Text

Inservice Insp Program for Welds & Supports First 10-Yr Interval. Related Info Encl
	ML20236M919
Person / Time
Site:	FitzPatrick
Issue date:	08/06/1987
From:	; POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	;
Shared Package
ML20236M860	List: JPN-87-043, Forwards Inservice Insp Program for Welds & Supports Summary Rept of First 10-yr Interval.Summary of Insp,Radiation Survey & Info Re Hydrostatic & Pressure Tests Also Encl; ML20236M919;
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	NUDOCS 8708110300
	Download: ML20236M919 (177)
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ATTACHMENT I TO JPN-87-043 INSERVICE INSPECTION PROGRAM FOR WELDS & SUPPORTS FIRST TEN-YEAR INTERVAL l

l RELIEF REQUESTS i

l t

1 New York. Power Authority James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 i DPR-59 '

8708110300 070B06 PDR 0 ADOCK 05000333

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j component / Weld Specific Relief Requests - First 10 Year Interval (1975 - 1985).

1. Item B.l.2: Reactor Vessel Shell Welds Other Than in ,

Beltline; Code Category B-B. (See Attachment II, page 4).

i a) Relief is requested from the Code-required extent of examination for all the meridional welds in the vessel top closure head: j

)

VV-TH-1A VV-TH-lD VV-TH-lG j VV-TH-1B VV-TH-lE VV-TH-lH VV-TH-1C VV-TH-1F The Code requires 10% of the length of each of these welds to be examined. Due to an administrative error, only 9.6% of each weld was actually examined (i.e., 8" examined /83" total length of each weld). This error was discovered after the 1985 refueling outage was completed and The Code-required extent i the plant re-started.

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of examination will be performed in the future. !

l Since no indication was found in the lengths ;

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examined, and since the unexamined length is so ,

small, this minor discrepancy will not affect the ;

safety of the plant.

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b) Relief is requested from the Code-required extent of examination for the following meridional welds in the vessel bottom closure head:

VV-BH-2A VV-BH-2C VV-BH-2E VV-BH-2B VV-BH-2D VV-BH-2F (See Attachment II, page 6).

Inspection of the Code-required 10% of the length of each of these welds is not possible due to restricted accessibility. Access is limited to four 18" diameter manways 90 0 apart in the vessel support skirt. In addition, the control l l

rod drives and twelve core instruments provide I extensive interference. Drawings detailing these interferences and the limited access were included as Enclosure #5 of Attachment IV of Reference 4. The relief request discussed in 1

Attachment 4 of Reference 4 provides additional l l

detail supporting this request. Five percent of l weld VV-BH-2D was inspected.during this first 10 year interval. Since inspection of the other welds is not possible, relief is requested from 100% of the Code-required extent of examination of all these welds except VV-BH-2D. Relief from n

50% of the Code-required extent of examination is I-2 1

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requested for weld VV-BH-2D. As no indications i

have been discovered in VV-BH-2D, nor in the welds of the top head, this relief will not affect the safety of the plant. !

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2. Item B.l.4: Reactor Vessel Nozzle Inner Radii; Code l

Category B-D. (See Attachment II, pages 8-10). !

l a) Relief is requested from inspection of the inner blend radii of the nozzles listed in Table 2.1.

The examinations that were performed were restricted by interference from permanent structures such as non-removable vessel l insulation, instrumentation lines / penetrations, and other nozzles. Because detailed measurements of these interferences were not taken at the time of some of these examinations, the extent of ;

examination actually performed is not recorded.

Although it is likely that the extent of examination completed is similar to that detailed in Section 2b, relief is requested from examination of the inner blend radii of the following nozzles due to inaccessibility: )

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TABLE 2c1 l l

i N0ZZLE NAME/ FUNCTION YEAR EXAMINED N-2A Recirculation System Inlet 1977 N-2E Recirculation System Inlet 1977 )

l N-2H Recirculation System Inlet 1977 j i N-2J Recirculation System Inlet 1981 l N-3C Main Steam Outlet 1977 N-8B Jet Pump Instrumentation 1977 l

2. b) As discussed in Section 2a, examination of the l

reactor vessel nozzle inner blend radii in the areas listed in Table 2.2 is restricted by access limitations. Accessibility is limited by permanent insulation and/or permanently installed instrumentation / drain-piping. Detailed measurements were taken of these areas, and relief from examination is requested. These restrictions apply only to the axial scans of the volume in question, both for the nozzles listed in Table 2.2 and for those listed in Section 2a. The volume of ,

interest was inspected completely by j l

circumferential scans. The limitations listed I reflect the variation in the available distance from the nozzle for performance of an axial scan l around the nozzle circumference. Since the bulk of the nozzle weld areas were inspected, these relief requests (both a. and b.) will not affect the l

safety of the plant. (See Attachment II, pages 8 l

and 9).

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3. Items B.1.6, B.4.6: Primary nozzle to safe-end welds, 1

I longitudinal /circumferential weldt in piping, Code Category B-F and B-J. (See Attachment II, pages 148, 149).

As described in Reference 4 and illustrated in Attachment 3 to thia letter, volumetric examinations of the Jet Pump Instrumentation Nozzle (N-8A,B) safe-end and penetration seal welds could not be performed due to extremely high radiation fields. Attachment III is a radiation survey taken during inspection attempts during tne 1985 refueling outage. Even after flushing, the shielded dose exceeds 5 rem /hr. Significantly, the lead shielding is directly over the areas to be inspected and would require removal before inspection. Therefore, the Authority requests

, relief from volumetric examination of thece welds. Visual examinations were performed, including one during the vessel hydrostatic test to detect evidence of ledkage. Due to the alternative examinations performed, this rollef request will not affect the safety of the plant. 1

4. Item B.4.1: Bimetallic circumferential weld in piping Code Category B-F.

The Authority requests relief from 100% volumetric x

examination of 24" diameter binetallic welds in the RHR system numbered:

r I-7 i

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24-10-142 24-10-130 24-10-143 24-10-131 24-10-144 24-10-132 As shown on page 39 of Attachment II, the geometry of these welds prevents examination by ultrasonic shear wave techniques. The wall thickness of over 2" prevents meaningful radiographic inspection without system drain down and component disassembly. Development of unique calblocks is curren+1y underway. Until such time as an i

adequate, practical examination methodology is developed, limited ultrasonic, visual and surface examinations will be

! performed in lieu of volumetric inspection. (See Attachment II, page 38).

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5. Item B.4.12: Piring Pressure Retaining Bolting less than 2" in diameter; Code Category B-G-2.

l Relief is requested from visual examination of the pressure retaining bolting associated with Flanges A, B, C, and D in l i

the Residual Heat Removal (RHR) System head spray line. As j

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previously indicated, this bolting was scheduled for

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inspection only when these components were disassembled for other maintenance. Since most bolting failure occurs l during loosening and retightening, and since drywell leakage limits would serve as a warning of a failed bolt, this relief request will not affect plant safety. (See Attachment II, page 42).

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6. Item B.1.11: Reactor Vessel Pressure Retaining Bolting less than 2" in Diameter; Code Category B-G-2. (See Attachment II, page 11).

The components in this category are the bolting of the 137 Control Rod Drives and of the 43 Incore Instrumentation Penetrations. This bolting is inaccessible in place due to the control rod drives and incore instruments, and was inspected only during disassembly for component maintenance / replacement. During the first 10 year interval, 79 components or 57% of the CRDs' bolting were inspected, and 7 components or 16% of the incore instrumentation bolting were inspected. Relief is requested from the Code-required extent of examination (100%) for the ten year interval with the above percentages inspected instead.

l l Remote inspection for leakage was also performed on each component during the Class 1 hydrostatic test at l the end of the interval.

Since most bolting failure commonly occurs during loosening and retightening, this relief request will not affect plant safety.

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L 7. Item B.6.9: Valve Pressure Retaining Bolting less than 2" in diameter; Code Category B-G-2.

Relief is requested from visual examination of the pressure retaining bolting in the valves listed in 1 Table 7.1.

This bolting was scheduled for inspection only when

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these components were disassembled for other maintenance. Since most bolting failure occurs during loosening and retightening, and since FitzPatrick has 1 i

drywell leakage limits, this relief request will not j affect plant safety. (See Attachment II, pages 18, 42, 74, 82, 96, 112, and 132).

