a a

u y

8 m

NN D5 4

tM 4

i Z

e

O O

O 45.

REQUEST FOR RELIEF 6

CODE PROGRAM CODE EXAM COMPONENT OR ITEM CLASS TABLE ITEM CATEGORY REGENERATIVE HEAT EXCHANGERS 1

1.3.2 B3.1 B-B EXCESS LETDOWN HEAT EXCHANGER 1

1.3.3 B3.1 B-B RHR HEAT EXCHANGERS '

2 2.1.3 C1.1 C-A C1.2 C-B BORIC ACID TANKS 2

2.1.4 Cl.1 C-A Cl.2 C-B os

, CODE REQUIREMEtTT Ultrasonic examinations shall be conducted in accordance w.i th Appendix I of Section XI or the provisions of i

l Article 5 of Section v.

y BASIS u

PJ The design requirements for these heat exchangers and tanks resulted in relatively thin wall vessels which permitted them to be fabricated from piping components or thin plate. Therefore, the ultrasonic examination procedure for pipe welds would be more applicable than these for heavy wall vessels.

ALTERNATE The ultrasonic examination procedures will comply with Appendix III of the 1974 Edition through the Summer 1976 Addenda of ASME Section XI.

I l

SCHEDULE FOR IMPLEMENTATION i

mg D <:

April 16, 1977 CU i

c -

2$

os

46.

REQUEST FOR RELIEF CODE PROGRAM CODE EXAM COMPONENT OR ITEM CLASS TABLE ITEM CATEGORY SAFE END TO PIPING 1

1.4 B4.1 8-F CIRCUMFERENTIAL AND LONGITUDINAL PIPEWELDS 1

1.4 B4.5 B-J BRANCH PIPE W'1DS 1

1.4 B4.6 B-J INTEGRALLY WELDED SUPPORTS 1

1.4 B4.9 B-K-1 CIRCUMFERENTIAL BUTT WELDS 2

2.2.1 C2.1

,-F/C-G LONGITUDINAL WELD JOINTS IN FITTINGS 2

2.2.2 C2.2 C-F/C-G BRANCH PIPE TO PIPE WELD JOINTS 2

2.2.3 C2.3 C-G CODE REQUIREMDTTS Ultrasonic examinations shall be conducted in accordance with Appendix I of Section XI or' the provisions of Article 5 of Section V.

7 vi BASIS b

Appendix I of Section XI is not applicable to most of these piping welds due to the size and material limitations of Appendix I.

And the use of side drilled holes to establish a distance amplitude correction (DAC) curve, as required by Article 5 of Section V, results in an instrument gain setting which greatly impairs the examiner's ability to detect and to interprete indications by producing a much lower signal-to-noise ratio and decreases the usable DAC range.

ALTERNATE The rules of Appendix III, including Supplement 7, of the 1974 Edition through the Sumner 1976 Addenda of ASME Section XI will be used for the ultrasonic examination of piriing welds and welds in components fabricated from pipe.

The evaluation of indications will comply with the rules of the Summer 1975 Addenda of Section XI.

36 I

tt:

co s SCHEDULE FOR IMPLEMENTATION os April 16, 1977

O 47.

REQUEST FOR RELIEF CODE PROGRAM CODE EXAM COMPONENT OR ITEM CLASS TABLE ITEM CATEGORY REACTOR COOLANT PUMP 1

1.5 B5.4 B-K-1 INTEGRALLY WELDED SUPPORTS a

l CODE REQUIREMENT l

Perform volumetric examination of the. integrally welded support attachments.

i BASIS Present ultrasonic examination methods would be ineffective because of the weld joint geometry and the heavy wall, austentic stainless steel cast structure of the pump body and lugs.

~

Y u

ALTERNATE S~

If a proven volumetric examination technique is developed an attempt will be made to examine these welded supports.

However, if a volumetric examination techniq'e is not developed, a surface examination.:111 be performed on the weld to the extent possible.

SCHEDULE FOR IMPLEMENTATION April 16, 1977 9 :n D$b

! OG m-

>.* O I

Z l

Os

48.

REQUEST FOR RELIEF CODE PROGRAM CODE EXAM COMPONENT OR ITEM CLASS TABLE ITEM CATEGORY h

REACTOR COOLANT PUMPS FLANGE AND SEAL HOUSE BOLTING 1

1.5 B5.1 B-G-1 l

B5.2 1 B-G-1 STEAM GENERA'IOR MANWAY BOLTS 2

2.1.1 Cl.4 C-D ACCUMULATOR MANWAY BOLTS 2

2.1.2 Cl.4 C-D RHR HEAT EXCHANGER FLANGE BOLTING 2

2.1.3 C1.4 C-D BORIC ACID TANK MANWAY BOLTS 2

2.1.4 Cl.4 C-D PIPING PRESSURE RETAINING BOLTO 2

2.2.4 C2.4 C-D PUMP PRESSURE RETAINING BOLTS 2

2.3 C3.2 C-D VALVE PRESSURE RETAINING BOLTS 2

2.4 C4.2 C-D CODE REQUIREMENTS

\\

Ultrasonic examinations shall be performed in accordance with Article 5 of Section V when the provisions of Appendix I of Section XI do not apply.Section V requires that calibration be established on a test bar that has certain physical and chemical parameters.

BASIS The Section V technique utilizing the calibration test bar was not used for the baseline examinations and it is not as sensitive to detect discontinuties as the presently applied back reflection method.

In addition, when using the back reflection method, the poorer the end reflecting surfaces (painted, corroded, etc.) the more conservative the examinations are.

_A_LTERNATE w

D The items will be examined using the back reflection method correlated with an as built sketch of the particular O

bolt or stud being examined. ASME Section XI will be used for evaluation criteria.

o> H

~e SCHEDULE FOR IMPLEMENTATION April 16, 1977

~.

1 52.

REQUEST FOR RELIEF CODE PROGRAM CODE EXAM COMPONENT OR ITEM CLASS TABLE ITEM CATEGORY NON-WELDED SUPPORT COMPONENTS 1

1.4 B4.10 B-K-2 2

2.2.6 C2.6 C-E-2 i

IND-2500 (c) 3 4

l CODE REQUIREMENT Examination Category B-K-2 and C-E-2 of ASME Section XI requires all areas of the support component from the piping, valve, and pump attachment to and including the attachment to the supporting structure be examined.

BASIS w

Y Insulation will not be removed for visual examination provided that all mechanical connections and welds can be i

examined.

It has been our experience that any loss of support capability or inadeqt. ate restraint can usually be detected through the inspection of the uninsulated portion of the support and the surrounding insulation. The i

governing Codes and Regulations used in the design and construction of those systems that are now classified as Class 2 and 3 did not require provisions for inspection access for these systems. Thus, it would be an ubdue burden without compensating increase in safety to require insulation removal for support inspection.

i ALTERNATIVE The insulation will be removed from a supported component for further inspections whenever the connections and welds can not be examined or an abnormality is detected that may have been a result of a loss of support capability or inadequate restraint.

i I

y SCHEDULE FOR IMPLEMENTATION y5 CU April 16, 1977 3$z o

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55.

REQUEST FOR RELIEF CODE PROGRAM CODE EXAM COMPONENT OR ITEM CLASS TABLE ITEM CATEGORY i

1 SAFE END TO PIPING 1

1.4 B4.1 B-F CIRCUMFERENTIAL AND LONGITUDINAL PIPE WELDS 1

1.4 B4.5 B-J j

CIRUMFERENTIAL BUTT WELDS 2

2.2.1 C2,1 C-F/C-G IONCITUDINAL WELD JOINTS IN FITTINGS 2

2.2.2 C2,2 C-F/C-G BRANCH PIPE TO PIPE WELDS 2

2.2.3 C2.3 C-G RHR HEAT EXCHANGERS 2

2.1.3 C1.1 C-A C1.2 C-B BORIC ACID TANKS 2

2.1.4 C1.1 C-A j

C1.2 C-B

-m i

4 p

CODE REQUIREMENT w

S When using Appendix III of ASME Section XI Summer 1976 Addenda, the basic calibration blocks shall be made froni j

material of the same nominal diameter as those to be examined, i

BASIS j

I i

A flat basic calibration block may be used in lieu of a block essentially the same curvature for components greater than 20 inches in diameter. Any difference in accuracy and sensitivity for ultrasonic examination when using a flat basic calibration block verses a curved basic calibration blocks for components greater t..an 20 inches in l

diameter is within the accuracy of the test.

NSP believes that compliance with Appedix III requirements for basic calibration block curvature would be an undue burden with no increase in public safety.

l

[

ALTERNATIVE l

' ug For surface curvature, the rules of Article 5 of Section V,.1974 Edition through Summer 1975 Addenda, will apply Da for examination of pipe welds and welds in components fabricated from piping, In addition-the other requirements l O of Appendix III for basic calibration blocks will be met.

(n H k

SCHEDULE FOR IMPLEMENTATION April 16, 1977 I

1 i

63.

