Text

Rev 3 to 80A8613, Inservice Insp Program Plan,Rhr Sys, Shoreham Nuclear Power Plant Unit 1. W/Two Oversize Drawings
	ML20196A901
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	01/25/1988
From:	; NUCLEAR ENERGY SERVICES, INC.
To:	;
Shared Package
ML20196A839	List: ML20196A841; ML20196A847; ML20196A866; ML20196A877; ML20196A881; ML20196A901; ML20196A908; ML20196A918; ML20196A930; ML20196A936; ML20196A947; ML20196A960; ML20196A977; ML20196A991; ML20265C912; ML20265C917; ML20265C922; ML20265C927; ML20265C932; ML20265C936; ML20265C940; ML20265C945; SNRC-1414, Forwards Rev 4 to Inservice Insp Program,Incorporating Provisions to Inspect Class 2 Welds Per ASME Code Case N-408 & Relief Requests for Insp of Containment Penetration Flued Head Welds;
References
	80A8613, NUDOCS 8802050199
	Download: ML20196A901 (94)
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.

M NUCLEAR ENERGY SERVICES DOCUMENT NO. 30A8613 REV. 3 I

OF IN PAGE _

v INSERVICE INSPECTION PROGRAM PLAN i

RESIDUAL HEAT REMOVAL SYSTEM SHOREHAM NUCLEAR POWER PLANT UNIT I Prepared For LONG ISLAND LIGHTING COMPANY (O)

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p ggg REVISION LOG NUCLEAR ENERGY SERVICES, INC.

PAGE 80A8613 OF,,

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y DATE DESCRIPTION APPROVAL 1 7/10/84 -

See CRA 4456 Revision includes 6 g lp editorial changes and the addition of new information 2 5/8/S5 ll, figures 8613-7, 11, 20, 21 l f See CRA 5304. (([4 ((] ,, [

3 1/25/88 8 0,12-14 see CRA 6730 M 6,h l

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DOCUMENTNO._ "A % "

NUCt. EAR ENERGY SERVICES O TABLE OF CONTENTS PAGE

1. INTRODUCTION 4

2. CLASSIFICATION 4 1

3. EXEMPTIONS 4

4. EXCEPTIONS 6

5. CALIBRATION STANDARDS 11

6. PROGRAM PLAN AND SCHEDULE 11

7. PRESSURE TESTS L3

3. ISOMETRIC FIGURES AND SKETCHES 13

9. AUGMENTED REQUIREMENTS 14 Tables 3-1 Exemptions 4 4-1 Exceptions 6 5-1 Calibration Standards 11 6-1 Section XI Examination Schedule 12 S-1 Isometric Figures 13 Appendix A l

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l l FORM s NES 205 2/80

., DOCUMENT NO. SOA8613

" GE 4 op. M NUCt. EAR ENERGY SERVK;ES

1. INTRODUCTION This document presents the Inservice inspection Requirements for the Residual Heat Removal System of the Shoreham Nec: ear i5wer Plant.

l The General Text, NES Document Number 80AS60$ presents the basis for the Inservice Inspection Program and a more detailed d'escription of the Inservice Inspection l Program Plan than is contained in this document.

2. CLASSIFICATION T e Residual Heat Removal System piping and instrumentation diagrams have been reviewed and Quality Group A and B boundaries have been established in accordance with Regulatory Guide 1.26 Rev 3. These boundaries are shown on Figure FM-20A-ISI and FM-20B-ISI.

3. EXEMPTIONS The portions of the Residual Heat Removal System that are exempted from the volumetric and surf ace examinations of Section XI are listed in Table 3-1.

TABLE 3-1 EXEMPTIONS Quality Component Basis for Boundary Group Description Exemption Diagram A All piping 1 inch IWB-1220(b) FM-20A-ISI nominal pipe size FM-20B-ISI and smaller l I FCAM e NES 205 2/80

my DOCUMENT NO, R n A s r,11 PAGE 9 0F f4 NUCLEAR ENERGY SERVCES TABLE 3-1 (Continued)

EXEMPTIONS Quality Component Basis for Boundary Group Description Exemption Diagram B 6"- W R -239-301 -2 Code Case FM-20A-ISI g 6"- W R-371-301-2 N-403(a)(6) 10"-WR-273-301-2 10"-W R-279-301-2 12"- W R-27 5-301-2 B 6"-WR-290-301-2 Code Case FM-20B-IS!