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r e . e TABLE 7.1 System Valve Number Reactor Water Recirculation 02-MOV-43A 02-MOV-53B 02-MOV-43B 02-MOV-54A 02-MOV-53A MOV-54B Residual Heat Removal RHR-29 10-AOV-25A RHR-81A 10-AOV-25B RHR-81B 10-AOV-32 RHR-88 10-AOV-33 Reactor Water Clean-Up 12-MOV-15 RWC-62 12-MOV-18 RWC-68 1

RWC-46 12-MOV-68 Reactor Core Isolation Cooling 13-MOV-15 13-MOV-16 13-MOV-21 13-MOV-22 Core Spray 14-MOV-12A 14-MOV-12d High Pressure Coolant Injection 23-MOV-15 23-MOV-16 23-MOV-18 23-MOV-19 Main Steam 29-RV-71A 29-AOV-80A Feedwater 34-NRV-111A FWS-29B FWS-29A I-11

_ _ - _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ . l

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8. Items B.4.9, B.5.4, B.5.5, B.6.43 Integrally walded ,

supports; Code Category B-K-1. (See Attachment II, pages 20, 44, 98, and 114)

In previous correspondence, the issue of extent and examination method for Code Category B-K-1 components has been discussed extensively. Specifically, and most 1 lately, References 2 and 3 have restated this issue without resolution.

I The Authority has determined that a surface examination

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1 is a more meaningful examination of these components, l as indicated in the later Code Editions, and has

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performed such inspections.during the first interval i

without discrimination based on attachment plate thickness. During this interval, up to April 1985, the l l

extent of examination complied with the JAF ISI !

l Program's base Code, the 1974 Edition through Summer l 1975 Addenda, which required examination of 25% of all components.

Our understanding of the NRC's position, as detailed in Reference 3, is that surfac.w examination of these ]

components is acceptable providing the extent of examination follow that of the later Code Editions ,

(i.e., 1977 Edition, Summer 1978 Addenda, or later).

This would require examination of 100% of all I-12

components whose attachment base metal is 5/8" thick or greater.

The first ISI interval for JAF has been completed without resolution of this issue. This issue does not affect the ISI Program for the second interval, which is based on the 1980 Code, Winter 1981 Addenda.

l However, less than 100% of these components with a 5/8"

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thick or greater attachment base metal were inspected during the first interval, as required by the 1977/78 I code, and some support attachment plates less than 5/8" '

thick were examined. Table 8.1 shows both the total i number of components and the number inspected, with an attachment plate 5/8" thick or greater. Table 8.2 shows the total number of support attachment welds and the number inspected without regard to thickness. The examination extent originally proposed in the JAF ISI Program (25%) has been met in all casec. Moreover, since 100% of all required support welds will be

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inspected during the next interval, performance of

" additional" inspections at the start of this next interval is not meaningful. However, inspection of these components will be scheduled at the start of the next interval as far as practical. Table 8.3 lists the specific components for which relief is requested.

This relief request will not affect plant safety, as no I-13 l

l evidence of service induced failure has been' discovered i and future inspections will be in accordance with later Code requirements. I TABLE 8.1

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Total B-K-1 Total Percentage System -Welds >5/8" Thick Inspected Insoected Recirculation 32 14 43%

Residual Heat 12 4 33%

Removal Reactor Water 1 1 100% ,

Clean-up Reactor Core Isolation Cooling 0 0 N/A Core Spray 0 0 N/A-High Pressure 2 0 0%

Coolant Injection Main Steam 37 17 46%

Feedwater 7 4 57%

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TABLE 802-Total Attachment Total Percentage System Welds Inspected Inspected Recirculation 32 14 43%

Residual Heat 26 12 46%

Removal-Reactor Water 9 5 55%

Clean-up Reactor Core Isolation Cooling 14 10 71%

Core Spray 6 3 50%

High Pressure 5 3 60%

Coolant Injection i

Main Steam 46 24 52%

Feedwater 18 11 61%

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I TABLE 8.3 B-K-1 Components (2 5/8" Attachment Base Metal Thickness) Not Inspected in First Interval Reactor Water Recirculation System 22-02-2-22A 28-02-2-89A 22-02-2-22B 28-02-2-89B 28-02-2-31B 28-02-2-89D 28-02-2-31D 28-02-2-110F 28-02-2-150 28-02-2-143 28-02-2-158 28-02-2-145 22-02-2-86A 28-02-2-151 22-02-2-87A 28-02-2-156 1 22-02-2-87B 28-02-2-146B l

)

l Residual Heat Removal 24-10-132A 24-10-146C 37-10-152A j l 24-10-132B 24-10-992 37-10-139A 1 24-10-989 24-10-993 Reactor Water Clean-up 4-12-470C 4-12-477B Reactor Core Isolation Cooling None 1 5/8" Core Spray None 2 5/8" High Pressure Coolant Injection 14-23-428A 10-23-668A Main Steam 24-29-519A 24-29-550A 24-29-602C 24-29-522A 24-29-557A 24-29-626A 24-29-534A 24-29-569B- 24-29-543C 4 24-29-542C 37-29-573C 24-29-543D 24-29-607C 24-29-593 24-29-574C 24-29-630B 24-29-638C 24-29-574D 24-29-638B 24-29-574B Feedwater 18-34-937A 12-34-401A 12-34-944 1

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9. Itsms B.4.10, B.S.5, B.6.5 Pressure Boundary Piping, Pump, Valve Supports; Code Category B-K-2. (See Attachment II, pages 20, 44, 75, and 84). q l

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The code requires 100% of all such components to be visually j i

examined during the' ten-year interval. Since for some systems slightly less than 100% were inspected, relief is requested 1 from examination of the components listed.in Table 9.1. These supperts will be scheduled for inspection during the first half of the next ten year interval. Table 9.1 lists the system, total percentage inspected, and the specific j components for which relief is requested. This relief request

, will not affect the safety of the plant, as the vast majority of these components were inspected with little or no evidence ,

of service induced failure.

Table 9.1 Percent (Number Inspected)/ Support System (Total Population) Number Recirculation 94% (49/52) 02-2-1B-S-15 02-2-2B-S-4 02-2-9B-AN-10*

Residual Heat Removal 86% (32/37) 10-2C-AN-205 10-43-AS-236 i 10-14A-NS-240B {

10-43-AN-230 l 10-43-AN-229 Reactor Water Clean-Up 95% (23/24) 12-14-NS-12 Reactor Core Isolation 95% (19/20) 13-4A-NS-1A Cooling 1

{

Main Steam 94% (55/58) 29-lC-AN-23B 29-lC-AN-28 29-1D-AN-40A

This support will be eliminated during the 1987 refueling

! outage as part of the by-pass line removal.

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10.-Item B.6.7: Valvo Internal Prascura Boundary Surfacent Code Category B-M-2. (See Attachment II, pages 22, 46, 77, 100, 116, 136, and 145). j Relief is requested from visual examination of the internal surfaces of the valves listed in Table 10.1. As previously indicated, these components were scheduled for inspection j only when disassembled for other maintenance. Based on the I

visual inspections performed, combined with the drywell leakage monitoring, this relief request will not affect the safety of the plant.

1 TABLE 10.1 System Valve Number Reactor Water Recirculation 02-MOV-43A 02-MOV-53B 02-MOV-43B 02-MOV-54A 02-MOV-53A 02-MOV-54B Residual Heat Removal RHR-29 10-AOV-25A RHR-81A 10-AOV-25B RHR-88 10-AOV-32 ;

10-AOV-33 Reactor Water Clean-up 12-MOV-15 RWC-46 12-MOV-18 RWC-62 12-MOV-68 RWC-63 Reactor Core Isolation 13-MOV-21 13-MOV-15 Cooling 13-MOV-22 13-MOV-16 Core Spray 14-MOV-12A CSP-14A !

14-MOV-12B CSP-14B High Pressure Coolant 23-MOV-15 23-MOV-18 Injection 23-MOV-16 23-MOV-19 Main Steam 29-AOV-80A 29-RV-71C 29-RV-71G 29-AOV-86A 29-RV-71D 29-RV-71K l 29-RV-71A 29-RV-71E 29-RV-71L 29-RV-71B 29-RV-71F 29-RV-71J Feedwater 34-NRV-lllA FWS-28A FWS-29A FWS-28B FWS-29B l

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11. Item C.2.5, C3.3, C4.4 Intcgrally cttached cupports; Code Category C-E-1. (See Attachment II, pages 46, 89, 105, and 124).

l In Reference 3, the Authority combined Class 1, 2, and 3 components into one inspection program with a common inspection interval. To do this, the Authority proposed completion of 50% of the Code requirements for Class 2 and 3 components during the February 1985 outage. However, for Code Category C-E-1, less than 50% of the specific Code requirements were completed by end of this "first" interval. Examinations necessary to meet 50% of the total, as discussed in References 1 & 2, will be performed during the first half of the next interval. However, inspection of these components will comply with the Code currently in effect, and, therefore, will include only those components whose attachment plate is greater than 3/4" thick. Table 11.1 lists the number of inspections required (based on 50% I j

i of the Code requirements for equivalent streams) during the I second interval. This relief request will not affect plant safety, as no evidence of service induced failure has been discovered. Future inspections will comply with current Code requirements. 1 i

TABLE 11.1 Additional Number of C-E-1 Welds System To Be Inspected Percent inspected Residual Heat Removal 13 34%

Reactor Core Isolation 1 40%

Cooling I-19

TABLE 11.1 (Cont'd)

Additional Number of C-E-1 Welds System To Be Insnected Percent Insnected l

l l Core Spray 4 18%

Containment Air 20 45% l Dilution (CAD) '

j 12. Items C.2.1, 2.2, 2.3: Welds in pressure retaining piping; Code Categories C-F and C-G. (See Attachment l II, page 129).