REQUEST FOR RELIEF l

CODE PROGRAM CODE EXAM COMPONENT OR ITEM CLASS TABLE ITEM CATEGORY i

REACTOR COOLANT 1

1.5 B5.6 B-L-1 PUMP CASING WELDS CODE REQUIREMENT Volumetric examination of the pump casing weld at or near the end of the inspection interval.

il BASIS Present ultrasonic examination methods would be ineffective because of the neavy wall, austeraitic stainles; steel g

cast structure of the pump body.

Ou ALTERNATE If a proven volumetric examination technique (ultrasonic or radiograpy) is developed, an attempt will be made to l

examine this weld when pump is disasr%1ed near the end of the inspection interval.

If a volunetric inspection technique is not developed, a surface examination will be performed on the weld to the extent p.'ssible.

SCHEDULE FOR IMPLEMENTATION September 30, 1981 u :n Uk G

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t l

64.

REQUEST FOR RELIEF i

CODE PROGRAM CCDE EXAM COMPONENT OR ITEM CLASS TABLE ITEM CATEGORY i

i REACTOR VESSEL SAFETY INJECTION 1

1.1 Bl.4 B-D N0ZZLE TO VESSEL WELDS

)

CODE REQUIREMENT The 1974 Edition through the summer 1975 Addenda of ASME Section XI requires a minimum and identified a maximum percentage of examinations that are to be completed by the expiration of each of the three inspection periods.

l l

BASIS The Safety Injection nozzle to vessel welds (2) will not be examined in accordance with this schedtle. The

  • w I

4 Westinghouse reactor vessel inspection tool will be used to perform these examinations, and to date, they have.

been unable to develop a reliable inspection head for these small injection nozzles. The inspection head is nev designed to house contact ultrasonic transducers. This design will allow a very minimum variation in alignment between the core barrel and the vessel nozzle, and also in the cladding variation on the nozzle inside diameter.

ALTERNATE l

Both Safety Injection nozzle to vessel welds will be examined at the end of the ten year interval when the core barrel is removed.

SCHEDULE FOR IMPLEMENTATION September 30, 1981 E!E S:;5 4

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C NORTHERN STATES POWER CO.

TN I'I DRAIRIE ISLAND 1; NIT 2 PAGE 1 g 6 TEN VEAR INTERVAL INSPECTION

SUMMARY

MtX)R IIDt:

REACTOR VESSEL EXAM.

COEMENT OR SYSTDI, 1UTAL INSPEC-MIN OR MW.

CATE.

AND 00S3tIPTION &

M).PER IDDITIFICATIM EXAMINATIm TIN WM MM N7 RDRRKS (ITa' iTIN 1T) BE FXAMINFD TTTN NT AND NT prpion 81.1 F4 IJNGITUDINAL AND RAUIRES THE REMOVAL CIRCLWFERENTIAL WELDS IN OF CORE BARREL CORE REGION LONGITUDINAL WELDS NONE CIRCUMFERENTIAL WELDS 1

U.T.

WELD NO. 3 21 FEET (MIN.)

THREE LOWER SHELL ASSEMBLY 50 RELIEF NO. 55 (2-ISI-42)

TO INTERMEDIATE WELD Bl.2 B-B LONGITUDINAL AND RMUIRES THE RD40 VAL CIRCUMFERENTIAL WEL J

OF THE CORE BARREL SHELL (OTHER THAN Th E OF CATEGORY B-A AND B-C) AND MERIDIONAL AND CIRCLWFERENTIAL SEAM WELDS P

IN BOTTOM HEAD AND CLOSURE t'

HEAD (OTHER THAN THOSE OF y

CATEGORY B-C) i m

LONGITUDINAL WELDS NONE MERIDIONAL WELDS NCHE CIRCUMFERENTIAL WELDS 3

U.T.

WELD NO. 2 25 INQlES (MIN.)

THREE UPPER SHELL ASSEMBLY 5

RELIEF NO. 55 (2-ISI-42)

TO LOWER SHELL ASSEMBLY WELD NO. 4 25 INCHES (MIN.)

THREE LOWER TRANSITION HEAD 5

(2-ISI-42)

TO SHELL WELD WELD NO. 5 25 INCHES (MIN.)

THREE BOTTOM HEAD RING TO 5

(2-Isi-42)

LOWER TRANSITION HEAD WELD B1.3 a-C VESSEL-TO-FIANCE AND RELIEF NO. 55 HEAD-TO-FIANGE CIRCUMFERENTIAL WELDS VESSEL TO FIANGE 1

U.T.

WELD NO. 1 CLOCKWISE. 14 FT.

ONE VESSEL FIANGE 33 (2-ISI-42)

(MIN.)

CLOCKWISE. 12 FT, TWO VESSEL FIANGE 62 (MIN.)

qg CLOCKWISE. 16 FT.

THREE VESSEL ITANGE 100 gg (MIN.)

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NORTHERN STATES POWER CO.

TABIE 1.2 PRAIRIE ISLAND UMIT 2 PAGE 1 op 2 TEN VEAR INTERVAL INSPECTION

SUMMARY

MVOR ITIN:

PRESSURIZER 4

i EX,W GMUUT OR SYSlDI, 1UTAL INSPEC-my E

CAlt'.

AND DESCRIPTim 0F W.PER IDDTIFICATION MMTIN TI21 RDERKS SN N g--

E mW TTTN 10 BF FX4fTNTD TTTN NT M NT prpion B2.1 P-B LONCIWDINAL AND RELIEF NO. 55 CIRCWJERENTIAL WELDS (2-1S1-36)

EXAMINATION OF i

LONGITUDINAL WELDS LONGITUDINAL WELDS 2

U.T.

WEID NO. 1 7" (MIN.)

THREE BOTTOM HEAD, UP O 45' 5

AT ME JUNCTION WITH 7" (MIN.)

THPEE LOWER SHEII, DOWN 10 THE CIRCL"MFERENTIAL 0

45' WEIDS - ORIENTATION CW FROM MANWAY FOR WEID NO. 2 8" (MIN.)

ONE UPPER SHELL. UP G 1350 5

WELD 1 AND WELD 2 8" (MIN.)

TWO TOP HEAD. DOWN O 1350 10 CIRCUMFERENTIAL WELDS 3

U.T.

WEID No. 3 5" (MIN.)

ONE BOTTOM HEAD TO 240' 1.7 V!' EL NAME 5" (MIN.)

TWO LOWER SMFIJ 120' 3.4 FIATE @ O*,

CW FOR 5" (MIN.)

THREE 0'

5.2 CIRCLHFERENTIAL l

SHEli V!LDS WELD NO. 4 5" (MIN.)

ONE UP'ER SHELL TO 2408 1.7 5" (MIN.)

TWO I/VER SHELL 120' 3.4 7

5" (MIN.)

THREE 08 5.2 WEID NO. 5 5" (MIN.)

OtiE TOP SHELL TO 240*

1.7 5" (M m.)

TWO UPPER SHEll 120' 3.4 5" (MIN.)

THREE 0*

5.2 52.2 B-D N0ZZLE-TO-VESSEL WELDS NONE 82.3 B-E HEATTR PENETRATIONS 78 Y

HEATER SER. NO.

LOWER HEAD 1 THRU 7 7 PENETRATIWS ONE 9

34 THRU 40 7 PENETRATIONS TWO 18 72 THRU 78 7 PENETRATIONS THREE 27 B2.4 B-F N0ZZLE-TO-SAFE END WELDS 5

S-U.T.

2-8010A-IAS.E.

2 WELDS (100%)

0NE/Tm SAFETT LINE (6-2RC-204) 20 2-8010B-IAE.E.

ONE/TWO SAFETY LINE (6-2RC-208) 40 2-151-35 AND 2-151-30 qg WEID 15 S.E.

1 WELD (100%)

TWO SURCE. LINE 14" 60 g

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WELD 1A S.E.

1 WELD (100%)

TWO RELIEF LINE (4" x 3")

80 2-ISI-27 THREE (3-2RC-21)

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2002 2.1.1 1h REVISION 6 7/31/81

s NORTHERN STATES POWER CO.

N I'

DRA!RIE ISLAND L'MIT2 TEN YEAR INTERVAL INSPECTION

SUMMARY

MW IM: PIPING PRESSI'RE BTNDARY I

EXAM.

(XMON OR SSTDt.

1UTAL INsprc-TI N OR

MIS, j

CATE.

AND DESCRIPTI m OF M).PER IDDiTIFICATIm EXAMINATI N TION MRKS SYSM NtNBER N7 mRY TTTN 1T) PF FX4fTNFD T1TN AHINT AND EXTINT prnim B4.5 B-J 6.0 IN. N W. DIA. SYSU MS REACTOR VESSEL 6

U.T.

BUTT WELDS ONE SAFETY INJECTION LOOP A - 6" 1 WELD 100%

TWO EL 721' (6-2SI-25A) 17 LOW HEAD 2-151-29 1 WELD 100%

THREE EL 707' (6-2SI-25A) 33 REACTOR VESSEL 8

U.T.

BUTT WELDS 1 WEID 100%

ONE EL 716' (6-251-258) 13 13 SAFETY INJECTION LOOP B - 6"

-NN E-TWO IDW HEAD 2-ISI-28 1 WEIS 100%

THREE EL 723' (6-2RC-145) 25 SAFETY INJECTION 3

U.T.

