ML20079D361

From kanterella
Jump to navigation Jump to search
Requests Relief from Requirements of ASME Section XI Number I-00010 Rev 4 Re Volumetric & Surface Exams of Welds
ML20079D361
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 07/03/1991
From: Cottle W
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GNRO-91-00112, GNRO-91-112, NUDOCS 9107110260
Download: ML20079D361 (16)
v • d • e


Text

&.____

9 ENTERGY

""' "" 7 " "" " ' "" * '

w~

?

> i tr l

W. T. Cottle July 3, 1991 1

U.S. Nuclear Regulatory Commission Mail Station P1-137 Washington, D.C.

20555 Attention:

Document Control Desk Subject Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 ASME Section XI Relief Request Number 1-00010 Revision 4 GNRO-91/00112 Gentlemen:

This submittal requests relief from the requirements of ASME Section XI, in accordance with 10CFR50.55a(g)(5)(iv) and 10CFR50.55a(g)(6)(i).

A revision of the previously approved relief request is attached.

Relief Request 1-00010 Revision 4 addresses welds which require relief for volumetric and surface examinations.

In addition t o these new items, notes were added to items previously approved in Revision 3.

These notes indicate welds not subject to hydrostatic testing.

Changes to Table 1 of the previously approved relief request are summarized in Attachment 1.

Your review and approval of these requests is requested prior to January-1, 1992, in order to allow for planning of the upcoming refueling outage, which is scheduled for April 1992.

If additional Information is required to support your review, please advise.

Yours truly, e :) P W.

WTC/JE0/mtc attachments: 1.

Summary of Revision 4 Changes 2.

Relief Request Number I-00010 Revision 4 cc:

(See Next Page)

I

- d. ( A G9106262/SNLICFLR - 1

\\,lj \\ { i C' I 9107110260 910703 PDR ADOCK 05000416 I'

g P

PDR

July 3, 1991 GNRO-91/00112 Page 2 of 3 cc:

Mr. D. C. Ilintz (w/o)

Mr. J. L. Mathis (w/a)

Mr. R. B. McGehee (w/o)

Mr. N. S. Reynolds (w/o)

Mr.11. L. Thomas (w/o)

Mr. F. W. Titus (w/a)

Mr. Stewart D. Ehnet er (w/a)

Regional Administrator U.S. Nuclear Regulatory Commission Region Il 101 Marietta St.,

N.W.,

Suite 2900 Atlanta, Georgia 30323 Mr. L. L. Kintner, Project Manager (w/a)

Of fice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mall Stop 11D21 Washington, D.C.

20555 G9106262/SNLICFLR - 2

- _ - _ _ _ _ _ _ _ _ _ to GNRO-91/00112 Page 1 of 1 Summary of Revision 4 Changes - Relief Request 1-00010

" Inservice Examination of Propsure Retaining),' elds" Relief Request Revision 4 Change Item No.

Requ_es t es!

Reason _for ChangelComments 8

Correct Item No. 8 pipe size is I)eser Ipt ion corrected to 24" 72 & 73 Add Items Rollef is requested to permit partial examination for these welds 3,13,14,15 and Add Items Notes were added to indicate 21672 that these welds are not subject to hydrostatic testing G9106262/SNLICFLR - 4

.-.____.._.._._.....s_._

.. _. _....... _ _ _ _ _.... ~..

_ __ _ _.. to GNRO-91/00112 Page 1 of 13 l

.l Relief Request Number I-00010 Revision 4

" Inservice Examination of Pressure Retaining Wolds" Pages Following:

~ 4 Pages Relief Request - Revision 4-8 Pages

-Table 1 Reviston 4 J

' G9106262/SNLICFLR - 5.

. - _ _ _ _., _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - - _ _ _ _ - -. - _ _ = _ =

GRf.ND GULF NUCLEAR STATION Incorvico Incp3ction ROquirOmOnto Section 4 l

INSERVICE INSPECTION e h R g est 1

TEN YEAR PROGRAM GRAND GULF NUCLEAR STATION UNIT 1 REL1EP REQUEST I-00010, REVISION 4 PAGE 1 OF 4 INSERVICE EXAMINATION QE EBESSURE RETAINING WELDS I.