In Reference 3, the Authority combined Class 1, 2, and 3 components into one inspection program with a common r

inspection interval. To do this, the Authority proposed completion of 50% of the Code requirements for Class 2 and 3 components during the February 1985 outage. Inspection of two additional welds, in the Containment Air Dilution System (an air system receiving non-Code required, augmented inspections) ,

Category C-G, will be performed during the first half of the next interval to meet the program requirements.

The Code-required inspection percentages, as modified in References 2 and 3, have been met otherwise. This a

relief request will not affect plant safety, as no i 1

evidence of service induced failure has been !

I discovered. Future inspections will be in accordance l l

with later Code requirements. l i

I-20 i

i ATTACHMENT II TO JPN-87-043 i j

INSERVICE INSPECTION PROGRAM FOR WELDS & SUPPORTS FIRST TEN-YEAR INTERVAL l

l l

SUMMARY

OF INSPECTIONS PERFORMED i

I

'l New York Power Authority James A. FitzPatrick Nuclear-Power Plant 4 Docket No.-50-333 DPR-59 1

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SERV 2CE INSPECTION 10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

RPV WELDS i

EQI5_l.1 A relief request is submitted in Attachment I, as, due to the design configuration of the bottom head, these welds are completely l inaccessible. (See Attachment I, page I-2, request 1b).

MQTX 2_i These nozzle welds were examined prior to the development of the updated ultrasonic techniques now being used. Because of the techniques and requirements during our early outages the measurements and location of the restrictions were not included in the dath packages. Therefore, a relief from examination of estimated 100% of weld volume for the first interval is submitted for these welds in Attachment I. (See Attachment I, page I-3 lb).

EQT1-.11 In Attachment I, a relief request is submitted for these nozzles with detailed information add.essing measurements and location of restrictions associated with the welds. (See Attachment I, page I-4).

NOTE 4:

In column " Examined Area", (W-#) denotes a removable RPV insulation panel.

NOTE 5 A relief requert is submitted in Attachment I for the percentage examined of these welds, which, due to inaccurate determination of weld length, had less than 10% actually inspected. (See Attachment I, page I-1, request la).

NOTE 6 Relief from Code requirement is requested in Attachment I. A visual examination of this bolting will be made when the components are j disassembled for other maintenance. (See Attachment I, page I-9, )

request 6).

I 1

l l

Page 14

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l 1

SERVICE INSPECTION 10 YEAR

SUMMARY

i JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

l RECIR/02

! i 1 )

B-G-2 )

I 1

1 1

NOTE la Relief from Code requirement is requested in Attachment I. A visual ;

examination of valve bolting will be made when the valves are disassembled for other reasons. (See Attachment I, page I-10, request 7).

I i

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I l

l l

i i

Page 19 ]

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EO . _

TN 4 5 6 4 5 6 _

I B B B B B B Y .

R 1 1 1 2 2 2 -

EO - - - - - -

DG K K K K K K _

OE - - - - - -

CT B B B B B B A

C -

M 2 2 2 2 2 2 _

E 0 0 0 0 0 0 T / / / / / /

S R R R R R R Y I I I I I I S C C C C C C E E E E E E R R R R R R

INSERVICE INSPECTION 10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

RECIR/02 B-K-1 / B-K-2 NOTE la Relief from Code requirements is requested. (See Attachment I, page I-12, request 8).

NOTE 2:

Relief from Code requirements is requested. (See-Attachment I, page I-17, request 9).

I 1

i l

I

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1 Page 21 i

l l1j

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2 S _

2 K R e e A t g M o .

a E N 1 _

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ll l l1ll1l

. > INSERVICE INSPECTION 10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLAhT PIPING & SUPPORT

SUMMARY

PIPING AND SUPPORTS RECIR/02 i

l Code Cat 3 gory B-M-2 .

l l

l NOTE It l

l Relief from Code requirements is requested in Attachment I. A visual examination of the valves will be made when the valves are disassembled for other reasons. (See Attachment I,.page l

I-18, request 10).

l l

Page 23

!i ) ,i

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UAI T NX N E A

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I R DX EY RE WR ENN OA BI O %

2 PM S MMI 0 O M K UAT 0 I RU N NXC 1 TYAS A EE CRE T S E ALT PMCR E S MUO G NUNP R .

I S P A E .O %

KU H DQN 0 ERCS C OE/ 2 CAI S CR%

I ERD I VYTN D R AA E0P M -

S1 ZG A N TN R N I I I C O _

FP S LI I AT

.P TA A OL 4 TU S P E O M P A

J S

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0 -

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/

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i(!lIl ll lll :ll

INSERVZCE INSPECTION 10 YEAR

SUMMARY

JAMES A. FITZPATRfCK NUCLEAR POWER PLAh7 PIPING & SUPPORT

SUMMARY

ECRAM DISCHARGE TANKS i

NOTE 1:

A Preservice Inspection examination of these components I was performed during the 1983 Summer Outage.

1 1

l l

Page 28 f i

l{l)l 9 S 2 K E R T e A O .

g M N1 a E P R

D E

ST ME %

%AL 0 XP 0 EM 1 O

C S

CM CAD SXE GET 2 I E I L LXP A M TTO OCC TE S

D REC ENC _

BI S _

MMG -

UAI T NX N E A

L P

I R DX -

EY RE WR E NN OA BI O M PM S MMI 2 O M K UAT I RU N NXC TYAS A EE CRE T S EALT PMCR E SMUO G -

NUNP R .

I S P A E .O %

KU H DQN 5 ERCS C OE/ 2 _

CAI S CR%

I ERD I VYTN D R AA E0P M S1 Z G A N TN R N I I I C O FP S LI I AT

.P TA OL A

S TU P

2

=

E O M

A J

P S _

S A 2 L _

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. 2 .

TN 1 I C Y

R EO DG B _

OE -

CT C A _

C .

M E 3 T 0 S / _

Y D S R C

ll llllhL

. . . INSERVICE INSPECTION 10 YEAR

SUMMARY

l JAMES A. FIT 3 PATRICK NUCLEAR POWER PLANT l PIPING & SUPPORT

SUMMARY

f l

SCRAM DISCHARGE TANKS t

l NOTE 11 ,

1 A Preservice Inspection examination of these components was performed during the 1983 Summer Outage.

l l

I l

1 1

i l

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l Page 30 l l

l l

J

S K E R T A O .

M N1 .

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D E

ST ME

%AL XP 0 EM

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CAD

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PMCR E S MUO G NUNP R . -

I S P A E .O % .

KU H DQN 5 ERCS C OE/ 2 CAI S CR% _

I ERD I VYTN D -

R AA E0P M S1 ZG A N TN R N I I I C O FP S LI .

I AT _

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TU 1 ._

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R -

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CT C A

C M

E 3 T 0 S /

Y D S R C

I :

-

INSERVICE INSPECTION 10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

i l

l SCRAM DISCHARGE TANKS ,

1 l

l FOTE I A Preservice Inspection examination of these components was performed during the 1983 Summer Outage.

l 1

l l

l I

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Page 32 1

3 3

S K

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e M g E a R P .

D .

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%AL .

XP 0 EM -

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I S P A E .O KU H DQN 0 ERCS C OE/

CAI S CR%

I ERD I VYTN D R AA E0 P M S1 ZG A TN R N N -

I I I C O FP S LI I AT

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e A - - - T 1 g M O a E N P R t D

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~

MMG -

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T NX N E -

A -

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PMCR -

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I S P E .O %

KU DQN 0 - - -

ERCS OE/ - - - 5 -

CAI CR%

I ERD -

VYTN R AA E0P S1 ZG N TN N I I I O FP LI I AT

.P TA 4 0 0 A OL 0 0 0 3 TU _

S P _

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S 2 2 2 A 2 2 2 L _

C _

M . 5 3 4 6 4 5 EO TN 2 3 4 2 3 4 I C C C C C C Y

R EO 1 1 1 2 2 2 DG - - - - - -

OE E E E E E E CT - - - - - -

A C C C C C C C

M E 3 3 3 3 3 3 T 0 0 0 0 0 0 S / / / / / /

Y D D D D D D S R R R R R R C C C C C C

l INSERVICE INSPECTION 10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

f CRD/03 l

C-E-1./ C-E-2 EQTK_11 Components were installed during the Summer, 1983 outage; and only preservice inspections were performed this interval.