BUTT WELDS ONE g

HICH HEAD LOOP A - 6" TWO 2-ISI-8 1 WELD 100%

THREE CUBICLE A (6-2RC-138) 33 SAFETY INJECTION 3

U.T.

BUTT WEID 1 WELD 100%

ONE CUBICLE B (6-2RC-13D) 33 TWO 33 HIGH HEAD LOOP B = 6" 33 2-151-18 THREE e.

  • y PRESSURIZER SAFETY 8

U.T.

BUTT WEIDS

-NONE-ONE g

LINE A LINE A - 6" 3 WELDS 100%

TWO CUBIC 12 B (6-2RC-20A) 38 2-1S1-30 1 WEID 100%

THREE CUBICLE B (6-2RC-20&)

50 PRESSURIZER SAFETY 8

U. T.

BUTT WEIDS 2 WELDS 100%.

ONE CUBICLE B (6-2RC-208) 25 LINE B LINE B - 6" 2 WELDS 100T TWO 50 i

2-1S1-30 1 WEID 100%

THREE CUBICLE B (6-2RC-205) 62 PLO - CAP 1

U.T.

BUTI WEID

-dW E-ONE LOOP A - 6"

-NONE-TWO 2-ISI-9 1 WELD 100%

THREE CUBIC 12 A (6-2RC-13A) 100 ONE

=**

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U.T.

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TWO CUBIC 12 B (6-2RC-13C) 100 100 2-151-19

-NU1E-THREE f

LM"R 4

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D NORTHERN STATES POWER CO.

'RA!RIE !SLAND l't:IT 2 TABE 1.4 TEN YEAR I N TERV AL INSPECTION

SUMMARY

MVOR IID4: PIPING PRESSURE BOUNDARY I. N EXAM.

03fMLYT OR SYS1IN, 1UTAL INSPEC-CATE-AND DESCRIPTIN OF

.T.PER IDINTIFICAT!m EXAMINATI m I OR TION SYSTDI NtNBER N7 RD nRKS 2

ITD' mw TTTM 10 BF EWTNTD TTTN AMXNT AND EFTdNT prnmn B4.10 B-K-2 CONTINUED (NON-WELDED)

REACTOR VESSEL 4

V SUPPORT 1 SUPPORT 100%

ONE EL 721' (6-2SI-25A) 25 SAFETY INJECTION LOOP A -

4" &

1 SUPPORT 100%

WO EL 723' (4-2RC-14A) 50 6"

2-ISI-29 2 SUPPORTS 100%

THREE EL 722' (6-2RC-14A) 100 (4-2RC-14A)

PRESSURIZER SAFETY 2

V SUPPORTS LINES LOOP A & B -

6" -

2-ISI-30 LINE A 1

V 1 SUPPORT 100%

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(6-2RC-20A) 50 LINE 3 1

V 1 SUPPORT 100%

TWO ATOP PZR.

(6-2RC-20B) 100 U

"c !!! A SURCE 12 V

SUPPORTS 3 SUPPORTS 100%

ONE CUBICLE B (10-2RC-4) 25 I40P B - 10" 4 SUPPORTS 100%

TWO CUBICLE B (10-2RC-4) 58 2-ISI-31 5 SUPPORTS 100%

THREE CUBICLE B (10-2RC-4) 100 REACTOR CORE C0OLANT 4

V SUPPORTS 1 SUPPORT 100%

THREE SANDPLUG (27.5-2RC-3A:

75 ADDED 2 RESTRAINTS LOOP A 1 SUPPORT 100%

TWO CUBICLE A (31-2RC-2A) 25 IN 1981 OUTAGE 2-ISI-32 1 SUPPORT 100%

THREE CUBICLE A (31-2RC-2A) 50 REACTOR CORE COOLANT 4

V SUPPORTS 1 SUPPORT 100%

ONE CUBICLE B (31-2RC-28) 25 ADDED 2 RESTRAINTS LOOP B 1 SUPPORT 100%

THREE SANDPLUG (27.5-2RC-38]

75 IN 1981 OUTAGE 2-ISI-33 1 SUPPORT 100%

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I MEDE2N STATES POER (D.

TABR '

PRAIRIE ISIAND UNIT 2 I

PA2 OF I

1EN YEAR Ih*IIRVAL INSPECTIN Sl)MARf M 2 MM M I g. PRESSURE VESSELS - STEAM CENERA M RS EXAM GMGIAT OR SYSUN, ACGS*

INSPECTIW (40 YEAR)

SUB CATE-AND ESGIPUN Op NDE 1DTAL IEg 40 YR.

10 YR.

PERIOD TIN N

E IM 00RY ITIN 10 BE EXAMINED EN ITDG gm EXAM M

(10 YR.)

C1.1 C-A

_CIRCLHFERENTIAL BUTT WELDS STEAM CENERATOR NO. 21 UT 5

5 2

1 CONTAINMENT 2-151-37 (MULTIPLE STREAMS)

STEAM CENERATOR NO. 22 UT 5

5 3

1 CONTAINMENT 2-ISI-37 NO. 21 WELD 8 UT 20%

20%

TWO 20%

TUEESHEET TO SHELL EXAMINATION OF T=3.25" L=!

EACH CIRCLHFERENTIAl No.21 WELD F UT 20%

20%

TRANSITION TO SHELL WELD WILL INCLUDE T=3.68-3.62 L=46' THREE AREAS THAT No. 22 WELD C UT 20%

20%

SHELL TO S!* ELL ARE DISTRIBUTED T=3.25-2.82 L*35' AROUND THE VESSEL NO. 22 WELD E UT 20%

20%

SHELL TO TRANSITION AS UNIFORMLY AS T=2.82-3.68" L=35' POSSIBLE u

l No. 22 WELD H UT 20%

20%

THREE 20%

SHELL TO HEAD

'u T=3.62 L=46' C1.2 C-8 NOZZLE-TO-VESSEL WELDS STEAM CENERATOR NO. 21 UT 2

2 1

CONTAINMENT 2-ISI-37 (MULTIPLE STREAMS)

STEAM CENERATOR NO. 22 L'T 2

2 1

1 CONTAINMENT 2-ISI-37 NO. 21 M.S.N0ZZLE(32")

UT EL. 795' NO. 21 F.W. NOZZLE (16")

UT 1

100%

EL. 771' NO. 22 M.S. NOZZLE (32")

UT 1

1 THREE 100%

EL. 795' NO. 22 F.W. NOZZLE (16")

UT EL. 771' C1.3 C-C INTEGRALLY WELDED SUPPORTS NONE C1.4 C-D PRESSURE RETAINING BOLTS 10 TEAK RELIEF NO. 48 PFRCENT STEAM CENERATOR NO. 21 V&UT 40 40 20 CONTAINMENT 2-ISI-37 (MULTIPLE STREAMS)

STEAM CENERATOR NO. 22 V6UT 40 40 20 CONTAINMENT 2-ISI-37

-4 m NO. 21 MANWAY A V4UT 00 TWO 100%'

UPPER SHELL UT WILL BE ?ER-DE NO. 21 MANWAY B V&UT UPPER SHELL FORMED AS A MIN-O NO. 22 MANWAY A V6UT UPPER SHELL IMUM on 10% OF

$o NO. 22 MANWAY B V6UT 20 THREE 1001 UPPER SHELL THE BOLTS ON EACH JOINT.

l

=

1 e

I t

NNI!ERN STATES POfER (D.

TABLE 2.1.2 PRAIRIE ISIAND LNIT 2 PA2 I

Or 1 TDI YIAR IVIIRVAL INSPECTION SLHMRY N 2 SY5' IDS MUOR ITIN: PRESSURE VESSELS -ACCLHULATORS j

1 llAM GMNT OR SYS11N, ACGS-Ip ;PECTIW E

CAIE-AND DESGIPTIW g NDE M AL IBLE 40 YR.

10 YR.

(40 YEAR) j PERIOD ITIN CDRY 111N TO BE EXAMINED EIMDS ITDS I196 D(AM M

(10 YR.1 T

.j f

C1.1 C-A CIRCLHFERENTIAL BUTT WELDS ACCtHULATOR No. 21 UT 4

4 2

1 CONTAINMENT 2-151-76 4

I (MULTIPLE STREAMS) 1 ACCLHU M TOR NO. 22 UT 4

4 2

CONTAINMENT 2-ISI-76 NO. 21 WELD 2 UT 20%

20%

SHELL TO HEAD EXAMINATION OF EACH T=2.75-1.39 L=31' CIRCUMFERENTIAL 1

NO. 21 WELD 6 UT 20%

20%

THREE 20%

DOLLAR PLATE TO HEAD WELD WILL INCLUDE T=1.39 L=16' THREE AREAS THAT ARE NO. 22 WELD 1 UT 20%

20%

HEAD TO DOLLAR Pu TE DISTRIBUTED AROUND T=1.39 L=16' THE VESSEL AS j

N0. 22 WELD 5 UT 20%

20%

HEAD TO SHELL UNIFORMLY AS T=2.75-1.39 L=31' POSSIBLE

[

C1.2 C-5 N0ZZLE TO VESSEL WELDS ACCUMUM TOR NO. 21 UT 1

1 1

100%

EL. 705',

12-2SI-29A 2-ISI-76 (MULTIPLE STREAMS)