Component:

Inaccessible portions of ASME Section III, Class 1

and 2

pressure retaining and integral attachment piping wells listed in table 1 (see attached).

II.

Code:

These portions of the pressure retaining and integral attachment piping welds were designed and fabricated to ASME Section III, clanc 1 and Class 2 requirements.

Applicable inservice inspections are to be performed in accordance with the ASME Section XI, 1977

Edition, through and including the Summer 1979 Addenda.

III.

Code Requirements:

Class 1 and Class 2 pressure retaining piping welds are required to be volumetrically and surface

examined, essentially 100% of the weld, once every ten year interval in accordance with ASME Section XI, Table IWB-2500-1, Category B-J, Table IWC-2500-1, Category C-F.

The Class 1 integral attachment welds depicted in table 1 are required to be surface examined once each ten year interval in accordance with ASME Section XI, Table IWB-2500-1, Category B-K-1.

IV.

Information to Portions of welds that were preservice support the examined have physical obstructions due to determination that design.

Due to this limited the Code accessibility, it is impractical to requirements are perform the surface and volumetric impractical:

examination for 100%

of the required examination volume as indicated for the welds listed in Table 1.

V.

Specific Relief Permission is requested to perform the Requested:

Code required examinations to the extent described in Table 1.

M:\\ MECH \\ HUNTER \\ RELIEFS \\RR10R4TX.010

i

. GRAND 1 GULF-NUCLEAR-STATION _

Incorvico Incpcotion-.R0guircmento-INSERVICE INSPECTION Section 4 TEN 1 YEAR PROGRAM GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST-I-00010, REVISION 4 PAGE 2 OF 4 JJISERVICE EXAMINATION DE

. PRESSURE RETAINING WELDS VI.

Reasons why relief Request for permission to limit the code should be granted:

required examination to the accessible

. areas should be granted for the following reasons:

^

1.

The inaccessible portions of listed pressure retaining welds were examined by radiography, passed in accordance with ASME Section

III, 1

Class-1 and 2 requirements.

2.

The inaccessible portions of. the pressure

. retaining' and integral attachment-welds were surface examined- (magnetic particle or liquid

-penetrant), passed in accordance with ASME III and/or XI, Class 1 and Class 2 requirements.

3.

The inaccessible portions-of listed piping welds' will be subject to a system leakage test.

after. each refueling outage for Class-1, and each inspection-period for Class 2 in accordance with-ASME Section XI requirements.

4.

The inaccessible portions of listed-piping welds will' be subject. to a system hydrostatic test

. each

-inspection. interval. in :accordance with ASME Section XI, Class'1 1and.2-requirements.

5.

Accessible portions of listed. welds

~

will be volumetrically-. and ' surface examined each; inspection interval in accordance 'with.ASME Section' XI.

Should -indications be -found, an F

engineering evaluation.will : be made to determine if-the-inaccessible portions of the listed welds have been affected.

es

-M:\\ MECH \\ HUNTER \\ RELIEFS \\RR10R4TX.010 a.

.2

GRAND Gulv NUCLEAR STATION Incorvico Inspcction R0quircm nto

~

80ction 4 INSERVICE INSPECTIOtt N

TEN YEAR PROGRAM GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00010, REVISION 4 PAGE 3 OF 4 INSERVICE EXAMINATION 9.E PRESSURE RETAINING WELDS VI.

Reasons why relief 6.

Leak detection is provided, by way of should be granted the leakage detection system with (continued):

continuous monitoring, for the RHR,

RCIC, MS,
RWCU, RECIRC and FW systems.

7.

The failure of any one of these presstre retaining piping welds would have no adverse effect on plant safety as there is isolation capability and/or shut down capability as part of the plant design.

8.