I l

i 1

1 l

l l

t l

i

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I I

I l

Page 35 l l

1 1

)

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6 K E T d .

3 R T P - ( _

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e M N1 EW2 g E XI 2 a R

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D E

ST ME %

%AL 9 - - - .

XP 5 EM O _

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CM CAD SXE .

GET %

I E 8 - - - .

I L 2 _

LXP A' M .

TTO _

OCC TE S

D REC ENC BI S - - -

MMG - _

UAI T NX N E A

L -

P I

R DX EY RE WR ENN % .

OA BI O 5 -

N PM MMI 2 - - .

- O M UAT I RU NXC -

TYAS EE CRE S EALT -

PMCR SMUO NUNP . _

I S P E .O

_ KU DQN %

. ERCS OE/ 5 - 0 -

. CAI CR% 2 I ERD VYTN

_ R AA

_ E0P _

S1 ZG

_ N TN N O

I I I FP LI I AT 7

.P TA 7 0 4 0 A OL 4 1 TU S P E O M P A

J S

S 2 A 2 2 2 L

C M . 1 2 3 4 _

EO _

TN 2 2 2 2 I C C C C Y

R _

EO _

DG F F F F _

OE - - - -

CT C C C C A

C _

M E 3 3 3 3 T 0 0 0 0 S / / / /

Y D D D D S R R R R C C C C

INSERVICE INSPECTION 10 YEAR

SUMMARY

1 JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

CRD/03 C. .E

(

i NOTE 1 I A Preservice Inspection Examination of these components was performed during the 1983 Summer Outage.

i i

a 1

l

)

f i

Page 37 4

I 1

4

ji \

S 8 K E _

3 R T -

A O . -

e M N1 -

g E a R * -

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REC ENC BI S 1 MMG -

UAI -

T NX .

N E _

A .

L P ._

I ._

R DX EY RE WR ENN -

OA BI O N PM MMI 7 O M UAT I RU NXC TYAS EE S

CRE EALT -

PMCR -

SMUO NUNP .

E I S P .O ._.

KU DQN 0 -

ERCS OE/ 0 CR%

CAI 1 _

I E RD _

VYTN R AA _

E0P .

S1 ZG _

N TN N -

Y I I O _

FP LI -

AT

.I P TA 7 A OL .

TU -

S P E O M P A

J S _

S A

L 1 _

C M . 1 EO TN 4 -

I B -

Y R _

EO _

DG F _

OE - -_

CT B A

C -

M E 0 -

T 1 S / .

Y R -

S H R

o

I SERVICE %NSPECTION 10 YEAR

SUMMARY

JAMES A. TITZPATRICK NUCLEAR POWER PLANT-PIPING & SUPPORT

SUMMARY

RHR/10 B-F

)

l I

( NOTE 1:

l Relief from Code requirements is requested. Due to the design configuration of (6) six welds, (i.e., valve to valve and tee to valve), only a limited volumetric examination of these welds could be performed. (See Attachment I, page I-7, request 4).

i F N_ /

"VAlVE" "TEC" J - _

unable to obtain coverage needed for angle beam inspection, straight beam used as a "best effort" exam.

Page 39 l

S K

0 R E 4 A T M O 1 e E N g R a

P D E

ST ME % %

%AL % - 0 0 XP 0 0 0 EM 3 1 1 O

C S

CM CAD SXE GET I E 1 I L 2 - 1 LXP 2 1 A M TTO OCC TE

- S D

- REC

_ ENC BI S MMG 0 2 - 0

- UAI T NX N E A

L

_ P

_ I R DX O EY RE WR ENN R OA BI O R D 2 N PM MMI 0 - 1 U Y -

O M UAT 2 S H T I RU NXC - - V TYAS EE 1 1 1

CRE S _

EALT _

PMCR _

SMUO NUNP . _

YS P E . O KU DQN % % %

5 ERCS OE/ 5 - 5 CAI CR% 2 2 2 I ERD VYTN R AA E0P S1 ZG N TN N I I I O FP LI I AT

.P TA 2 1 1 1 A OL 7 1 TU S P E O M P A _

J S _

S A 1 1 1 1 L

C M . 5 6 7 8 EO TN 4 4 4 4 I B B B B Y

R EO DG J J J J OE - - - -

CT B B B B A

C M

E 0 0 0 0 T 1 1 1 1 S / / / /

Y R R R R S H H H H R R R R m

iili ! lll[

l INSERVICE INSPECTION 10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

.B-J SYSTf:M RHR/10 j l

l HQIF,J1 l

These items are exempt under IRB 1220(b)(c) ASME Section XI 1974 Edition through Summer Addenda 1975. Refer to Code Category B-P for examination summary.

l l

l L

l l

Page 41

2 S _

4 e

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D REC ENC BI S MMG -

UAI T NX N E A

L -

P I

R X EY D WR REN OA ENO 2 4 N PM BI T O M I RU M M T.

UA TYAS NXE CRE ES -_

EALT -

PMCR SMUO NUNP .

I S P E . O %

KU DQN % 0 ERCS OE/ 0 0 CAI CR% 0 1 I ERD 1 VYTN R AA E0P S1 ZG N

I TN I I N

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TU -

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a +

INSERVICE INSPECTION

.10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING &- SUPPORT

SUMMARY

RHR/10 B-G-2 NOTE lt Relief from Code requirements.is requested. A visual examination of the component bolting will be made when the components are -

disassembled for other reasons. (See Attachment I, page I-8, f request 5).

)

l l

I 0

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)

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+

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Page 43

) i I:

-____-_--__-_-____._-_Y

ll ll 4 S 4 K 1 2 3 R

e A E E E g M T T T a E O O O P R N N N

_ D E .-

- ST ME % - - % -

%AL 4 6 0 XP 5 7 0 EM 1 O

C S

CM _

CA SXD GEE I T 4 - - 3 - 7 _

I E 1 2 LXL A P TTM OCO TEC S .

D REC ENC - -

BI S - - - -

MMG UAI T NX N E _

A _

L P

I R X

. EY D

- WR REN OA ENO 4 - - 3 - 7 N PM BI I 1 2 _

O M MMT I RU UAC TYAS NXE CRE ES EALT PMCR S MUO NUNP . _

I S P E .O % %

ERCS KU DQN OE/

5 - -

0 0

- 0 0 -_

CAI CR % 2 1 1 I E RD VYTN R AA E0P S1 ZG N TN N I I I O FP LI I AT

.P TA 6 0 0 0 0 7 A OL 2 3 _

TU S P E O M P A

J S

S _

A 1 1 1 1 1 1 L

C M . 0 EO 9 4 4 1 5 5 TN I 4 5 6 4 5 6 B B B B B B Y .

R _

EO 1 1 1 2 2 2 _

DG - - - - - -

OE K K K K K K CT - - - - - -

A B B B B B B C

M E 0 0 0 0 0 0 T 1 1 1 1 1 1 S / / / / / /

Y R R R R R R S H H H H H H R R R R R R

1

. . INSERVICE INSPECTION 10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

RHR/10 B-K-1 / B-K-2 llQTE_.lt This total includes three penetrations to pipe welds classified as E-D by later codes and the revised JAF ISI Program.

NOTE 2:

Relief from Code requirements is requested in Attachment I. 1 (See Attachment I, page I-12, request 8).

NOTE 3:

l Relief from Code requirements is requested in Attachment I. (See Attachment I, page I-17, request 9).

Page 45

l ljll S

K R e A t M o .

E N1 R

D E

_ ST

_ ME

%AL %

XP 1 EM 4 O

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CM

- CAD -

SXE -

GET

_ I E I L 5 LXP A

. M .

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D REC ENC BI S MMG -

UAI T NX N E A

L P -

I -

R DX .

EY RE -

WR ENN -

OA BI O N PM MMI 5 .

O M UAT .-

I RU NXC TYAS EE CRE S EALT PMCR _

SMUO NUNP I S P E .O KU DQN %

ERCS OE/ 0 CAI CR% 0 I ERD 1 VYTN R AA E0P S1 ZG N TN N I I I O FP LI I AT

.P TA 2 A OL 1 TU S P E O M P A _

J _

S S

A L 1 C _

M . 7 EO TN 6 I B Y

R EO 2 DG -

OE M CT -

A B L

M E 0 T 1 S /

Y R S H R

. . INSERVICE INSPECTION 10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

)

RHR/10 B-M-2 ,

NOTE le Relief from Code requirements is requested. A visual examination of the internal surfaces of valves will be made when valves are disassembled for other reasons.

(See Attachment I, page I-18, request 10).