6"- W R -371 -301-2 N-403(a)(6)

{ l 10"-W R -274-301-2 10"-WR-2SO ' ~ ?

12"-WR-276 - 4 B All piping 4 inch Code Case FM-20 A-ISI nominal pipe size N-40S(a)(1) FM.20B-ISI !

and smaller i

l I FORM s NES 205 2/60

1 m DOCUMENT NO. SOA8613 l W '

NUCt. EAR ENERGY SERVICES O 4. EXCEPTIONS For those examinations in the Residual Heat Removal System that cannot be completed in accordance with the Section XI requirements a relief request will be prepared and submitted to the NRC. Those areas for which a relief request has been prepared are listed in Table 4-1.

TABLE 4-1 EXCEPTIONS Component Component Fig. Relief Identification Description No. Request Remarks Ell-X-10A Integrally welded 8613-9 S613-R 1 A ttachment (suppression pool penetration)

E l 1-X-10 B Integrally welded 8613-13 8613-R1 A ttachment (suppression pool penetration)

B 31-NS006-B W 40 B31-NS006-BW34 Safe-end to Tee Tee to Safe-end 8613-03 8613-R 2 g 8613-01 3613-R 2 B31-NS005-BW36 Safe-end to Tee 3613-02 3613-R 2 E l l-IC-62-F W 20 Pipe to 10" x 8" Red. 8613-15 8613-R3 l

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l l FORM e NES 205 2/B0

ay DOCUMENT NO. ROA?611 O 11 NUCLEAR ENERGY SERVICES PAGE 7 op 14 V

RELIEF REQUEST 8613-R 1 System: Residual Heat Removal Category: C-C Ouality Group: B Component

Description:

Integrally welded attachments Type 4 con tainm ent penetration at penetration X-10A&B Code Requirement: Surface Examination l

Basis for Relief: These welds are located under a containment test channel which makes them inaccessible for surface examination.

Alternate Tasting: A leakage test will be conducted during the first refueling outage and then once during each period for a total of 4 tests in the first interval.

l I FCAM e NES 205 2/60

DOCUMENT NO. SOA8613 O'

OW NUCLEAR ENERGY SERVCES t i

1 RELIEF REQUEST 8613-R 2 b

System: Residual Heat Removal Category: B-3/Nonconf orming Service Sensitive (NUREG-0313)

Quality Group: A Component

Description:

Safe-end to tee welds, B31-NS006-BW40, 34; B31-NS005-BW36.

Code Requirement: Volumetric examination of 100% of circumferential and the adjoining i It, sections of longitudinal pipe welds shall be ]

perf orm ed.

Basis for Relief: Relief is required from the ASME Section XI examinations and augmented examinations required by NUREG-0313 on the basis G of partial inaccessibility of the welds and required volume due to plant design. The estimated percent of weld scan to be j

performed is listed on the following page.

The justification for requesting relief from the examination '

t equirements :s:

A substantial percent coverage of each of the par tially inspectable welds was achieved during the PSI (See at tachm ent). Since the construction, operating conditions and environmental conditions on the non-inspectable portions of the l weld are identical to the areas which can be inspected, the results of the inspected areas can be extended to the non-inspected area.

Alternate Testing: None.

l I FORM e NES 205 2/80

m DOCUMENT NO. 9nARArt NUCLEAR ENEROY SERVICES PAGE o 0F in l

RELIEF REQUEST 8613-R2 ATTACHMENT d

Estimated Predicted E Weld % of Scan Completion Identification Completed of Scan Number System Configuration Nature of Obstruction for PSI forISI B31-NS006-BW40 RHR Tee to Pipe Part Geometry 21 21 B31-NS005-BW36 RHR Tee to Pipe Part Geometry 64 64 B31-NS006 BW34 RHR Tee to Pipe Part Geometry 63 63 O

l l I FORM s NES 203 2/60

\

DOCUMENT NO.

30A %I3 O

NUCt. EAR ENEROY SERVK:ES o

'd RELIEF REQUEST 8613-R 3 g-System: Residual Heat Removal Category: C-F Quality Group: B Component

Description:

Pipe to 10" x 3" reducer weld, Ell-IC-62-FW20 Code Requirements: Volumetric examination covering 100% of weld.

Basis for Relief: Relief is required from the ASME Section XI examinations on the basis of partial inaccessibility of the weld.