ACCLHUMTOR No. 22 UT 1

1 EL. 705',

12-251-298 2-151-76 I

C1,3 C-C INTEGRALIT WELDED SUPPORTS ACCUMULATOR NO. 21 S

1 1

CONTAINMENT, SKIRT WELD 2-ISI-76 (MULTIPL3 STREAMS)

{

ACCLHULATOR No. 22 S

1 1

1 100%

CONTAINMENT, SKIRT WELD 2-ISI-76 C1.4 C-D PRESSURE RETAINING BOLTINC 10 YEAR RELIEF NO. 48 PERCENT l

ACCUMULATOR No. 21 V&UT 24 24 CONTAINMENT, MANWAY BOLTS 2-ISI-76 i

(MULTIPLE STREAMS) 1 ACCUMULATRO No. 22 V6UT 24 24 24 THREE 100%

CONTAINMENT, MANWAY BOLT $ 2-ISI-76 i

UT WILL BE PERFORME:

AS A MINIMUN ON 10% OF THE BOLTS

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TABIE 2.1.4 PRAIRIE ISIAND INIT 2 PAGE I

0F 1

1EN YEAR INTERVAL INSPECTICN SIMWW i

(IASS 2 SYSID6 MAJOR I1IN: PRESSURE VESSELS-BORIC ACID TANKS i

EXAM GM'mL%T OR SYSIIN, K HS-INSPECTICN SUB CATE-AND DESCRIPTION OF NDE 1UTAL IBLE 40 YR.

10 YR.

(40 PERIOD M)CATIN N

IllN (DRY 111M 10 BE EXAMINED EN I1DS 1136 EXAM EXAM NT 7

(30 yg,)

C1.1 C-A CIRCLHFERENTAIL BUTT WELDS RELIEF 45 AND 56 BORIC ACID TANK NO. 21 UT 2

2 2

AUX. BUILDINC 2-151-68 EXANINATION OF EACH 20%

HFAD TO SHELL CIRCUMFERENTIAL NO. 21 WELD 1 UT 20%

j T=.312 L= 3 3' WELD WILL INCLLTE 20%

SHELL TO MEAD THREE AREAS THAT ARI i

NO. 21 WELD 2 UT 20%

T=.312 L= 33' DISTRIBUTED AROUND THE YESSEL AS a

1 UNIFORMLY AS POSSIBLE.

j C1.7 C-B NOZZLE TO VESSEL WELDS RELIEF 45 AN3 56 i

f BORIC ACID TANK NO. 21 UT 1

1 1

100%

EL. 735', AUX BLDC 2-ISI-68 F

C1.3 C-C INTECRALLY M LDED SUPPORTS Y

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BORIC ACID TANK NO. 21 S

4 4

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TM PRAIRIE IS!AND INIT 2 PAGE 1

OF 3

1Di YEAR IN11RVAL INSPECTIN SLMARY PIPINC-INTECRALLY WELDED SUPPORTS N2N m gm EXAM GMtMAT OR SYS11N, Acas-yggpgcg7m (40 YEAR)

M CATE-AND DESCRIPTION OF NDE 1UTAL IBLE 40 YR.

10 YR.

PERIOD IMTIN N

ITM CDRY ITIN 10 BE ETAMINED H KOS 11DS 1196 EXAM EXAM NT (10 YR.)

C2.5 C-E-1 INTECRALLY WELDED SUPPM 10 YEAR PERCENT MAIN STEAM A & B 30-2MS-1 S

9 9

5 WO( 3)

(105%)

CONTAINMENT 2-ISI-46A THREE(2)

(MULTIPLE STREAMS) 30-2MS-2 S

10 10 5

ONE(1)

CONTAINMENT 2-ISI-47A TWO(2)

THREE(2)

MAIN STEAM A & B 31-2MS-1 S

5 5

4 ONE(3)

(120%)

AUX BLDC 2-ISI-46B (MULTIPit STREAMS)

TWO(1) u 31-2MS-2 S

5 5

2 THREE(21 AUX BLDC 2-ISI-47B L

MAIN OTEAM A & B m

O RELIEF HEADERS 30-2MS-1 S

1 1

1 THREE (100%)

AUX BLDC 2-ISI-uB (MULTIPLE 30-2MS-2 S

1 1

AUX BLDC 2-ISI-478 STREAMS)

MAIN STEAM A & B 6-2MS-1 S

1 1

(100%)

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1 1

1 ONE AUX BLDC 2-ISI-478 STREAMS)

FEEDWATER A & B 16-2FW-13*

S 9

9 5

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(105%)

CONT / AUX BlI, 2-ISI-48A TWO(2)

S 1

1 2-ISI-48B(MULTIPLE 16-2FW-11*

S 1

1 1

THREE(3 16-2FW-16 S

8**

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4 ONE(2)

CONT / AUX BLDC 2-ISI-49A STREAMS)

TWO(1)

    • EN0t.PSULATED THREE(1 RELIEF No. 50 RHR PUMP SUCTION 10-2RH-3 S

3 3

3 ONE (100%)

CONT / CONT SPRAY 2-ISI-50 TWO (SINCLE STREAM)

THREE Eh LM

~S

xanm stairs mWER 00.

TAB 1E PRAIRIE ISIAND UNIT 2 TIN YEAR INIIRVAL INSPECTION SlM MRY N2N W m 3 PIPINC-INTECRALLY WFLDED SUPPORTS 1

EXAM QMMENT OR SYS11N, gas.

INSPECTION g

CATE-AND DESCRIPTION (F M

TUTAL IBLE 40 YR.

10 YR.

(40 YEAR)

N (DRY ITIN 10 BE EXAMINED E ~IES IIIMS IIIMs EXAM EXAM PERONT l

l C2.5 10 YEAR C-E-1 CONTINUED i

PERCENT 8-2RH-4B S

2 2

1 TWO (133%)

RHR FIT 2-ISI-50(MULTIPLE 8-2RH-4A S

1 1

1 TWO RHR PIT 2-1S1-52 STREAMS) 12-2Rn-55 S

1 1

1 THREE (100%)

EL 666' RHR PIT 2-ISI-50(MULTIPLE 12-2RH-5A S

1 1

EL 666' RHR PIT 2-ISI-52 STREAMS)

RER PUMP DISCHARGE 8-2RH-7A S

1 1

1 THREE (100%)

EL 667' RHR H1 2-ISI-57 l

(SINCE STREAM) 1 8-2Ra-98 S

1 1

1 THREE (100%)

EL 680' RHR PIT 2-I51-55 (SINCLE STREAM) u 6-2SI-105 S

3 3

3 THREE (100%)

CONT SPRAY 2-151-55 (SINCLE STREAM) j r

M 4

I h

10-2RH-11 S

4 4

4 ONE(1)

(100%)

CGNT b' RAY 2-1S1-57 THREE(3 (SINGLE STREAM)

I l

CONTAINMENT SUMP B RELIEF No. 50 I

DISCHARCE EL 6J5' 00"T 2-ISI-58(MULTIPLE i

14-2SI-338 S

3 3

j 14-2SI-33A S

3 3

EL 695' C0hT 2-ISI-59 STREAMS) 1 BORIC ACID SUPPLY TO SAFETY INJECTION 12-2S1-11 S

1 1

1 THREE (100%)

EL 698' AUX BLDG 2-ISI-61 J

(SINGLE STREAM) l t

8-2SI-18 S

5 5

2 THREE (401)

EL 707' AUX BLDC 2-151-61 (SINGLE STREAM) t i

SAFET* INJECTION PUMP SUCTION 6-2RH-105 S

3 3

2 TWO (100%)

CONT SPRAY 2-ISI-63 y,

M THREE (HULTIPLE STREAMS)

Rg 6-2RH-10A S

5 5

2 ONE CONT SPRAY / AUX BLDC 2-ISI-65 "5

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1 PORIHERN STATES PONER (D.

TABIE 2.2.6 t

PRAIRIE IS1AND INIT 2 l

PAGE 1

OF 3

IDI YEAR INITRVAL INSPECTIN SlM4ARY i

WOR IUN. PIPING-NON-WELDED SUPPORTS I

N 2 SYSID E 4

1 EXAM GMuaAT OR SYSTIN, N-INSPECTICN (40 M y M

NDE 1UTAL IBII 40 YR.

10 YR.

M OD MTI(N N

i CATE-AND DESCRIPTICN g NT N

CORY 119410 BE EX#GNED-EMS 111MS rnn; EXAM EXAM (10 YR.)