I I

i I

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l l

1 Page 47 l

8 S 4 K R

e A g

M a E P R D

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- UAI .

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N PM MMI 0 O M UAT 0 I RU HXC 1 TYAS EE _

CRE S EALT _

PMCR -

SMUO NUNP I S P E .O KU DQN %

ERCS OE/ 0 CAI CR% 0 I ERD 1 VYTN R AA E0P S1 ZG _

N TN N S _

I I I O T _

FP LI N _

AT L E _

.I P TA L N _

A OL A O -

TUP P .

S M E O O M P C A

J S _

S _

A 1 L

C M . 1 EO 1 TN I 4 B

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I AT

.P TA A OL 6 TU S P E O :

M P .

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CT C A

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r a

INSERVICE INSPECTION 1 10 YEAR

SUMMARY

l JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

)

RHR HEAT EXCHANGERS NOTE la l

Reference letter-JPN-85-16, " Inservice Inspection Program",

dated March 4, 1985 (Attachment 1) for percentages to be completed during the 1st ten year interval on Class 2 Systems.

Page 50

~

1 S 5 K E R T e A O .

g M N1 a E P R *

- D E

ST ME %

%AL 0 _

XP 0 EM 1 O

C S

CM CAD SXE GET I E %

I L 0 LXP 0 _

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TTO OCC TE S

D .

REC E NC BI S _

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CT C A

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R H _ .

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6 .

' INSERVICE INSPECTION

.10 TEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

t RHR HEAT EXCHANGERS NOTE 1:

Reference letter JPN-85-16, " Inservice Inspection Program",

dated March 4, 1985 (Attachment 1}'for percentages to be completed during the 1st ten year interval on Class 2 Systems.

l l

i 1

i i

I.

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Page 52 1

1 1

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UAI

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J S

S A 2 L

C _

M . 3 EO TN 1 I C Y

R EO DG C OE -

CT C A

C M

E O T l S /

Y R S H R

INSERUICE INSPECTION 10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

RHR/10 i

C-C 1

NOTE 1:

Reference letter JPN-85-16, " Inservice Inspection Program",

dated March 4, 1985 (Attachment 1) for percentages to be completed during the 1st ten year interval on Class 2 systems.

l 1

1 I

l Page 54

5 S 5 K R

e A -

g M _

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%AL XP EM O

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CM CAD SXE GET I E 0 I L LXP -

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I R DX EY RE WR ENN OA BI Q N PM MMI 0 O M UAT I RU NXC TYAS EE CRE S EALT PMCR S MUO NUNP .

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A _

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Y R R R R R R S H H H H H H -+

R R R R R R u .

a G

INSERVICE INSPECTION 10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

RHR/10 C-E-1 / C-E-2 l

NOTE 1:

Reference letter JPN-85-16, " Inservice Inspection Program",

dated March 4, 1985 (Attachment 1) for percentages to be completed during the 1st ten year interval on Class 2 systems.

NOTE 2:

Relief is requested based on examination of 50% of the Coce l-requirements of one equivalent stream during'the six years of the "first" interval. One equivalent stream has been determined to contain 85 C-E-1 components. Examination of 50%

of these would require inspection of 43 components; a total of 29 were inspected. .Therefore, a total of fourteen support attachment welds to pressure retaining boundary inspections will be performed during the second interval. (See Attachment

I, page I-19, request 11).

l l

i Page 57 i

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M 12311 1 2311 12311 12311 E .

TO 22 234 2 2 234 2 2234 22 234 I N CCCCC CCCCC CCCCC CCCCC M

A .

AAAAA BBBBB AAAAA BBBBB E

R D. 33333 33 333 SSSSS 55555 TI S

E .

DT FFFFF FFFFF FFFFF FFFFF OA - - - - - - - - - - - - - - - - - - - -

CC CCCCC CCCCC CCCCC CCCCC M 00000 00000 0O000 00000 E 1 1 111 1 111 1 1 l 11 1 1 1 1 1 1 T ///// / / / / / ///// /////

S RRRRR RRRRR RRRRR RRRRR Y HHHHH HHHHH HHHHH HHHHH S RRRRR RRRRR RRRRR RRRRR

S S K S E 3, S E 3, E 3, S E 3, T E 3, T 2, O 2, R T T 2, O 2, 0

6 O T 2, O RI N1 N1 N1 O N1 e E N1 g R * * * *

a P

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M . 1231 1 12 3 11 12 311 1 2 311 12 311 EO . . . . .

TN 22 234 2 2 23 4 2 2 2 34 2 2 234 2 2 2 3 4 I CCCCC CCCCC CCCCC CCCCC CCCCC M .

A E D. AAAAA CCCCC BBBBB DDDDD AAAAA R I 66666 66 666 66 666 66666 77777 T

S E .

DT FFFFF FFFFF FFFFF FFFFF FFFFF OA - - - - - - - - - - - - - - - - - - - - - - - - -

CC CCCCC CCCCC CCCCC CCCCC CCCCC M 00000 00000 00000 00000 00000 E 1 1111 1 1 1 1 1 1 1 11 1 1 1 1 1 1 1 1 1 1 1 T // /// /// / / ///// / / / / / // ///

S RR RRR RRRRR R RR RR RRRR R RRRRR Y HHHHH HHHHH HHHHH HHHHH HHHHH S RRRRR RRRRR RR RRR RRRRR RR RRR

S K S E 3, S

E 3, S

E 3, S E 3, S E 3, R T 2, T2 T2 T 2, T2 A O O , O , O O ,

M N1 N1 N1 N1 N1

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P M O M T I R U P TYA S M CR E E 0 - 4 00 2 - 2 - 2 - 1 - - 2 - 1 E AL T X P MC R E S MU O NUN P I S P K U L E RC S B A CAI U T 6 - 8 - 1 9 - 9 - 9 - 2 - - 9 -

I E R D S O VYT N T R A A E 0 P S1 Z G N T N I I I S F P S I A

.P L 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 A C S

E M

A J

M . 1 2 3 1 1 1 2 3 1 1 1 2 3 1 1 12 3 1 1 1 2 E O . . . . . . .

T N 2 2 2 3 4 2 2 2 3 4 2 2 2 3 4 2 2 2 3 4 2 2 2 I CCC CC CCCC C C CCCC CCC CC CCC M .

A E D. BBB B B AAAA A C CCCC B BB B B DDD R I 7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 B 8 8 8 8 8 8 8 T

S E .

D T FFFFF FFFFF FFFFF FFF FF FF F OA - - - - - - - - - - - - - - - - - - - - - -

CC CCCCC CCCCC CCCCC CCCCC CCC M 000 00 0 0000 000 00 00 0 00 0000 E 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 T / / / / / / / / / / / / / / / / / / / / / /

S R R R R R R R R R R R R R R R R R R R R R R Y HHHHH HHHHH HHHHH HHHHH HHH S RR RR R R R R R R R R R RR RR R R R R R

l j!

S K S E 3, S E 3, S E 3, S E 3, S E 3, 2

6 R

A T 2, O T 2, O T 2, O T 2, O T 2, O

M N1 N1 N1 N1 N1 -

e E g R *

a P

% % % % S % %

E . 2 2 2 2 2 2 2 _

DQ / / / / / / /

OE 1 - 1 - 1 - 1 - 1 -

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.E ST %

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0 - 0 -

0 -

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C T

N R .I A E S X.

L BM P MAT 2 - 2 - 0 - 0 - 1 -

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E ALT X PMCR E SMUO NUNP

_ I S P KU L BA ERCS

_ CAI UT 9 - 0 - 9 - 5 - 9 -

I ERD SO 1 1 1 2 VYTN T R AA E0P S1 ZG N TN I I I S FP S I A 22 2 2 2 22 22 2 2 2 2 2 2 22 2 22 2 22 22

.P L A C S

E M

A J

M . 12 311 12311 12311 12311 12311 EO TN 22 2 34 2 22 34 2 22 34 2 2 234 2 2 2 3 4 I CCCCC CCCCC CCCCC CCCCC CCCCC M .

A E D. AAAAA BBB8B AAAAA BBBBB AAAAA RI 99 999 9999 9 00000 00000 1 11 11 T 1 1 1 1 1 1 11 1 1 1 1 11 1 S

E .

DT FFFFF FFFFF FFFFF FFFFF FFFFF OA - - - - - - - - - - - - - - - - - - - - - - - - -

CC CCCCC CCCCC CCCCC CCCCC CCCCC M 00000 00000 00000 0C000 00000 E 111 1 1 1 1 1 1 1 11 1 1 1 1l 1 1 1 1 1 1 1 1 T ///// / / /// / / / / / ///// / / ///

S RRRRR RRRRR RRRRR RRRRR RRR RR Y HHHHH HHHHH HHHHH HHHHH HHHHH S RRRRR RRRRR RRRRR RRRRR RRRRR

S K S E 3, S E 3, S E 3, S E 3, E R T 2, T 2, T 2, T 2, T A O O O O O4 M N1 N1 N1 N1 N 3

6 E

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OA N PM O M T I RU P TYAS M 0 -

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A D.