The basis for requesting relief from the ASME Section XI examination is as follows:

l l

1. Complete examinations wit! be performed on welds of similar configurations which utilized the same weld techniques, procedures and materials. The inspected welds shall be subject to the same operating and environmental conditions as the partially inspected welds, it is, therefore, reasonable to extend the results of the inspectable welds to the patially inspectable welds. '

2. A substantial percent (37.5%) coverage of the partially inspectable welds was achieved during the PSI. The predicted percent completion during 151 is 95 Since the construction, operating conditions and environmental conditions on the non-inspectable portions of the weld are identical to the inspected area, the results of the inspected areas can be extended to the non-inspected area.

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FORM NES 205 2/80

DOCUMENT NO. 80A3613 m _

11 W NUCLEAR ENEROY SERVX:ES -

O C

5. CALIBRATION STANDARDS Table 5-1 lists the Calibration Standards for ultrasonic examinations scheduled for the Residual Heat Removal System.

TABLE 5-1 Calibration Standards Title Size Material Drawing 10-030-CS 10" S CH.80 S A-106, GR.B NES 30C0513 12-040-CS 12" S CH.40 S A-106, GR.B Later 16-0 40-CS 16" SCH.43 SA-106, GR.B Later 16-STD-CS 16" STD. SA-106, GR.B Later 18-040-CS IS" SCH.40 SA-106, GR.B NES 30C0519 20-U40-CS 20" SCH.40 SA-106, GR.B NES 80C0519 20 030-C5 20" SCH.80 SA-106, GR.B NES 80D0514 20-80S-SS 20" SCH. SOS SA-358, TP 304 NES SOD 0514 20-S TD-CS 20" S TD. SA-106, GR.B Later 24-040-CS 24" SCH.40 SA-106, CR.B NES 30C0519 24-030- CS 24" SCH.80 S A-106, GR.B NES 30D0514 24-30S-55 24" SCH.805 SA-333, TP 304 NES 80D0514

6. PROGRAM PLAN AND SCHEDULE The specifi<- Residual Heat Removal ISI examination requirements are defined by the Program Plan and Schedule Tables. This Prograrn Plan 'ists all the required examinations for a 10 year interval of 3 periods of 40 months each. Table 6-1 presents a summary of these Section XI required examinations scheduled by different Code categories applicable to this system.

Each weld and component is designated by a t.nique identification number, and then described. Also identified is the app!! cable examination procedure number, Code category and number, examination method, and the calibration block,if required.

Any comments specific to a component are noted in the reraarks column.

Examination items are divided according to the Isometric figure on which they appear and are listed following the direction of flow in the pipe. Multiple examination l ) requirements of the same component are listed together in the .,chedule + ables.

FORM e NES 205 2/B0

DOCUMENT NO. 30A3613 my _

O11 (d NUCLEAR ENERGY SERVCES PAGE I2 05- I4 TABLE 6-1 SECTION XI EXAMINATION SCHEDULE RESIDUAL HEAT REMOVAL SYSTEM Examinations by Component Code Period Total in Description Category P P P Total System 3 2 3 Dissimilar metal welds B-F 1 1 1 3 3 Bolting < 2" (circumferential)

Piping welds B-G-2 B-3 6

10 5

10 11 5 16 16 A 31 124 Integral attachments B-K-1 0 1 1 2 2 Valve bodies B-M-2 3** 0 0 3 9 Systems leakage test B-P * * * - -

System hydro test BP 0 0 1 1 -

Vessel welds C-A 1 1 1 3 3 l

Nozzle welds C-B 1 1 0 2 2 Integral attachments C-C 6 4 4 14 14 Piping welds (circumferential)* *

C-F-2 15 16 16 47 618 (460)O System leakage test C-H I i 1 3 -

System hydro test C-H 0 0 1 1 -

Leakage Test is required at each refueling outage.

Deferral of these examinations to the end of the interval is permissible.

Weld selection in accordance with Code Case N-403.

@ Only 460 welds require nondestructive examination in accordance with Code Case N-403.

l I FostM s NES 205 2/60

DOCUMENT NO. 80A3613 11 l

W O' NUCLEAR ENERGY SERVCES A

7. PRESSURE TESTS In accordance with Section XI all Quality Group A pressure retaining components are to receive a leakage test in accordance with IWB-5221 every refueling outage, all Quality Group B presiure retaining components are to receive a leakage test in accordance with IWC-5221 every period (40 months), and both Quality Group A & B pressure retaining components are to receive a hydrostatic test in accordance with lWB-5222 and IWC-5222 respectively at or near the end of the interval. The portions 1 I

of the Residual Heat Removal System requiring these pressure tests are those marked Quality Group A & B including lines ! inch and less on boundary diagram FM-20A-ISI and FM-20B-ISI.