The calculated maximum piping stresses and usage factor at the integral attachments on the piping, including consideration of the local pipe wall

stresses, have been determined in the class 1

stress report and are equal to the following:

a)

Primary plus secondary (equation 10); 32,775 psi (1. 7 2 S,),

b) usage factor is 0.0442.

Circumferential and longitudinal welds in piping with stress levels below 2.4 S, and usage factors below 0.4 are excluded from ISI examinations, in accordance with Table IWB-2500-1 Category B-J.

9.

Examinations at GGNS of category B-J, B-K-1 and C-F welds have not identified any flaws or evidence of service induced degradation.

~

1 M : \\ME CH \\ HUNT ER \\R E L I E F S \\R R 10R4T X. 010

GRAND GULF NUCLEAR STATION InCOrvico Incp;ction R0quircn0nto INSERVICE INSPECTION 82ction 4 e

e equest TEN YEAR PROGRAM GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00010, REVISION 4 PAGE 4 OF 4 INSERVICE EXAMINATION 9E ERESSURE RETAINING WELDS VII.

Alternate testing:

All the wolds identified in Table 1 will be inspected twice by volumetric or surface examination, as applicable, during the 10 year interval as discussed in GGNS Safety Evaluation Report, Supplement #2.

VIII.

NRC discussion "The staff has reviewed the information statement submitted which supports the licensee's (revision 3) :

conclusion that the Section XI ASME Code requirements are impractical for the piping welds identified in Table 1 due to inaccessibility of portions of the welds.

Compliance to the Code requirements would require the redesign and refabrication of the piping system to eliminate physical obstructions due to - pipe supports, pipe

fittings, and components.

The proposed alternative limited volumetric examinations along with the Section XI ASME Code surface examinations and the hydrostatic tests, ensure an acceptable level of inservice structural integrity.

The licensee concludes, and the staff agrees, that' relief should be granted as requested in Relief Request No. I-00010, Revision 3 and the alternative testing imposed." (Reference MAEC-90/0261)

M:\\ MECH \\ HUNTER \\REllEFS\\RR10R4TX.010

+

Inservice Inspection Requirements GRAND'Gutr NUCLEAR STATION Section 4 INSERVICE INSPECTION Rener R e est TEN' YEAR PROGRAM GRAND GULF NUCLEAR STATION j

UNIT:1' RELIEF REQUEST NO. I-00010 REVISION 4 j-TABLE'l EXAMINABLE EXAMINABLE ITEM NO SYSTEM WELD 150 PIPE VOLOMETRIC TYPE SURFACE VELD REASON FOR ND NO NO SIZE COMPONENT AREA SCAN AREA CLASS TYPE LIMITATIONS 1

E12 '

G014-FV RH-8-8 6"

VALVE TO ELBOW 55%

T 100%

1 CIRC ELBOW RADIUS 2

B21 69-CI-B-l/B MS-11-8 28" ELBOW SEAM 38%

T 3F,

1 LONG PIPE RESTRAINT l-3*

ESI G004-9-8-1 RI-8-2 6"

ELBOW TO ELBOW 70%

T 10%

2 CIRC ELBOW RADIUS 4

B21 Gil-DI-B-L/B MS-11-11 28" ELBOW SEAM 38%

T 38%

1 LONG PIPE RESTRAINT 5

B21 G8-Al-B-l/B MS-11-2 28" ELBOW SEAM 38%

T 38%

1 LOMG PIPE GESTRAINT 6

B21 G030-FV-23 FW-8-2 24" VALVE TO PIPE 93%

T

'00%

1 CIRC SOCK-0-LET 7

B21 G030-FW-36 FW-8-4 24" VALVE TO PIPE 93%

T 1001 1

CIRC SOCK-0-LET I

8 B21 5026-FW-17 FV-11-7 24" PIPE TO TEE 93%

T 100%

1 CIRC ~

SOCK-G-LET 9

B21 G001-V4 MS-11-3 2S" VALVE TO PIPE 82%

T 100%

1 CIRC PIPE Rta+kAINT 10 B21 G001-W4 MS-11-9

-28" VALYE TO ELBOV 82%

T 100%

1 CIRC PIPE RESTRAINT 11 B21 G9-CI-B-L/A MS-11-8 28" ELBOV SEAM 38%

T 38%

1 LONG PIPE RESTRAINT DELETE 3

  • Under the rules of IWC-5210(a), this weld is riot subject to system hydrostatic testing. Item 4 under " Reasons why relief should be granted" does not apply to this weld.