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E .

DT FFFFF FFFFF FFFFF FFFFFF OA - - - - - - - - - - - - - - - - - - - - -

CC CCCCC CCCCC CCCCC CCCCCC M 00000 00000 00000 000000 E 1 1 111 1 111 1 1 11 11 1 1 111 1 T ///// /// / / ///// //////

S RRRRR RRRRR RRRR R RR RRRR Y HHHHH HHHHH HHHHH HHHHHH S RRRRR RRRRR RRRRR RRRRRR l ll .

i INSERVICE INSPECTION 10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

j RHR/10 i C-F l NOTE 1:

Reference letter JPF-85-16, " Inservice Inspection Program",

dated March 4, 1985 (Attachment 1) for percentages to be completed during the 1st ten year interval on Class 2 systems.

NOTE 2:

The streams in each system have been identified by a number sequence with multiple streams being further defined by an alphabetical suffix.

NOTE 3:

Ihe percentages indicated in the column, % Code Req., apply to multiple streams in the following manner, i.e., Stream 6A, 6B, l 6C and 6D require a total of 12 1/2% for atny of/and or combin-ation of streams, not for each individual stream. These percentages are based on the relief request described in Note 1.

NOTE 4:

The final percentage and total number of additional inspections are based on the number of applicable components in one equivalent stream made up of the appropriate combination of equivalent sub-streams. In accordance with the request for relief for Code requirements for the Class Two systems, no additional inspections are required for Code Category C-F in the RER System.

Page 64

INSERVICE INSPECT 80N 10 YEAR

SUMMARY

J JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

RHR/10 C-F NOTE 42 Stream 2 requires (1) one additional examinations under Item No. C2.3.

NOTE 5.1 Stream 3 requires (3) three additional examinations under Item No. C2.1 with (1) one additional examination under Item No. C2.3.

NOTE 6:

Stream 5 requires (2) two additional examinations under Item No. C2.1. l NOTE 7:

1 Stream 6 requires (2) two additional examinations under Item No. C2.1. t NOTE 82 Stream 7 requires (1) one additional examination under Item No. C2.1 and (1) additional examination under Item No. C.2.3 and (1) additional examination under Item No. C4.1.

Page 65 t

INSERVICE INSPECTION 10 YEAR

SUMMARY

l JAMES A. FITZPATRICK NUCLEAR POWER PLANT J PIPING & SUPPORT

SUMMARY

]

j RHR/10 C-F NOTE 9:

1 1

Strecm 8 requires (1) one additior.a1 examination under Item 4 No. C2.'.

l NOTE 10:

j Stream 10 requires (2) two additional examinations under Item l C2.1 and (1) one additional examination under Item C.2.3.

l

! l NOTE 11: {

! Stream 11 requires (1) one additional examination under Item

! C2.1.

l l

l

.l l

l Page 66 l

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TN 2 2 2 34 22 2 34 2 22 34 22234 2 2234 I CCCCC CCCCC CCCCC CCCCC CCCCC M .

A D.

E AAAAA BBBBB 2 2 2 2 2 33333 AAAAA RI 4444 4 444 4 4 1 11 1 1 11 111 6 666 6 T 1 1 1 1 1 S

E .

DT GGGGG GGGGG GGGGG GGGGG GGGGG OA - - - - - - - - - - - - - - - - - - - - - - - - -

CC CCCCC CCCCC CCCCC CCCCC CCCCC M 00000 00000 00000 00000 00000 E 1 1 111 1 1 1 1 1 1 1 11 1 1 11 1 1 1 1 1 1 1 T ///// ///// ///// ///// / / / / /

S RRRRR RRRR R RR RRR RRRRR RRRRR Y HHHHH HHHHH HHHHH HHHHH HHHHH S RRRRR RRRRR RRRRR RRRRR RRRRR

8 6

e

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WR UXC OA NEE N PM S O M I RU TYAS CRE T EALT P PMCR M 5 -

S MUO E 2 NUNP X I S P E -

KU ERCS CAI

[ : RD E L VYTN BA R AA UT 5 -

E0P SO 2 S1 ZG T N TN I I I FP I

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A J

M . 12311 EO _

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A D.

E BBBB3 RI 66666 T 1 11 1 1 S

E .

DT GGGGG OA - - - - -

CC CCCCC M 00000 E 1 1 1 1 1 T //// /

S RRRRR Y HHHHH S RRRRR

INSEIVICE INSPEr/J'N.

10 YEAR SUMMAa*

JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

RHR/10 C-G NOTE lt Reference letter JPN-85-16, " Inservice Inspection Program",

dated March 4, 1985 (Attachment 1) for percentages to be completed during the 1st ten year interval on Class 2 systems.

I NOTE 2:

The items in each system have been identified by a number sequence with multiple stream being further defined by an alphabetical suf fix. !

I

.i

-1 1

I I

Page 69 I

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INSERVICE INSPECTION 10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING &- SUPPORT

SUMMARY

B-J SYSTEM RWC/12 1

.1 NOTE 1:

These items are exempted under IWB-1220 (b)(3)'ASME Section XI 1974 Edition'through Summer Addenda 1975. Refer to Code Category B-P for examination summary.

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INSERVICE INSPECTION 10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

I RWC/12 l

B-G-2 l

l NOTE 1:

l l Relief from Code requirements is requested. A visual )

examination of the valve bolting will be made when the valves j l '

are disassembled for other reasons. (See Attachment I, page l I-10, request 7).

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~0 INSERVICE INSPECTION {

10 YEAR

SUMMARY

I l' JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

j RWC-12 / B-K-1 & B-K-2 l

NOTE 1:

Relief from code requirements is requested.

(See Attachment I, page I-17, request 9).

l 1

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I INSERVICE INSPECTION l 10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

RWC / 12 Code Category B-M-2 l

NOTE 1: ;

Relief from code requirements is requested in Attachment I. A visual examination of the internal surfaces of valves will be made when valves are disassembled for other reasons.

(See Attachment I, page I-18, request 10).

t Page 78

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.y INSERVICE INSPECTION 10 YEAR

SUMMARY

JAMES A..FITZPATRICK NUCLEAR POWER' PLANT PIPING & SUPPORT

SUMMARY

')

B-J l SYSTEM RCIC/13 l

i NOTE 1.1 These items are exempt under IWB 1220(b)(3) ASME Section XI, I 1974 Edition through Summer Addenda 1975. Refer to Code Category B-P for examination summary.

l 1

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INSERVICE INSPECTION 10 YEAR

SUMMARY

I JAF NAPP PIPING & SUPPORT

SUMMARY

RCIC/ 13 B-G-2 i !

{ NOTE 1:

l Relief from code requirements is requested: visual examination of the valve bolting will be made when valves are disassembled for other reasons. (See Attachment I, page I-10, request 7).

l

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INSERVICE INSPECTION 10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

RCIC/13 B-K-1 & B-K-2 i

! ii i

l NOTE 1 i

This total includes one penetration to pipe weld classified as 1 E - B in the later Codes and in the revised JAF ISI program.

NOTE 2:

I, Relief from Code requirements is requested. ]

(See Attachment I, page I-17, request 9). !

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INSERVICE INSPECTION :

10 YEAR SYJMMARY j JAMES A. FITZPATRICK NUCLEAR POWER PLANT f PIPING & SUPPORT

SUMMARY

l RCIC/13 l Code Category B-M-2 l

I 1

f 1

4 NOTE 1 1

Relief from' Code requirements is requested in Attachment I. Visual j examinations of the internal surfaces of valves will be made when i

. valves are disassembled for other reasons. (See Attachment I, page I-18, request 10).

i

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. n.

INSERVICE INSPECTION

10. YEAR

SUMMARY

j l

JAMES u. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

RCIC/13 C-E-l'& C-E-2 NOTE 1 Reference letter JPN-85-16, " Inservice' Program", dated March 4, 1985 (Attachment 1) for percentages to be completed during the 1st ten year interval on Class 3 Systems.

ROIE 21 One addit onal surface examination will be required under item No. C2.5 (See Attachment I, page I-19, request 11).

')

i l

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Page 90 i

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t' INSERVICE INSPECTION !