10 TEAR RELIEP 52 C2.6 C-E-2 SUPPORT COMPONENTS PERCENT MAIN STEAM A & B 30-2MS-1 V

2 2

1 TWO (133%)

EL 760' CONT 2-ISI-46A (MULTIPLE 30-2MS-2 V

1 1

1 THREE EL 750' CONT 2-ISI-47A STREAMS) f 31-2MS-1 V

2 2

1 THREE (100%)

EL 726 CONT 2-ISI-46A(MULTIPLE 31-2MS-2 V

2 2

1 THREE EL 726' CONT 2-ISI-47A STREAMS)

}

I 30-2MS-1(HDR)

V 2

2 1

ONE (133%)

EL 726' AUX BLDC 2-ISI-46B(MULTIPLE I

30-2MS-2(HDR)

V 1

1 1

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'3 F

16-2FW-13 V

2 2

2 Ivo (1001)

EL 751' CONT 2-ISI-48A THREE (SINGLE STREAM)

RHR PUMP SUCTION 10-2RH-3 V

6 6

6 ONE(2)

(100%)

CONT /COlff SPR/.y 2-1S1-51 TWO(1)

(SINGLE STREAM)

THREE(3 i

1 8-2RH-4B V

2 2

1 THREE (133%)

RHR PIT 2-ISI-51 (MULTIPLE 8-2RH-4A V

1 1

1 TWO RHR PIT 2-ISI-53 STRhand!

12-2BH-5B V

2 2

1 THREE (50%)

P.HR FIT 2-151-51 (MULTIPLE 12-2RH-5A V

2 2

1 THREE RHR PIT 2-151-53 STREAMS)

RHR PUMP DISCHARGE i

8-2RH-7B V

2 2

1 THREE (133%)

EL 667' RHR PIT 2-ISI-55(MULTIPLE 8-2?1-7A V

1 1

1 THREE EL 667' RHR FIT 2-ISI-57 STREAMS) 8-2RH-95 V

4 4

2 THREE (133%)

RHR PIT 2-ISI-55(MULTIPLE 8-2RH-9A V

3 3

2 THREE RHR PIT 2-151-57 STREAMS) 6-2SI-108 Y

3 3

1 THREE (100%)

CONT SPRAT 2-ISI-55(MULTIPLE 6-2SI-12 V

1 1

1 ONE CONT 2-1S1-57 STREAMS) 10-2RH-11 V

3 3

2 THREE (67%)

EL 710' CONT SPRAY 2-ISI-57 SINGLE STREAM) gM 1

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NORDDN STATES POWER (D.

Tg 2.2.6 PRAIRIE ISLAND INIT 2 3

TDI YEAR INITRVAL LNSPECTION SI) NARY PIPING-NON-WELDED SUPPORT N2N wm 3:

EXAM GMmNT OR SYS11N, ACCES*

INSPECTIm i

M CATE-AND DESCRIPTION Op NDE TOTAL IBLE 40 YR.

10 YR.

(40 YEAR)

M OD i

IM CORY ITIN 10 BE EXAMINED EN IlDS I1IM; M

EXAM UN (10 YR.)

C2*6 10 TE^"

C-E-2 CONTINUED PERCENT i

CONTAINMENT SUMP B DISCHARGE LINES 12-2RH-6B V

2 2

1 THREE (100%)

EL 695' CONT SPRAY 2-ISI-58(Mtl.TIPLE 4

12-2RH-6A V

2 2

1 THREE EL 695' CONT SPRAY 2-ISI-59 STREAMS) l SAFETY INJECTION PtHP SUCTION 6-251-13A V

1 1

1 ONE (100%)

EL 703' AUX BLDG 2-ISI-60 6-2SI-138 V

1 1

EL 703' AUX BLDG (MULTIPLE STREAMS)

N BORIC ACID SUPPLY TO L

SAFETY INJECTION y

8-2SI-18 V

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(SINGLE STREAM)

SAFETY INJECTION PUMP SUCTION 6-2RH-10B V

2 2

1 nio 100%

EL 688' RHR FIT 2-ISI-63(MULTIPLE 6-2RH-10A V

2 2

1 TWO EL 693' RHR FIT 2-ISI-65 STREAMS)

REFUELING WATER STORACE TANK DISCHARCE d

14-2S1-1 V

1 1

EL 693' AUX BLDG 2-ISI-67 (SINCLE STREAM) 12-2SI-4 V

1 1

1 TWO 100%

EL 693' AUX BLDG 2-ISI-67 (SINGLE STREAM) 10-2SI-8 V

1 1

1 THREE 100%

EL 686' AUX BLDG 2-ISI-67 (SINGLE STREAM) l l

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2.1.2-21 REVISION 6 7/31/81 I

4 0

l NORT!!ERN STATES PNER (D.

TABLE 2.3 PRAIRIE ISIAND INIT 2 1Di YEAR IMIIRVAL INSPrfTIN SlMtARY PUMPS CIASS 2 SY91D E MMOR ITIN:

i i

EXAM QMWcNT OR SYS11N, ACGS-INSPFITIm 1

SUB CA1E-AND DESCRIPTION (F NDE 1UTAL IBLE 40 YR.

10 YR.

(4 YEAR)

M OD MTI@

EM ITm GORY ITIN TD BE EXAMINED MEllIES IIU6 ITD6 EXAM EXAM (10 YR.)

N j

C3*I C-G PUMP CASING WELDS SAFETY INJECTION PUMPS t

i CASING TO FLANGE WELD ON DISCHARCE

}

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1 (50%)

EL 693' AUX BLDG 2-ISI-60 j

  1. 22 PUMP UT 1

1 1

(MULTIPLE STREAMS) 2

{

C._ SING TO FLANGE WELD ON SUCTION

  1. 21 PUMP UT 1

1 1

(50%)

EL 693' AUX BLDG 2-ISI-60 4'

  1. 22 PUMP UT 1

1 (MULTIPLE STREAM) 4 C3.2 C-D PRESSURE RETAINING BOLTING UT WILL BE PERFORM-F ED ON A MINIMUM ON 7

M 10% OF THE BOLTS IN EACH JOINT ( AND NOT LESS THAN 2)

RHR PUMPS j

  1. 22 PUMP V,UT 24 24 (100%)

EL 666' RHR PIT 2-ISI-50 (PMLTIPLE

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4 SAFETY INJECTION PUMPS i

f21 DISCH FLANGE BOLTS V,UT 8

8 8

THREE (100%)

EL 693' AUX BLDG 2-ISI-60

  1. 22 DISCH FLANGE BOLTS V,UT 8

8 (MULTIPLE STREAMS) e

  1. 21 DRIVE END COVER BOLTS V,UT 16 16 (100%)

EL 693' AUX BLDG 2-ISI-60

  1. 22 DRIVE END COVER BOLTS V,UT 16 16 16 THREE (MULTIPLE STREAMS)
  1. 21 nitta0ARD END COVER i

BOLTS V,UT 16 16 16 THREE (100%)

EL 693' AUX BLDG 2-ISI-60

  1. 22 OUTBOARD EN COVER l

BOLTS V,UT 16 16 (MULTIPLE STREAMS)

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4 NrRI1E2N STATES POWER (D.

TABE 2.4 PRAIRIE ISIAND UNIT 2 11N HAR INIIRVAL INSPECTION SLMMRY CIASS 2 SYSms MMOR ITD(:

VALVES EXAM (IMMIAT OR SYSRN, ACCES-gem l

l SUB CATE-AND DESCRIPTION g NDE M AL IBLE 40 YR.

10 YR.

(40 YEAR)

M OD N

CDRY ITIN TO BE EXAMINED EN IIINS ITIM; EXAM EXAM (10 YR.)

N C4.1 C-F VALVE BODY WELDS UT NONE l

{

C-C Ca. 2 C-D PRESSURE RETAININC BOLTINC 10 YEAR RELIEF NO. 48 PERCENT MAIN STEAM A & B 4

31-2MS-1 V,UT 1 Valve L Valve 1 Valve TWO (100%)

EL 726' CV-31116 2-ISI-46B(MULTIPLE t

31-2MS-2 V,UT 1 Valve 1 Valve EL 738' CV-31117 2-1S1-475 STREAMS) 26-1 7/8" BOLTS i

30-2MS-1 V,UT 5 Valve: 5 Valves 2 Valves ONE (100%)

EL 789' RS-21-11,-12, 2-1S1-465 nro

- 13,-14 6-15 (MULTIPLE STREAMS) l 30-2MS-2 V,UT 5 Valvei 5 Valves 3 Valves TWO(1)

EL 759' RS-21-16 -17, 2-151-478 j

THREE(2)

-18,-19, 6 20 12-1 3/8"-9-BOLTS RHR DISCHARCE i

u 6-2RH-108 V,UT 1 Valve 1 Valve 1 Valve ONE (100%)

EL 713' 2-88035 2-ISI-54 (MULTIPLE u

6-2RH-12 V,UT 1 Valve 1 Valve EL 712' 2-8803A 2-151-56 STREAMS) l 12 BOLTS 1

ACCUMULATOR DISCHARCE 12-2SI-29A V,UT 1 Valve 1 Valve 1 Valve THREE (100%)

EL 698' 2-8800A 2-1S1-75 l

12-2SI-298 V,UT 1 Valve 1 Valve EL 698' 2-88005 (MULTIPLE STREAMS) j 16-1 7/8"-9-BOLTS

.' WILL BE PERFORM-i ED AS A MINIMUM ON 10% OF THE BOLTS l

(WITH A MINIMUM OF i

2) j C4.3 C-E-1 INTEGRALLY WELDED SUPPORTS S

NONE (UNDER 2.5) i C4.4 C-E-2 SUPPORT COMPONENTS V

NONE (UNDER 2.6) b I

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O ASME Section XI Pressure Testing Program - Unit No. 2 ASME Code Edition and Addenda: 1974 Edition through and including Summer 1975 Addenda Program Period: April 21, 1978 through December 21, 1984 The system Code Class boundaries are established on the attached ASME Code Classification Drawings, Sheets 2 through 40.