Q:\\ MECH \\ HUNTER \\ RELIEFS \\RR10R4TB.010

(._.

n- - -

7 Inservice Inspection Requirements GRAND GULF NUCLEAR STATION 8ection 4 INSERVICE INSPECTION Relief Request TEN YEAR PROGRAM GRAND GULF NUCLEAR STATION UNIT 1

(

RELIEF REQUEST NO. I-00010 REVISION 4 l

f TABLE 1 s

EXAMINABLE EXAMINABLE I

ITEM NO SYSTEM WELD 150 PIPE VOLLMETRIC TYPE SURFACE VELD REASON FOR l

NO NO NO SIZE COMPONENT AREA SCAN AREA CLASS TYPE LIMITATICMS i

13*

E51 G004-7-8-4 RI-8-1 10" REDUCER TO TEE 71%

T 100%

2 CIRC TCE l

14*

E51 G004-7-8-9 RI-8-1 10" REDUCER TO TEE 71%

T 13C%

2 CIRC TEE 15*

ESI G004-7-8-8 RI-8-1 10" REDUCER TO TEE 71%

T 100%

2 CIRC TEE l

16 B33 G024-W2 RR-11-19 4"

ELBOW TO TEE 6?%

T 100%

1 CIRC TEE i

17 G33 G002-W179 CU-8-7 4"

ELBOV TO FITT 63%

T MA 1

CIRC CLBOW RADIUS l

l I

18 E21 G11-01-B-L/A MS-11-11 28" ELBOW SEAM 38%

T 3?T 1

LOMS PIFE RESTRAINT 19 B21 6001-W9 MS-11-12 28" VALVE TO PIPE 82%

T 100%

1 CIRC PIPE RESTRAINT 20 E21 G8-Al-B-L/A MS-11-2 28" ELBOW SE AM 38%

T 36%

1 LONG PIPE RESTRAINT 21*

ES1 0001-VI RI-8-12 6"

VALVE TO ELBOW 73%

T 100%

2 CIRC ELBOW RADIUS 22 E51 G001-W40 RI-11-4 6"

valve TO EtBOW 73%

T 100%

1 CIRC EtBOV RADIUS t

23 B33 G001-W5 RR-11-2 24" ELBOW TO PLMP 73% see note 1 T

100%

1 CIRC PU"?

24 B33 G001-V6 RR-11-2 24" PIPE TO PLAP 53% sae note 1 T

100%

1 CIRC PL*P

'Under the rules of IWC-5210(a), this weld is not subject to system hydrostatic testing. Item 4 urder " Reasons why relief should be granted" dxs not apply to th:s weld.

M:\\ MECH \\ HUNTER \\ RELIEFS \\RR10R4T8.010

GRAND' GULF NUCLEAR STATION

', Inservice Inspection Requirements T

INSERVICE' INSPECTION.

Section 4:

TEN YEAR PROGRAM.

Relief' Request GRAND GULF' NUCLEAR STATION UNIT 1 RELIEF REQUEST'NO. I-00010 REVISION"4' TABLE 1

.EXAMINABLE EXAMINABLE ITEM NO SYSTEM WELD

150 PIPE VOLtNETRIC AREA TYPE SURFACE VELD REASON FOR NO k0 NO SIZE-COMPONENT SCAN AREA CLASS TYPE LIMITATIONS.

25 833 G001-W8 RR-11-3' 24"'