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8. ISOMETRIC FIGURES AND SKETCHES ,

1 The piping isometric figures listed in Table S-1 show the identification and location of areas for the Residual Heat Removal System requiring examir.ation. Sketches may I also be included that illustrate or locate areas of components requiring identification l

for examination. Boundary Diagrams are provided to show the Quality Group boundaries and also to define those areas requiring pressure testing under Code !

Category B-P and C-H. I

)

TABLE 8-1 Isometric Figures '

3613-1 Rev.1 3613-2 Rev.1 l 8613-3 Rev.1 l

8613-4 Rev.!

8613-5 Rev.1 i 8613-6 Rev.I j 3613-7 Rev.2 l 3613-3 Rev.1 8613-9 Rev.2 l q g 8613-10 Rev.1 FCAM mES 205 2/B0

DOCUMENT NO. SOA8613 MGE I4 0F l4 NUCt. EAR ENERGY SERVICES V TABLE 8-1 (Continued)

Isometric Figures 3613-11 Rev.2 d 8613-12 Rev.I S613-13 Rev.I 8613-14 Rev.I 3613-15 Rev.1 3613-16 Rev.I 8613-17 Rev.2 8613-13 Rev.2 3613-19 Rev.1 8613-20 Rev.2 ,

1 3613-21 Rev.2 '

3613-22 Rev.0 Boundary Diagrams F M-20A-ISI Rev.1 F M-20B-ISI Rev.1 l

9. AUGMENTED REQUIREMENTS 9.1 NUREG-0313 (IGSCC)

There are twenty-four (24) welds that fall into the category of "nonconforming service sensitive" of NUREG-0313. Eighteen (18) of these welds are included in the Recirculation system, the remaining six (6) are in the Residual Heat Removal l system. These welds appear under the heading period IB and are required by NUREG-0313 to be examined at each reactor re'ueling outage or at other l scheduled plant outages. However, successive examinations need not be closer than 6 months. If three (3) successive inspections find the piping free of unacceptable indications, the examinations may be extended to each 36 month q g period (plus or minus by as much as 12 months) coinciding with a refueling outage.

FOAM e NES TO5 2/80

O APPENDIX A O

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1 DOCUMENT NO. 30 A3613 )

m l 11 NUCLEAR ENERGY SERVK;ES PAGE t op 7 APPENDIX A Table of Contents Number of Pages

1. Program Plan Work Schedule Tables Period i 17 l

Period 2 15 I Period 3 14 Period IB (IGSCC) 3

2. Isometric Figures I

S613-1 S613-12 3613-2 3613-13 3613-3 3613-14 3613-4 3613-15 3613-5 3613-16 3613-6 3613-17 8613-7 3613-13 3613-S 3613-19 3613-9 3613-20 I S613-10 S613-21 3613-11 8613-22 f

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3. Boundary Diagrams FM-20A-ISI F M-20B-ISI i

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FORM s NES 205 2/80

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m DOCUMENT NO. enA ui1 11 NUCLEAR ENERGY SERVCES PAGE 2 OF. >

O i 1

l The following notes apply to the Program Plan and Schedule Tables.

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I Note 1 - This examination has been scheduled for the first period, however the i examination may be deferred to a time later in the interval when the l

component will be disassembled.

Note 2 - Not applicable '

Note 3 - This weld is scheduled to be examined by requirements of NUREG-0313 l (ICSCC) which meets or exceeds the Section XI requirement and is listed here only for continuity.

l I l l FORM a NES 20S 2180

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O O O SHORDIAM NUCLEAR POWER STATION SYSTEM: RESIDUAL HEAT REMOVAL ISI PROGRAM PLAN AND SCHEDULE PERIOD 1 NES ISO NUMBER 8613-01 80A8613 REV. 3

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PAGE 1 OF 17

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I I I I i 1 100DE l l l COMPONENT I SIZE i COMPONENT j PROC. ! CAL. j 00DE ! (DDE iEXAM l REMARKS !