The Pressure Test Program for the Class 1, 2 and 3 systems is as follows:

ASME TEST

' TEST TEST SPECIFICATION REQUEST FOR RELIEF CODE CLASS TYPE FREQUENCY Leakage Refueling IWB-5210(a)

  1. 20, #60, IWB-5221 "4

IWA-5000

'ilydrostatic 10 years IWB-5210 (b)

  1. 20 IWB-5222 IWA-5000 2

Pressure 3.1/3 years IWC-2412

  1. 19, #20, #29 IWC-2510 IWC-5000 2

Hydrostatic 10 years IWC-2412

  1. 19, #20, #29 IWC-2510 IWC-5210

.h h 3

Pressure 10 years IWD-2410 (b)

  1. 20, #28

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2 2

2 2

2 2

2 2

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2 2

T P

P P

P P

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P P

P P

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P P

P S

S S

S S

S S

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S S

S S

S S

S VT LA B

B B

C C

C C

C C

C C

C C

C C

C VC S

L L

E O

O Y

W V

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L 1

1 2

2 2

2 2

2 L

I I

P 2

2 2

2 2

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P 1

1 1

E V

R R

U 2

2 2

N N

N N

N N

N N

D D

S E

E E

E E

E E

E D()

E H

H N

N N

G G

G G

G G

G G

A A

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E E

E

(

O M

M T

G G

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M M

M M

M M

M 2

C T

T S

T T

T T

T T

T T

2 S

S M

M M

S S

S S

S S

S S

E N

T T

T M

N N

M S

S S

E E

E E

E E

E E

S M

M V

V V

V V

V V

V A

N P

V V

V L

L L

L L

L L

L O

B A

W L

L L

A A

A A

A A

A A

C I

F V

V V

V V

V V

V V

V V

G T

P P

A P

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O Y

Y Y

Y Y

Y Y

Y Y

Y Y

I O

O D

T T

T T

T T

T T

T T

T R

L L

T E

E E

E E

E E

E E

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Sp C

F F

F F

F F

F F

F F

F S

2 1

2 A

A A

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2 E

2 2

2 S

S S

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S S

2 D

7 7

7 7

7 7

7 7

7 7

7 7

7 7

7 7

3 3

3 3

3 3

3 3

3 3

3 3

3 3

3 3

O N

7 6

5 1

2 3

6 7

7 8

9 0

1 2

1 1

6 1

1 1

?

1 1

1 1

1 1

2 5

5 E

1 1

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1 1

1 1

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1 2

1 1

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3 3

2 2

2 2

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2 2

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V V

V V

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M C

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R R

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ARCA 9

9 9

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1 1

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2 9

9 9

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F F

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O ASME CODE VALVES SYSTEM FLOW DIAGRAM VALVE NO.

- DESCRIPTION VLV TEST PROC FO EF CAT

^

CA NF-39252 CV-31939

, 18 B

SP-2090 E

N

  1. 18 C

S PI E SO 22 C CA NF-39252 CV-31940 18 B

SP-2090 E

M

  1. 18 C

ST IE S CA NF-39252 2CA-11-1 18 C

SP-2153 E

CS

  1. 5 C

S E

CA NF-39252 2CA-7-1 18 VACUUM BREAKER AT STANDPIP E C SP-2152 E

q

  1. 17 CA NF-39252 2CA-7-2 18 VACUUM BREAKER AT STANDPIP E C SP-2152 E

Q

  1. 17 CA NF-39252 2CA-1-1 18 CV-31939 INLT ISOL E

C1.2 L

CS CA NF-39252 2CA-1-2 18 CV-31939 OUTLET ISOL E

C1.2 L

CS CA NF-39252 2CA-1-3 18 CV-31940 INLET ISOL E

C1.2 L

CS w

'c.

CA RF-39252 2CA-1-4 18 CV-31940 OUTLET ISOL E

C1.2 L

CS l

DE:

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Q

19. REQUEST FOR P.ELIEF PACE OF ASME COMPONENT FUNCTION Code Viv Class Cat ALL CLASS 2 COMPONENTS PRESSURE RETAINING 2

CODE REQUIRDIENT The system pressure t"sts will not be conducted as required by the 1974 Edition through and iteluding the Summer 1975 Addenda of the ASME XI Code.

BASIS The 1974 Edition Summer 1975 Adden,da,does not address examination frequency or pressure requirements for Class 2 systems.

ALTERNATE INSPECTION (TESTING)

T U

All components will be pressure tested in accordance with 1977 Edition through and including'the Summer 1978 Addenda of the ASME Section XI Code with exceptions as listed below.

m EXCEPTIONS 1.

The examination method for the IWC-5221 & IWC-5222 Test will be in accordance with the 1974 Ed O

through 1975 Summer Addenda.

s" 2.

For those Class 2 systems whfch are in continuous operation and where no function test is performed the in service operation pressure shall be the test pressure.

e y

SCHEDULE FOR IMPLDIENTATION w-u January 1, 1982 g

z os W

o o

o 1

29.

REQUEST FOR RELIEF ASP E 4

COMPONENT

~ FUNCTION Code Viv Class Cat Safety Injection Piping unisolable from Class 1 Pressure Retaining 2

piping (Sheet 33) l Reactor Coolant System Piping 3/4" & smaller that Pressure Retaining 2

is unisolable from Class 1 Piping (Sheet 30) j l

Residual Heat Rc.moval System piping unisolable from Pressure Retaining 2

Class 1 Piping (Sheet 33)

RCP Seal Injection piping 3/4"~& smaller that is Pressure Retaining 2

unisolable from Class 1 Piping (Sheet 31)

RCP Seal Return piping unisolable from Class 1 Pressure Retaining 2

(Sheet 31)

Charging Line piping unisolable from Class 1 Pressure Retaining 2

yg

-(Sheet 31) h Sample System piping unisolable from Class 1 Pressure Retaining 2

(Sheet 30)

CODE REQUIREMENT 5

Portions of the Class 2 piping will not be tested at the pressures required by IWC-5000.

BASIS The piping is not isolable from the Class 1 piping.

ALTERNATE INSPECTION (TESTING)

The piping will be tested to the Class 1 requirements, i. e.:

1. The unisoisted portions of the Class 2 piping will be visually examined for evidence of leakage at 9 :e the system nominal operating pressure in accordence with the requirements of IWB-5221. Ihe inspection i

DE will be performed prior to startup following each reactor refueling outage.

y

2. The unisolcted portions of the Class 2 piping will be hydrostatically tested when the Class 1 piping

-g is tested.

'SCHEDUIE FOR IMPIEMEPTIATION i

j January 1, 1982

= -.

O O

O 39.

REQUEST FOR RELIEF ASME y

COMPONENT FUNCTION CODE VLV CLASS CAT 2VC-8-6 22'RCP Seal Line Check Close to isolate failure in seal in-jection line.

1 C

2VC-8-7 21 RCP Seal Line Check Close to isolate failure in seal in-jection line.

1 C

CODE REQUIREMENT The valves will not be exercised at cold shutdown as required by IW-3520(b).

BASIS U

Installation of the valve is such that it cannot be adequately exercised during normal plant operation.

Isolation of the valve for exercising requires removal of the RCP seal injection line from service.

ALTERNATE INSPECTION ( TESTING)

The valves will be exercised during refueling outages when plant conditions are more appropriate for a test of this type.

50' SCHEDULE FOR IMPLEMENTATION U

Refueling outage subsequent to April 21, 1978.

6 d.3 M.-.

A2

~$

I l

O O

O 45.

REQUEST FOR RELIEF CODE PROGRAM CODE EXAM COMPONENT OR ITEM CLASS TABLE ITEM CATEGORY REGENERATIVE IIEAT EXCHANGERS 1

1.3.2 B3.1 B-B EXCESS LETDOWN IIEAT EXCIIANGER 1

1.3.3 B3.1 B-B RIIR IIEAT EXCHANGERS 2

2.1.3 C1.1 C-A C1.2 C-B BORIC ACID TANKS 2

2.1.4 Cl.1 C-A i

C1.2 C-B CODE REQUIREMENT Ultrasonic examinations shall be conducted in accordance with Appendix I of Section XI or the provisions of p

Article 5 of Section V.

Y BASIS The design requirements for these heat exchangers and tanks resulted in relatively thin wall vessels which permitted them to be fabricated from piping components or thin plate. Therefore, the ultrasonic examination procedure for pipe welds would be more applicable than these for heavy wall vessels.

ALTERNATE The ultrasonic examination procedures will comply with Appendix III of the 1974 Edition through the Summer 1976 Addenda of ASME Section XI.

SCIIEDULE FOR IMPLEMENTATION y

D April 21, 1978

$5z os l

l

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j 46.