10 YEAR

SUMMARY

j JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

3 CF l

~

' SYSTEM RCIC/13

, NOTE 11 Reference letter.'JPN-85-16, " Inservice Program", dated March j j 4, 1985 (Attachment 1) for percentages'to be completed during j the 1st ten year interval on Class 2 Systems. l i

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I INSERVICE INSPECTION 10 YEAR

SUMMARY

I JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

B-J SYSTEM CS/14 ,

NOTE 1:

[ Refer to Code Category B-P for examination summary.

l i

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INSERVICE INSPECTION 10 YEAR SUMMI.RY JAMES A. FITZPATRICK NUCLEAR POWER PLANT j PIPING & SUPPORT

SUMMARY

l

CS / 14 B-G-2 l

l '

NOTE 1:

Relief from Code requirements is requested. Visual examination of the valve bolting will be made when the valves are disassembled for other reasons. (See Attachment I, page I-10, request 7).

l l

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INSERVICE INSPECTION 10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

I l

CS/14 l

B-K-1 i ,

I l

I i

NOTE 1:

This total includes t*:o penetration to pipe welds classified l as E-B in the later codes and the revised JAF ISI program. j{

l NOTE 2: i Relief from Code requirements is requested. (See Attachment I, page I-12, request 8).

l l

1 Page 99 l l

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l

INSERVICE INSPECTION 10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT j' PIPING & SUPPORT

SUMMARY

CS/14 i

I Code Category B-M-2 NOTE 1: )

i Relief from Code requirements is requested. Visual examination of interval surfaces of valves will be made when l valves are disassembled for other reasons.

(See Attachment I, page I-18, request 10).

1 l

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l Page 101

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INSERVICE INSPECTION 10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

C-C SYSTEM CS/14 NOTE 1:

Reference letter JPN-85-16, " Inservice Inspection Programs",

dated March 4, 1985 (Attachment 1) for percentages to be completed during Ist ten year interval of Class 2 systems.

l I

Page 104 I

i l

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CT C C C C C C A _

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S S S S S S S C C C C C C

INSERVICE INSPECTION ;

10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

C-E-1 / C-E-2 SYSTEM CS/14 NOTE 1:

l Reference letter, JPN-85-16, " Inservice Inspection Program",

dated March 4, 1985 (Attachment 1) for percentages to be completed during the 1st ten year interval on Class 2 systems.

NOTE 2 Additional examinations; (4) fear support attachment welds to the pressure retaining boundary. (See Attachment I, page I-19, request 11).

l Page 106

i j j

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A R D. AAAAA BBBBB AAAAA BBBBB AAAAA _

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DT GGGGG GGGGG GGGGG GGGGG GGGGG OA - - - - - - - - - - - - - - - - - - - - - - - - -

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E 44 4 44 444 44 -

T 1 1 111 11 111 4 4 4 44 4 4 4 44 44 4 44 _

S ///// ///// 1 111 1 1 1 1 11 1 1 1 1 1 _

Y SSSSS SSSSS ///// ///// /////

S CCCCC CCCCC SSSSS SSSSS SSSSS CCCCC CCCCC CCCCC

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BBBBB AAAAA BBBBB _

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OA - - - - - - - - - - - - - - -

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E 444 4 4 44 4 44 4 4 4 44 T 1 1 1 1 1 1 11 1 1 11 1 11 .

S / / / / / / / / / / /////

Y SSSSS SSSSS SSSSS S CCCCC CCCCC CCCCC

INSERVICE INSPECTION 10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

C-G SYSTEM CS/14 1

NOTE 1:

Reference letter JPN-85-16, " Inservice Inspection Program",

dated March 4, 1985 (Attachment 1) for percentages to be completed during the 1st ten year interval on Class 2 systems. ;

i l

i i

l 1

I Page log 5

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KU E .O ERCS DQN % %

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\

l INSERVICE INSPECTION 10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT l PIPING & SUPPORT

SUMMARY

B-J SYSTEM HPCI/23 !

l NOTE 1:

Refer to Code Category B-P for examination summary.

l l

l Page 111 i . . . . . . . . _

I 11 S

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Y -

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[

INSERVICE INSPECTION 10 YEAR

SUMMARY

JAMES A..FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

HPCI/23' B-G-2 NOTE le j i

Relief from code requirements is requested. A visual j l

examination of the valve bolting will be made when the valves are disassembled for other reasons. (See Attachment I,.page -

I-10, request 7).

1

.r i

l i l

.l 1

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D REC ENC - - - -

BI S - -

MMG UAI T NX N E A

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I R DX E Y RE WR ENN OA BI O 4 0 2 N PM MMI 3 0 0 O M UAT I RU NXC TYAS EE CRE S EALT PMCR SMUO NUNP .

I S P E .O 0

KU DQN % 0 0 0 0 ERCS OE/ 5 0 0 CAI CR% 2 1 1 I ERD VYTN AA i

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A _

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0 M . 9 4 4 1 4 4 EO TN 4 5 6 4 5 5 I B B B B B B Y 2 2 2 R 1 1 1 _

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CT B B B B B B _

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_ M E 3 3 3 3 3 3 T 2 2 2 2 2 2 S / / / / / /

Y I I I I I I S C C C C C C P P P P P P H H H H H H

o e l

INSERVICE INSPECTION j 10 YEAR

SUMMARY

I JAMES A. FITZPATRICK NUCLEAR POWER PLANT I

( \

l PIPING & SUPPORT

SUMMARY

I HCPI/23 l l

B-K-1 l

( NOTE le This total includes one penetration to pipe weld classified as E-B in the new Codes and the revised JAF ISI program.

NOTE 2:

Relief from code requirements is requested. (See Attachment I, page I-12, request 8).

i l

Page 115 l

l

I jl S

K R E A T .

6 M O 1 1 E N 1 R e D g E _

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D .

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_ PMCR SMUO NUNP .

I S P E .O KU DQN 0 ERCS OE / 0 CAI CR% 1 I ER D VYTN R AA E0P S1 ZG N TN N I I I O FP LI .

I AT

.P TA 4 A OL TU S P E O M P A

J S

S A 1 L

C _

M . 7 EO TN 6 I B Y

R EO 2 DG -

OE M CT -

A B C

M 3 E 2 T /

S I Y C S P H

. e l

4 INSERVICE INSPECTION 10 YEAR

SUMMARY

l JAMES A. FITZPATRICK NUCLEAR POWER PLANT l PIPING & SUPPORT

SUMMARY

i l

l

! SYSTEM HPCI/23 l B-M-2 I

l l

l NOTE 1r l Relief from Code requirements is requested in Attachment I.

Visual examination of the internal surfaces of valves will be j made when valves are disassembled for other reasons. (See Attachment I, page I-18, request 10). j Page 117 l

l 1

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.P TA L N A OL L O TU A P S P M E O O M P C A

J S

S A 1 L

C M . 1 1 _

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R 1 1 1 2 2 2 EO - - - - - -

DG E E E E E E OE - - - - - -

CT C C C C C C _

A C

M 3 3 3 3 3 E 2 2 3 2 2 2 T / / 2 / / /

S I I I I I I Y C C C C C C S P P P P P P H H H H H H

5 - 9 INSERVICE INSPECTION 10 YEAR

SUMMARY

~

JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

HPCI/23 i

C-E-1 & C-E-2 NOTE 1.

Reference letter JPN-85-16, " Inservice Inspection Program",

dated March 4, 1985 (Attachment 1) percentages to be completed during the 1st ten year interval on Class 2 systems.

1 I

l I

Page 120

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2 2 2 2 2 2 1 1 1 1 1 1 D

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XP 2 0 0 9 EM 5 5 1 O

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P MAT 5 - 4 - 0 - - 2 - - - - 5 -

UXC R NE E E Y S WR O A N P M O M T I R U P TYA S M 5 - -

CR E E 0 - 0 - 1 - - 0 - - - - 0 - 1 EAL T X P MC R ) E S MU O Y NUN P R I S P A K U M L ERC S M BA -

CAI U UT 2 07 - - 8 01 00 4 00 00 6 06 0 -

I ER D S S O 2 2 1 VYT N ( T R A A E 0 P S1 Z G N T N I I I S F P S I A 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2

. P L A C S

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M . 1 2 31 1 1 2 3 11 1 23 1 1 1 2 3 1 1 E O . . . . . .

TN 2 2 2 3 4 2 2 2 3 4 2 2 2 3 4 2 2 2 3 4 I C CCCC CCC CC CCC CC C CCCC M .

A E D.

R I 1 1 1 1 1 2 2 2 2 2 333 33 4 4 4 4 4 T

S

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D T FFFFF FF FFF FFF FF FFF F F OA - - - - - - - - - - - - - - - - - - - -

CC CCCCC CCCCC CCCCC CCCCC M 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 33 3 E 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 T / / / / / / / / / / / / / / / / / / / /

S I I I I I I I I I I I I I I I I I I I I Y CCCCC CCCCC CCCCC CCCCC S PP PP P P P PPP P P P P P P PP P P HHHHH HHHHH HHHHH HHHHH l

. l l

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A O . O . O . O . -

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XP 1 1 0 .