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E11-290-A 20 SAFE-END 10 EI. BOW 80A3131 20-80S-SS B-F B5.130 Ur SEE NOTE 3 20-080-CS <

80A3132 PT E11-20V-0005-b <2 VALVE 20V-0005 BOLTING 80A3133 N/A B-G-2 Irf.70 VF-1 E11-MOV-047-b <2 VALVE MOV-047 BOLTING 80A3133 N/A B-G-2 VF-1 ITT.70 B31-NS006-BW34 20 TEE TO SAFE-END 80A3150 2P-80S-SS B-J B9.11 trr SEE NOTE 3 80A3132 PT SEE R.R.8613-R2 E11-291A 20 ELBOW 10 PIPE 80A3131 20-080-CS B-J B9.11 Ur 80A3132 PT E11-IC-17-FW6 20 PIPE 10 ELBOW 80A3131 20-080-CS B-J B9.11 Ur -

80A3132 PT E11-3639-E 20 PIPE TO PIPE 80A3131 20-080-CS B-J B9.11 Ur 80A3132 PT i

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l l l l 1 i i 100DE 1 l l COMPONENT ! SIZE ! COMPONENT l PROC. I CAL. l 00DE I (DDE l EXAM i REMARKS i

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E11-IC-17-FY/ 20 PIPE TO PIFE 80A3131 20-080-CS B-J E9.11 trr 80A3132 PT

E11-MOV-048 20 VALVE BODY INTERNAL SURFACES N/A 80A3133 B-M-2 B12.50 Vr-3 SEE NOTE 1 l

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SiORDIAM NUCLEAR F0WER STATION SYSTEN: RESIDUAL lEAT REMOVAL ISI PROGRAM PLAN AND SCHEDUE PERIOD 1 NES ISO NUMBER 8613_02 80A8613 REV. 3 PAGE 3 0F 17 I 1 l l I i l l CODE i l 1 COMPONENT l SIZE l COMPONENT l PROC. I CAL. l 00DE l ODDE l EXAM ! REMARKS i l IDENTIFICATION l (IN) l DESCRIPTION l NO. l BIBCK i CAT. I NO. !MEDI l l 1 1 I i l I i ! i i e .

t E11_HV_071 ,24 VALVE BODY INTERNAL SURFACES 80A3133 N/A B-M_2 B12.50 VT-3 SEE NOTE 1 >

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SHOREAM NUCLEAR IOWER STATION SYSTEN: RESIDUAL HEAT REMOVAL ISI PROGRAM PLAN AND SCHEDULE PERIOD 1 ~

NES ISO NUMBER 8613-03 80A8613 REV. 3 PAGE 4 0F 17 i

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S110REHAM NUCLEAR POWER STATION SYSTEM: RESIDUAL lEAT REMOVAL ISI PROGRAM PLAN AND SCIEDULE PERIOD 1 NES ISO NUMBER 8613-05 80A8613 REV. 3 PAGE 5 0F 17

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[ COMPONENT I SIZE l COMPONENT l PROC. I CAL. l CODE ! CODE l EXAM i REMARKS l

! IDENTIFICATION j (IN) l DESCRIPTION i NO. l BLOCK ! CAT. I NO. IMEIE l l l l 1 i ! I i i ! l E11-BJ-01-b <2 FLANGE BJ-01 BOLTING 80A3133 N/A B-G-2 B7.50 Vr-1 E11-BJ-02-b <2 FLANGE BJ-02 BOLTING 80A3133 N/A B-G-2 B7.50 vr 1 E11-04V-0030-b <2 VALVE 04V-0030 BOLTING 80A3133 N/A B-G-2 177 . 7 0 VT-1 E11-BJ-03-b <2 FLANGE BJ-03 BOLTING 80A3133 N/A B-G-2 B7.50 vr-1 E11-1455-C 4 PIPE TO ELBOW 80A3132 N/A B-J B9.21 PT E11-1455-G 4 ELBOW ~ID FLANGE 80A3132 N/A B-J B9.21 PT .

4 E11-1456-C 4 PIPE 'ID ELBOW 80A3132 N/A B-J B9.21 PT

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

O O O SiORDIAM NUCLEAR F0WER STATION

. SYSTEN: RESIDUAL lEAT REMOVAL ISI PROGRAM PLAN AND SCHEDULE PERIOD 1 NES ISO NUMBER 8613-05 80A8613 REV. 3 PAGE 6 OF 17 e + .

I ! I I i ! ! ICODE I l l COMPONENT l SIZE l COMPONENT I FROC. I CAL. l 00DE I (DDE ! EXAM I REMARKS I I IDENTIFICATION I (IN) l DESCRIPTION i NO. l BLOCK l CAT. I NO. IMETH I !