VALVE TO PIPE

~ 50% see note 2' T

100%

1 CIRC V ALVE -

26 B33 G001-V28

.RR-11-9 24" ELBOV TO PUMP

- 62% see rote 1-T 100%

1 CIRC PUMP 27 '

B33 G001-V29 RR-11 '24"-

PUMP TO PIPE 61% see note 1 T

100%

1 CIRC

~ PtMP l

28 B33 G001-V31 RR-11-10 21" VALVE TO PIPE 50% see note 1&2 T

100%

1 CIRC VALVE 29 B33 G5-B1-B PR-11 9 4"/24" SVEEP TO PIPE 59% see note 1 T-100%

1 BRANCH SVEEP-0-LET 30 B33 GS-B1-E RR-11-3 4"/24"-

SVEEP TO PIPE 63% see note 1 T-100%

1 BRANCH SVEEP-0-LET 31 B33 G023-V37 RR-11-15 20" TEE TO PIPE 65% see note 1 T

100%

1 CIRC TEE 32 B33 G024-V8 RR-11 96 4"

PIPE TO SVEEP 50% see note 2 T

100%

1 CIRC SVEEP-0-LET 33 B33 G024-V27 RR-11-17 4"

PIPE TO SEEEP 50% see note 2 T

100%

1 CIRC SVEEP-0-LET

{

34 B33 f'.d-81-L RR+11-11 12"/16"

'SVEEP TO PIPE SC% see note 3 P

100%

1 BRAMCM SVEEP-0-LET l

35 833

-610-B1-K RR-i?

't 12"/16" SVEEP TO PIPE 50% see note 3 P

100%

1 BRANCH SVEEP-0-LET l

36 833 G10-51-J RR-11-11 12"/16" SVEEP TO P!PE 50% see note 3 P

100%

1 BRANCH SVEEP-0-LET l

l:

~

a i

I Q:\\ MECH \\ HUNTER \\ ELIEFS\\RR10R4T8.010 i

t t

Inservice Inspection Requirements GRAND Gulf NUCLEAR STATION Section 4 INSERVICE INSPECTION Relief Request TEN YEAR PROGRAM GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST NO. I-00010 REVISION 4 TABLE 1 7-l EXAMP.Le i EKAMINAELE ITEM NO SYSTEM VELD 150 PIPE t0LUMElk:C TYPE SURFACE kTLD REASON FOR NO NO NO SIZE COMPONENT AREA TAN AREA CLASS TYPE LIMITATIONS

..w-37 B33 G10-B1-H RR-11-11 12"/16" SVEEP TO P:PE 50% see note 3 P

100%

1 BRANCH SkTE P-0-L ET 38 B33 G10-B1-G RR-11-11 12"/16" SVEEP TO PIPE 5;% ee note 3 P

100%

1 BRANCH SkTEP-0-L ET 39 B33 G10-B1-F RR-11-11 12"/16" SVEEP TO P!PE 50% <ee note 3 P

100%

1 BRANCH 3Ep-0-LET 40 B33 G001-V34 RR-11-11 24" PIPE TO CROSS 50% see note 3 P

100%

1 CIRC CROSS 41 B33 G10-B1-A PR-11-11 16" PIPE TO CROSS 50% see note 3 P

100%

1 CIRC CROSS 42

B33, G10-B1-B RR-11-11 16" PIPE TO CROSS 50% see note 3 P

100%

1 CIRC CROSS 43 B24 G8-Al-C MS-11-2 8"/28" SVEEP TO PIPE 100%

T 98%

1 ESANCH PIPE SUPPORT 44 B21 G026-V36 FV-11 ~

24" PIPE TO VALVE 95%

T 100%

1 CUP PIPE S'# PORT 45 B21 G8-Al-L.M N P MS-11-2 28" LUGS TO PIPE N/A N/A 491 1

INT ATT PIPE RESTRAINT 46 B21 G10-B1-L.M,N,P MS-11-f 28" LUSS TO F..'E N/A N/A 49%

1 INT ATT PfPE RESTRAINT 47 B21 G9-CI-l,M N,P MS-11-8 28" LUGS TO PIPE N/A N/A 49%

1 INT ATT P!PE RESTUAINT 48 B21 Gil-DI-L M,N,P MS-11-11 28" LUGS TO PIPE N/A N/A 49%

1 INT ATT PIPE RESTRAINT 1

I l

l M:\\ MECH \\MUNTER\\ RELIEFS \\RR10R4TB.010

Inservice Inspection Requirements GRAND GULF NUCLEAR STATION Section 4 INSERVICE INSPECTION Relief Request TEN YEAR PROGRAM GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST NO. I-00010 REVISION 4 TABLE I I