REQUEST FOR RELIEF l

CODE PROGRAM CODE EXAM COMPONENT OR ITEM CLASS TABLE ITEM CATEGORY SAFE END TO PIPING 1

1.4 B4.1 B-F CIRCUMFERENTIAL AND LONGITUDINAL PIPEWELDS 1

1.4 B4.5 B-J BRANCH PIPE WELDS 1

1.4 B4.6 B-J l

INTEGRALLY WELDED SUPPORTS 1

1.4 B4.9 B-K-1 l

CIRCUMFERENTIAL BUTT WELDS 2

2.2.1 C2.1 C-F/C-G j

LONGITUDINAL WELD JOINTS IN FITTINGS 2

2.2.2 C2.2 C-F/C-G j

BRANCH PIPE TO PIPE WELD JOINTS 2

2.2.3 C2.3 C-G l

I CODE REQUIREMENTS F

Ultrasonic examinations shall be conducted in accordance with Appendix I of Section XI or the provisions of Article y

5 of Section V.

N BASIS Appendix I of Section XI is not applicable to most of these piping welds due to the size and mate ~ial limitations of Appendix I.

And the use of side drilled holes to establish a distance amplitude correctivn * ~M curve, as required by Article 5 of Section V, results in an instrument gain setting which greatly impair.

.e examiner's ability to detect and to interprete indications by producing a much lower signal-to-noise ratio and decreases the usable DAC range.

ALTERNATE l

l The rules of Appendix III, including Supplement 7, of the 1974 Edition through the Summer 1976 Addenda of ASME j

Section XI will be used for the ultrasonic examination of pip'ing welds and welds in components fabricated from pipe.

The evaluation of indications will comply with the rules of the Summer 1975 Addenda of Section X7.

4 y

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ad P-4 4

N C/3 3y SCHEDULE FOR IMPLEMENTATION 55 i

m 4

April 21. 1978 i

i

s l

47.

REQUEST FOR RELIEF CODE PROGRAM CODE EXAM

{

COMPONENT OR ITEM CLASS TABLE ITEM CATEGORY l

l REACTOR COOLANT DUMP 1

1.5 B5.4 B-K-1 l

INTEGRALLY WELDED SUPPORTS CODE REQUIREMENT i

Perform volumetric examination of the integrally welded support attachments.

1 i

BASIS

}

p Present ultrasonic examination methods would be ineffective because of the weld joint geometry and the heavy wall, austentic stainless steel cast structure of the pump. 'aody and lugs, u

i O

)

ALTERNATE 1

If a proven volumetric examination technique is developed an attempt will be made to examine these welded supports.

j if a volumetric examination technique is not developed, a surface examination will be performed on the

However, I

weld to the extent possible.

SCHEDULE FOR IMPLEMENTATION April 21, 1978

!3 1 G

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48.

REQUEST FOR RELIEF CODE PROGRAM CODE EXAM COMPONE1.T OR ITEM CLASS TABLE ITEM CATEGORY REACTOR COOLANT PUMPS FLANGE AND SEAL HOUSE BOLTING 1.5 B5.1 B-G-1 B5.2 B-G-1 STEAM GENERA'IOR MAIMAY BOLTS 2

2.1.1 Cl.4 C-D ACCUMULATOR MANWAY BOLTS 2

2.1.2 Cl.4 C-D RIIR IIEAT EXCIIANGER FLANGE BOLTING 2

2.1.3 Cl.4 C-D BORIC ACID TANK MANWAY BOLTS 2

2.1.4 C1.4 C-D PIPING PRESSURE RETAINING BOLTS 2

2.2.4 C2.4 C-D PUMP PRESSURE RETAINING BOLTS 2

2.3 C3.2 C-D VALVE PRESSURE RETAINING BOLTS 2

2.4 C4.2 C-D g

CODE REQUIREMENTS h

a Ultrasonic examinations shall be performed in accordance Lith Article 5 of Section v when the provisiens of o

Appendix I of Section XI do not apply.

Section V requires that calibration be established on a test bar that has certain physical and chemical parameters.

BASIS The Section V technique utilizing the calibration test bar was not used for the baseline examinatiens and it is not as sensitive to detect discontinuties as the presently applied back reflection method.

In addition, when using the back reflection method, the poorer the end reflecting surfaces (painted, corroded, etc.) the more conservative the examinations are.

ALTERNATE yg The items will be examined using the back reflection method correlated with an as built sketch of the particular DQ bolt or stud being examined. ASME Section XI will be used for evaluation criteria.

O

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-. o Z

SCIIEDULE FOR IMPLEMENTATION m

April 21, 1978

o o

o 52.

REQUEST FOR RELIEF l

COMPOMENT OR ITEM CODE PROGRAM CODE EXAM CLASS TABLE ITEM CATEGORY l

i NON-WELDED SUPPORT COMPONENTS 1

1.4 B4.10 B-K-2 2

2.2.6 C2.6 C-E-2 3

IND-2600 (c)

CODE REQUIREMENT l

Examination Category B-K-2 and C-E-2 of ASME bection XI requires all areas of the support comoonent from the piping, valve, and pump attachment to at.d including the attachment to the supporting ctructure be t<amined.

l f3 BASIS Y

l g

Insulation will not be removed for visual examination provided that all mechanical connections and welds can ba

~

examined.

It has been our experience that any loss of support capability or inadequate restraint can usually j

be detected through the inspection of the uninsulated portion of the support and the surrounding insulation.

The governing Codes and Regulations used in the design and construction of those systems that are now classified as Class 2 and 3 did not require provisions for inspection access for thase systems. Thus, it would be an uhdus burden without compensating increase in safety to require insulation removal for support inspection.

1 ALTERNATIVE i

The insulation will be removed from a supported component for further inspections whenever the' connections and

~

welds can not be examined or an abnormality is detected that may have been a result of a loss of support capability or inadequate restraint.

i i

SCHEDULE FOR IMPLEMENTATION N :xs

g April 21, 1978

' 01 5 m-ms o 2

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56.

REQUEST FOR RELIEF CODE PROGRAM CODE EXAM COMPONENT OR ITLM CLASS TABLE ITEM CATEGORY SAFE END TO PIPING 1

1.4 B4.1 B-F CIRCUMFERENTIAL AND LONGITUDINAL PIPE WELDS 1

1.4 B4.5 B-J CIRUHFERP.NTIAL BUTT WELDS 2

2,.2.1 C2,1 C-F/C-G LONGITUDINAL WELD JOINTS IN FITTINGS 2

2.2.2 C2,2 C-F/C-G BRANCH PIPE TO PIPE WELDS 2

2.2.3 C2.3 C-G RHR HEAT EXCIIANGERS 2

2.1.3 C1.1 C-A l

C1,2 C-B l

BORIC ACID TANKS 2

2.1.4 Cl.1 C-A l

C1.2

.C-B l

1 I

f CODE REQUIREMENT Y

When using Appendix III of ASME Section XI Summer 1976 Addenda the basic calibration blocka shall be made from r

material of the same nominal diameter as those to be examined.

BASIS A flat basic calibration block may be used in lieu of a block essentially the same curvature for components greater than 2U inches in diameter.

Any difference in accuracy and sensitivity for ultrasonic examination when using a flat basic calibration block verses a curved basic calibration blocks, for components greater than 20 inches in diameter is within the accuracy of the test.

NSP believes that compliance with Appedix III requirements for basic

~

calibration block curvature would be an undue burden with no increase in public safety.

ALTERNATIVE 7,

For surface curvature, the rules of Article 5 of Section V,1974 Edition thr0 ugh Summer 1975 Addenda, will apply

$s for examination of pipe welds and welds in components fabricated from piping, In addition, the other requirements Es $

of Appendix III for basic calibration blocks will be met.

rag SCHEDULE FOR IMPLEMENTATION April 21, 1978

4 63.

REQUEST FOR RELIEF CODE PROGRAM CODE EXAM COMPONENT OR ITEM CLASS TABLE ITEM CATEGORY REACTOR COOLANT 1

1.5 B5.6 B-L-1 PUMP CASING WELDS CODE REQUIREMENT Volumetric examination of the pump casing weld at or near the end of the inspection interval.

1 BASIS p

Present ultrasonic examination methods would be ineffective because of the' heavy wall, austenitic stainless s' eel u

cast structure of the pump body.

u CD ALTERNATE If a proven volumetric examination technique (ultrasonic or radiograpy) is developed, an attempt will be made to l

examine this weld when pump is disassembled near the end of the inspection interval.

If a volumetric inspection technique is not developed, a surface examination will be performed on the weld to the extent possible.

i i

SCliEDULE FOR IMPLEMENTATION 1

l September 30,.1981

, N 23 Dk lG l$ 5=

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L) i

64. REQUEST FOR RELIEF i

CODE PROGRAM CODE EXAM COMPONENT OR ITEM CLASS TABLE ITEM CATEGORY l

REACTOR VESSEL SAFETY INJECTION 1

1.1 Bl.4 B-D NOZZLE TO VESSEL WELDS CODE REQUIREMENT i

The 1974 Edition through the summer 1975 Addenda of ASME Section XI requires a minimum and identified a maximum percentage of examinations that are to be completed by the expiration of ear h of the three inspection periods.

l l

l BASIS u

L The Safety Injection nozzle to vessel welds (2) will.not be exauined in accordance with this schedule. The i

Oi Westinghouse reactor vessel inspection tool will be used to perform these examinations, and to date, they have.

been unable to develop a reliable inspection head for these small injection nozzles.