! l 1 ! I I I I I I E11-1457-C 4 ELBOW 1D PIPE 80A3132 N/A B-J B9.21 PT E11-1458-A 4 FLANGE BJ-03 TO 6X4 RED. ELBOW 8CA3132 N/A B-J 89.21 PT l

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i I I I I l ! ! CODE l l

! COMPONENT l SIZE I COMPONENT I PROC. I CAL. l 00DE ! CODE iEXAM i REMARKS l l IDENTIFICATION l (IN) l DESCRIPTION i NO. I BLOCK i CAT. I NO. IMEni i !

! I I i ! I I I I 1 E11-IC-30-FW7 24 ELBOW 1D PIPE 80A3131 24-040-CS C-F-2 C5.51 UT 80A3132 PT

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O O O SIDRDIAM NUCLEAR POWER STATION SYSTEM: RESIDUAL lEAT REMOVAL ISI PROGRAM PLAN AND SCHEDUE PERIOD 1 NES ISO NUMBER 8613-07 80A8613 REV. 3 PAGE 8 0F 17

! l 1 l ! I I !00DE I I l COMPONENT l SIZE I COMPONENT I FROC. 1 CAL. 1 (DDE ! ODDE lEXAM l REMARKS I r

! IDENTIFICATION I (IN) l DESCRIPTION I NO. I BIDCK I CAT. I NO. IMETH I I I i l I i ! ! I I I E11-IC-39-W12 18 ELBOW TO PIPE 80A3131 18-040-CS C-F-2 C5.51 Ur 80A3132 PT ,

E11-IC 40- W2 16 VALVE E11-MDV-033A 10 PIPE 80A3131 16-040-CS C-F-2 C5.51 Ur 80A3132 PT E11-IC-40-W5 16 EGOW TO N0ZZLE lEAT EX.E-034A 80A3131 C-F-2 C5.51 Ur 80A3132 PT G

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O O O SHORDIAM NUCLEAR POWER STATION SYSTEM: RESIDUAL EAT REMOVAL ISI PROGRAM PLAN AND SCHEDULE PERIOD 1 NES ISO NUMBER 8613-09 80A8613 REV. 3 PAGE 9 OF 17

! ! l l l l l 100DE ! l l COMPONENT l SIZE i COMPONENT I PROC. I CAL. I CODE I (X)DE ! EXAM l REMARKS 1 1 IDENTIFICATION I (IN) I DESCRIPTION l NO. I BIDCK I CAT. I NO. IMETH l 1 l l 1 l i ! i ! I I I l

E11-PSSP-811 16 INTEGRALLY WELDED ATTACHME!C 80A3132 N/A C-C C3.20 PT E11-PSSH-107 16 INTEGRALLY WELDED ATTACHENT 80A3132 N/A C-C C3.20 Pr E11-215-B 16 ELBOW W PIPE 80A3131 16-040-CS C-F-2 C5.51 Ur 80A3132 Pr E11-IC-34-FW1 16 VALVE E11-MOV-042A E PIPE 80A3131 16-040-CS C-F-2 C5.51 Ur 80A3132 PT a E11-IC-34-FW3 16 PIPE E ELBOW 80A3131 16-040-CS C-F-2 C5 51 Ur 80A3132 Pr l

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, O O O SHORDIAM NUCLEAR POWER STATION SYSTEN: RESIDUAL lEAT REMOVAL ISI PROGRAM PLAN AND SCllEDUlf PERIOD 1

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NES ISO NUMBER 8613-10 80A8613 REV. 3 PAGE 10 0F 17 1 I i i ! 1 ICODE I 1

! COMPONENT l SIZE l COMPONENT l PROC. l CAL. l 00DE ! 00DE IEXAM l REMARKS X 1 IDENTIFICATION ! (IN) l DESCRIPTION ! NO. I BLOCK l CAT. I NO. lMEni j i 1 1 I i ! I i i i I E11-PSA-109 24 INTEGRALLY WELDED ATTACIDENT 80A3132 N/A C-C C3.20 PT i E11-PSR-143 16 INTEGRALLY WELDED ATTACHMENT 80A3132 N/A C-C C3.20 PT E11-197-C 24 TEE TO flBOW 80A3131 24-040-CS C-F-2 C5.51 UT 80A3132 PT i

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