EXAMINABLE EXAM!NABLE ITEM NO SYSTEM VELD ISO PIPE VDL trETRIC TYPE SURFACE WELD REASON FOR ND NO NO SIZE COMPONENT AREA SCAN AREA CLASS TYPE LIMITATIogs 49 B33 G001W27 RR-11-9 24" FIPE TO VALVE 50% see note 1 T

100%

1 CISC VALVE 50 833 G001W33 RR-11-10 24" VALVE TO P1PE 50% see nete 1 T

100%

1 CIRC VALVE 51 B33 G10-Al-A RR-11-4 16" CROSS TO PIPE 50% see note 3 P

100%

1 CIRC CROSS 52 B33 G10-Al-B RR-11-4 16" CROSS TO P!PE

$0% see note 3 P

100%

1 CIRC CROSS 53 B33 G6-B1-C RR-11-9 4"/24" PIPE TO SWEEP 50% see note 1 T

100%

BRANCH s'.TE P 54 833 G10-Al-F RR-11-4 16"/10" PIPE TO ShTEP 50% see note 3 P

100%

1 BRANCH SWEEP 55 B33 G10-Al-G RR-11-4 16"/12" PIPE TO SZ EP 50% se. note 3 p

100%

1 goA%CH SWEEP E6 B33 610-Al-H RR-11-4 16"/12" PIPE TO SWEEP 50% see ncte 3 P

100%

1 g:AqCH SWEEP 57 B33 G10-Al-J RR-11-4 16"/12" PIPE TO S'=TEP 50% see note 3 P

100%

1 BRANCH SWTEP SS B33 G10-Al-K RR-11-4 15"/12" PIPE TO 56TEP 50% see note 3 P

100%

1 BgAgCH syrEP 59 B33 GIO-Al-L FR-11-4 16"/12" PIPE TO SVEEP 50% see note 3 P

100%

1 BsAgCH 3,7t p 60 B33 G001W4 RR-11-2 24" VALVE TO PIPE 50% see ete 1 T

100%

1 CIRC VALVE I

l

)

l i

M:\\ MECH \\ HUNTER \\ RELIEFS \\RR1024TB.010 l

m...

i GRAND Gulf NUCLEAR STATION Inservice Inspection Requirements 8ection.4

l INSERVICE INSPECTION TEN YEAR PROGRAM GRAND _ GULF NUCLEAR STATION' UNIT l' RELIEF REQUEST NO. I-00010 REVISION 4 TABLE 1

- EXAMINABLE EXAMINABLE ITEH N0' SYSTEM.

' VELD 150

~ PIPE YOLUMETRIC TYPE SURFACE VELD REASCM FOR i

NO '

NO NO -

SIZE COMPONENT, AREA

' SCAN '