The inspection head is now designed to house contact ultrasonic transducers.

This design will allow a very minimum variation in,. alignment between the core barrel and the vessel nozzle, and also in the cladding variation on the nozzle inside diameter.

i ALTERNATE i

4 j

Both safety Injection nozzle to vessel welds will be examined at the end of the ten year interval when the core barrel is removed.

c 4

4 SCHEDULE FOR IMPLEMENTATION September 30, 1981

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EOTION 3 PROPOSED TECHNICAL C/ECIFICATION CHANGES if Pmposed Schnical Specification changes to require inservice

\\

inspection 2nd testing'for Unit No.1 and common components to confom to 10 CFR 50, Section 50 55a(g) were submitted in a License Amendment Bequest dated October 15, 1976. Pmposed Technical Specification changes to require inservice inspection and testing for Unit No.2 components to confom to 10 CFR 50, Section 50.55a(g) were submitted in a License Amesament acquest lated October 12, 1977

'ahe Tech'..ical Specification changes we have proposed are re-produced in this Section to assist in review of.our inservice tnspection a.d testing prog mm.

Technical Specif6cion changes related to the Section XI Inservice Testing portion of the program have not yet been approved by the Cossaission.

Changes that still must be iseued are indicated by sidelines.

wa l O

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I O

31 REVISION 6 7/31/81

-. =

TS.4.1-1 4.0-SURVEILIANCE REQUIREMENTS Specific time intervals between tests may be adjusted plus or minus (q -

25% to acconnodate normal test schedules with the exception that, the 4

intervals between tests scheduled for refueling shutdowns shall not exceed two years.

In addition to other specified testing, testing of ASME Code Class 1, Class 2, and Class 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Presourc Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where relief has been granted by the Comunission pursuant to 10 CFR 50, Section 50.55a(g)(6)(1).

4.1 OPERATIONAL SAFETT REVIEW Applicability Applies to items directly related to safety' limits and liml. ting conditions for operation.

Objective To specify the minimum frequency and type of surveillance to be applied to plant equipment and conditions.

Specification A.

Calibration, testing, and checking of instrumentation channels and testing of logic channels shall be performed as specified in Table TS.4.1-1.

B.

Equipment tests shall be conducted as specified in Table TS.4.1-2A.

C.

Sampling tests shall be conducted as specified in Table TS.4.1-2B.

D.

Whenever the plant condition is such that a system or component is not required to be operable the surveillance testing associated wit * %at system or co=ponent may be discontinued. The asterisked items l

Tables 4.1-1, 4.1-2A, and 4.1-2B cre required at all times, hovi

.r.

Discontinued surveillance tests shall be resumed less than one test interval before establishing plant conditions requiring operability of the associated system or component, unless such testing is not pr'icticable (i.e. nuclear power range calibration cannot be done prior to reaching power operation) in which case the testing vill be resumed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of attaining the plant condition which permits testing to be accomplished.

i Basis channel Check Failures such as blown instrument fuses, defective indicators,

{

faulted an.plifiers which result in " upscale" or "downscale" l

indication can be easily recognized by simple observation of the i

functioning of an instrument or system.. Furthermore, such failures are, in many cases, revealed by alarm or annunciator action, and a check supplements this type of built-in surveillance.

i V

Based on experience in operation of both conventional and nuclear plant cystems, when the plant is in ooeration, the minimum checking frequencies set forth are deemed adequate for reactor and steam

[

i system instrumentation.

REVISION 6 3-2 7/31/81

TS.4.1-IA MINIMUM FREQUENCIES FOR EQUIPMENT TESTS FSAR Section Test Frequency Reference 1.

Control Rod Assemblies Rod drop times All rods during each 7

of full length refueling shutdown rods or following each removal of the reac-tor veneel head; affected rods following maintainance on or modification to the control rod drive system which could affect performance of those specific rods la. Reactor Trip Breakers Opcen trip Monthly 2.

Control Rod Assemblies Partial move-Every 2 weeks 7

ment of all rods 3.

Pressurizer Safety Set point Per ASME Code,Section XI, Valves Inservice Testing Program 4.

Main Steam Safety Set point Per ASME Code, Sectiot. XI, Valves Inservice Testing Program 5.

Reactor Cavity Water level Prior to moving fuel assemblics or control rods and at least once every day while the cavity is flooded.

6.

(Deleted) 7.

(Deleted) l 8.

(Deleted) 9.

Primary System Leakage Evaluate Daily 4

l

10. (Deleted) l
11. Turbine stop valves, Funec ional Monthly 10 governor valves, and intercept valves.

(Part of turbine overspeed protection.)

12. (Deleted)

.;r~s NOTES:

  • See Specification 4.1.D.

l 3-3 REVISION 6 l

7/31/81

TS.4.2-1 O

4.2 INSERVICE INSPECTION REQUIREMENTS Applicability Applies to in-service structural surveillance of the reactor coolant pressure boundary and other systems important to safety.

Objective To assure the continued integrity of the reactor coolant pressurt boundary and other systems important to safety.

Specification A.

Inspection Requirements Inservice inspection of ASME Code Class 1, Class 2, and Class 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where relief has been granted by the,Coasmission pursuant to 10 CFR 50, Sectica 50.55a(g)(6)(i). The additional inspections listed in Table TS.4.2-1 shall also be performed as specified.

O O

3-4 REVISION 6 7/31/81

e TS.4.2-2 O

B.

Corrective Meisures 1.

The source of any reactor coolant leakage detected by the examinations of-'4.2.A above shall be located by the removal of insulation where necessary -and the following corrective measures applied:

)

(a) Normally expected leakage from component parts (e.g.,

valve stems) shall be sinimized by appropriate repairs and maintenance procedures.

Where such leakage may reach the surface of ferritic components of the reactor coolant pressure boundary, the leakage shall be suitably channeled for collection and disposal.

(b) Leakage from through-wall flaws in the pressure-retaining membrane of a component shall be eliminated, either by corrective repairs or by component replacement.

Such repairs shall conform to the requirements of Section XI -

of the ASME Code.

2.

In the event boric acid residues are detected by th e examina-tions specified above, insulation from ferritic steel components shall be removed to the extent necessary for examination of the component surf aces wetted by reactor coolant leakage to detect evidence of corrosion. The following corrective measures shall be applied:

)

(a) An evaluation of the effect of any corroded area upon I

the structural integrity of the component shall be performed in accordance with the provisions of Section XI of the ASME Code.

(b) Repairs of corroded areas, if necessary, shall be performed in accordance with the procedures of Section XI of the ASME Code.

1

-O REVISION 6 3-5 7/31/81 i

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TS.4.2-3 3.

The structural integrity of the primary system boundary shall be maintained at the level required by the original acceptance standards throughout the life of the plant.

Any evidence as a result of the inspections required in 4.2.A that defects have initiated or grown, shall be investigated, including evaluation of comparable areas of the primary system. In the event further unacceptable structural defects are revealed, all remaining system components or piping in.this category shall be examined to the extent specified in that examination category.

C.

Records Records and reports of inservice inspection of ASME Code Class 1, Class 2, and Class 3 components shall conform to Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where relief has been granted by the Commission pursuant to 10 CFR 50, i

Section 50.55a(g)(6)(i).

O I

~

lO 3-6 REVISION 6 i

l 7/31/81-

s e

TS.4.2-4 Basts The inservice inspection program for the Prairie Island plant conforms tc the requirements of'1'O CFR 50, Section 50.55a(g). Where practical the inspection of ASME Code Class 1, Class 2, and Class 3 components is performed in accordance with Section XI of the ASME Code.

If a code required inspection is impractical for the Prairie Island facility, a request for a deviation from that requirement is submitted to the Commission in accordance with 10 CFR 50, Section 50.55a(g)(6)(i).

Deviations which are nee (ed from the procedures prescribed in Section XI of the ASME Code and applicable Addenda will be reported to the Commission prior to the beginning of each 10 year inspection period if they are known to be equired at that time. Deviations which are identified during the course of inspection will be reported quarterly throughout the inspec-tion period.

O i

1 i

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37 REVISION 6 7/31/81 e -

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Table TS.4.2-1 SPECIAL INSERVICE INSPECTION REQUIREMENTS Component Method of Extent and Examination Frequency REACTOR COOLANT PUMPS 1.

Pump Flywheel U.T.

An in place ~ ultrasonic volumetric examination of the areas of higher stress concentration at the bore and key way at approx. 3 year intervals, during the refueling or maintenance shutdown coinciding with the in-service inspection schedule as required by the ASME B & PV Code Section II.

P.T.

A surf ace examination of all exposed U.T.

surfaces and complete ultrasonic volumetric examination at approx.

10 year intervals, during the plant shutdown coinciding with the in-service inspection schedule as required by the ASME B & PB Code Section XI.

Removal of the fly-wheel is not re.luired to perform these examinations.

Notes:

1.

The following definitions shall apply to the inspection methods employed in Tabel TS.4.2-1.

a.

U.T. - Ultrasonic examination per paragraph IS 213.2.

b.

P.T. - Liquid Penetrant examination per paragraph IS 212.2.

O REVISION 6 3-8 7/31/81 l

1 l

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