AREA CLASS TYPE LIMITATIONS 61 B33 G001V9 RR-11-3 24"-

'P!PE TO VALVE 50% see note 1 T

100%

1 CIRC VALVE l

62 B33 G001V10 RR-11-3 24" VALVE TO PIPE 50% see note 1 T

100%

1 CIRC VALVE 63 B33 G6-Al-C -

RR-11-2 4"/it" PIPE TO SVEEP

'50% see note 1 T

100%

1 BRANCH SVEEP 1

64 B33 GS-Al-C RR-11-2 4*/24"

' PIPE TO SVEEP 50% see note 1 T

100%

1 BRANCH SVEEP i

65 B33

-G5-Al-B RR-11-2 4"/24" PIPE TO SVEEP 50% see note 1 T

100%

1 BRANCH SVEEP 66 B21-G11-01-C MS-11-11 28"/10" PIPE TO SVEEP 57%

T 97%

1 BRANCH HANGER 67

- B21 G10-BI-C MS-11-5 28"/10" PIPE TO SVEEP

'71%

T 100%

1 BRANCH HANGER 68 B21 G10-81-E MS-11-5 28"/10" PIPE TO SVEEP 71%

T 85%

1 ERANCH HANGER 1

69 B21 C10-B1-F MS-11-5 28"/10" PIPE TO SVEEP 78%

T 100%

1 SRANCH HANGER 70 B21 G10-Bi-H MS-11-5 28"/10" P1PE TO SWEEP 78%

T 100%

1 BRANCH HANGER 71 821 G10-B1-G MS-11-5

'28"/10" PIPE TO SWEEP 78%

T 100%

1 BRANCH HANGER 72*

E51 G004V18-RI-8-21 6"

VALVE TG PIPE 83.18%

T 100%

2 CIRC PIPE RESTRAINT-

  • Under the rules of IVC-5210(a), this weld is rot subject to system hydrostatic testing. Item 4 under " Reasons why relief should be granted" does not apply to this weld.

I i

i n:\\ MECH \\ HUNTER \\ RELIEFS \\RR10R4T8.010 I

]

l lla l

3

=..

s R%

e

~

O r

C F

o I

t T

h A

s c T w

S I

A c

M E

s a

R t

L E

/

DE C

LP

=

EY t

WT c

s tnem SS e

A i

r LC iuq t

e A'

s R

EE e

L 4

SM u

A s

n EE c

onq 4

I C o

e MA t

ec I

i oR AF' ti N

XR Et ct' O

.S f

e i

N S

pe I

sS l

O V

EM n

e I

PA E

i I

R T

R TS YC A

e T

0 c

S i

1 0

v R

EC 0

r A

LI e

0 1

SR x

s F. 1 -

1 EE s.

uTA 9

I I

E MtpM 1

n CT s

L AL e

I UI K0 B

Ev~

NN O A

U F

N T

LU T

w S

c G

E s

TN tE D

U i

O E

M Q

C N

P T

A E

M t

R R

O y

C t

G F

vA E

I 4l_

L EE E

FZ s

R II PS 3

1 N

0 S 1

5 O

M 1

1 I

v TN t

AO I

TI M STACR 4

REG D

s APO LO u

0 ER i

1 ESR W

0 c

LNP s

B CI T4 U

R E

NEA 0

1 CE R

M R

FIY E

\\

3 LV TO 1

3 SM c

URN Y

9 S

8 GEE 4

ST M

\\

DN S

I NI M

W EO 3

E A

TN 7

L R

\\H G

l' C

EM

\\:

-,i M

l

]

1,!,

hl 1'I 4

!l1lil l

31 l

!!3I!!

!i i1!

~

Insenice Ir.spection Requirements GRAND GULF NUCLEAR STATION Section 4 INSERVICE INSPECTION e

egest TEN YEAR PROGRAM GPJdiD GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST NO. I-00010 REVISION 4 TABLE 1 LEGEU:

P = SCA9 N ALLEL TO T T VELO T = SU 4 T A4GE ET (FEEPESCICULAPI TO THE WELD OTES:

t%se==1ds are aw; e-ted by t*e recairmts cf UEG C213 and tMeefc-e e-e erre ed =tte a p=ra t tei scan that is 1.

In a&Jition to the ~T" scan limitatica, is limited to me side of tN weld (SO) due to tN fitti-gs bet 7 Jcieed by tM==1d.

et required by ASME Sactica XI.

The -arallel scan 1001 coverage was obtaiW m em directico eniy, usi~; ref-acted ic gitudieal = eve.

2 1 W tatim.

is perfowd for cerclieve with UEG C313.103 ef A5wE Section XI ceveeege is atta tmed.it%t 3.

The "F" scaa a

M s VtECM\\tatt sve489-7.zR f CR 4t s.010 i

_.

Retrieved from "https://kanterella.com/w/index.php?title=ML20079D361&oldid=4388621"