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UXC R NEE EY S WR OA N PM O M T I RU P TYAS M 1 - 0 - 0 -

CRE E 3 -

EALT X PMCR E S MUO -

NUNP I S P KU L ERCS BA CAI UT 4 - 8 - 0 - 6 -

I ERD SO 2 2 1 VYTN T R

E0P AA -

S1 ZG N TN I I I S FP S I A 222 - - 2222 2 22 22 2 22 22 2

.P L A C S

E M

A J

M . 12311 12 3 11 12311 12311 EO TN 22 2 3 4 22 234 2 2 2 34 2 22 34 I CCCCC CCCCC CCCCC CCCCC M .

A D.

E _

RI 5S555 66666 77777 B8888 _

T _

S .

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DT GGGGG GGGGG GGGGG GGGGG OA - - - - - - - - - - - - - - - - - - - -

CC CCCCC CCCCC CCCCC CCCCC I

M 33333 33333 33333 33333 E 2 2 2 22 22 222 2 22 2 2 2 22 2 2 T ///// / //// ///// / / / //

S I I I I I I I I I I I I I I I I I I I I Y CCCCC CCCCC CCCCC CCCCC S PPPPP PPPPP PPPPP PPP PP HHHHH HHHHH HHHHH HHHHH

INSERVICE INSPECTION 10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

C-G SYSTEM HPCI/23 NOTE 1:

Reference letter JPN-85-16, " Inservice Inspection Program",

dated March 4, 1985 (Attachment 1) for percentages to be l completed during the 1st ten year interval on Class 2 systems, FOTE 31 One (1) additional examination will be required under Stream 1A, Item No. C2.3 and Stream 4A, Item No. C2.3 l

J i

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l Page 123

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LXP 1 A M TTO OCC _

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NUNP I S P E .O %

KU DQN % - 0 0 5

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C M

_ E 7 7 7 7 7 7 T 2 2 2 2 2 2 S / / / / / /

_ Y D D D D D D S A A A A A A C C C C C C

-l INSERVICE INSPECTION 10 YEAR

SUMMARY

JAMES'A. FITZPATRICK NUCLEAR POWER PLANT *i PIPIliG & SUPPORT

SUMMARY

-l l

C-E-1 / C-E-2 >

l SYSTEM CAD /27

's FOTE lt Reference letter JPN-85-16, " Inservice Inspection Program", j dated March 4, 1985 for percentages to be completed during the 1st ten year interval on Class 2 systems.

i NOTE 2r Additional examination required; (1) one support attachment weld to the pressure retaining boundary. (See Attachment I, ,,

l page I-19, request 11).

t I

l 1

h I

Page 125 h

6 2

1 S S S S K E . E . E .

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OE / / / / / 4 4 CR% 1 - - - - 1 - - - - 1 - 1 - - - - / - / - -

1 1 6 6 6 6 6 6 6 D

. E ST ME 0 - - - - 0 0 - - - - 0 -

%AL 0 - - - - 1 XP EM O

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MAT R UXC 0 - 0 -

E Y NEE W R S O A N P M O M I R U T TYA S P 0 - 2 - - - - 0 -

CRE M EAL T E 0 - 0 -

PMC R X SMU O E NUN P I S P K U ERC S L CAI BA I ER D UT 3 - 3 - 9 - 3 - - - - 4 -

VYT N SO 1 R A A T E0P S1Z G N T f I I I F P S I S

. P A 22222 22222 22222 22 222 222 22 A L C

S E

M A

J M . 12311 12311 12311 12311 12311 EO TN 222 34 2 2234 22234 22234 22234 I CCCCC CCCCC CCCCC CCCCC CCCCC M .

A E D. AAAAA BBBB8 AAAAA AAAAA BBBBB RI 1 1 1I 1 11 1 1 1 22 2 2 2 3 3333 33333 T

S ,

E .

DT GGGGG GGGGG GGGGG GGGGG GGGGG OA - - - - - - - - - - - - - - - - - - - - - - - - -

CC CCCCC CCCCC CCCCC CCCCC CCCCC M 77777 77777 777 77 77777 77777 E 222 22 22222 222 22 2 2 1 22 2 2 2 2 2 T / //// ///// ///// ///// / / / / /

S DDDDD DDDDD DDDDD DDDDD DDDDD Y AAAAA AAAAA AAAAA AAAAA AAAAA S CCCCC CCCCC CCCCC CCCCC CCCCC I

_ S S S S K E . E . E .

R T 2, T2 T2 A O O , O ,

7 M N1 N1 N1 2 E R * *

_ 1

_e

. g

_ a

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_ E . % % %

D Q 4 4 % % 4

/ - - - - / - - - - 4 4 /

_ O E / - - - 1 - 1 C R% 1 1 / - -

1 1 6 6 6

- 6 6 D

.E S T ME J L 5 - - - -

9 - - - - 0 - % - - - - 0 - 0 XP 2 1 0 EM 1 O

C '

T R .I N E A B S M X.

L M A T 1 - - - - 1 - - - - 0 - 1 - - - - 0 - 0 P U XC N EE R S E Y W R O A N P M T O M P I R U M TYA S E 0 - - - - 2 - - - - 0 - 0 - - - - 0 - 0 CR E X E AL T E P MC R S MU O NUN P I S P L K U BA E RC S UT 4 - - - - 2 - - - - 0 - - - - 0 - 1 CAI S O 1 5 - 1 1 I E R D T VYT N R A A E 0 P S 1 Z G N T N S I I I S F P A 2 2 2 2 2 2 2 2 2 2 2 2 2 I L 2 2 2 2 2 2 2 2 2 2

. P C A

S E

M A 1 1 1 J M .

E O 1

2 3 11 12 31 1 1 2 3 1 1 1

.23 .

2 TN 2 2 2 3 4 2 2 2 34 2 2 2 3 4 2 2 2 3 4 2 2 2 I CCCCC CC CCC CCCCC CCCC C CCC M .

A E D. 4 4 4 4 4 AA AAA B BBBB AAAA A B B R I S5 S5 5 55 5 S5 666 6 6 6 6 6 T

S E .

D T GGGGG GGGGG GGGGG GGGGG GGG OA - - - - . - - - - - - - - - - - - - - - - -

CC CCCCC CCCCC CCCCC CCCCC CCC M 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 # 7 7 7 7 E 2 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 T ///// ///// / / / / / / / / / / / / /

S DDDDD DDDDD DDDDD DDDDD DDD Y AAAAA AAAAA AAAAA AAAAA AAA S CCCLC CCCCC CCCCC CCCCC CCC

]lll1 j l A

. ~ _

S S S K E . E .

R A T 2, O

T O 2, 8 M N1 N1 2 E 1 R *

e g -

a P

E . % %

DQ 4 4 OE / /

CR% 1 - - - - - - - - - - - - - - 1 - - - -

6 6 D

. E ST %

ME - - - - - - - - - - 8 - - - -

%AL 0 - - - -

XP EM O

C T R .I N E A BMS X. - - - - - - - - - - 1 - - - -

L MAT 0 - - - -

P UXC NEE .

R S _

EY WR l

1.

OA N PM T O M P I RU M 0 - - - -

TYAS E 0 - - - -

CRE X EALT E PMCR SMUO NUNP I S P L T. U BA ERCS UT 0 - - - - 0 0 - - 0 - 2 -

CAI SO 1 1 1 1 I ERD T VYTN R AA E0P S1 ZG N TN S I I I S FP A 2222 2 22222 222 22 22222 I L

.P C A

S E

M A

J M . 12311 12311 12311 12311 EO .

TN 22234 22234 222 34 2 2234 I CCCCC CCCCC CCCCC CCCCC M .

A E D. CCCCC DDDDD EEEEE 77777 RI 66666 66666 66666 T

S E .

DT GGGGG GGGGG GGGGG GGGGG .

OA - - - - - - - - - - - - - - - - - - - - _

CC CCCCC CCCCC CPCCC CCCCC .

M 77777 7777 7 77777 77777 _

E 22 2 22 22 2 22 22222 22222 _

T / / / / / ///// ///// ///// -

S DDDDD DDDDD DDDDD DDDDD Y AAAAA AAAAA AAAAA AAAAA S CCCCC CCCCC CCCCC CCCCC

INSERVICE INSPECTION k 10 YFAR

SUMMARY

4

{

JAMES A. FITZPATWICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

CAD /27 l C -G f

1 NOTE 1:

Reference letter JPN-85-16, " Inservice Inspection Program". j dated March 4, 1985 (Attachment 1) for percentages to be completed during the 1st year interval on Class 2 systems. !

t I

j EOTE 2 1 Two (2) additional examinations will be required under Item No. C?. 1 (See Attachment I, page I-20, request 12).

I i

i l

i j

i Page 129 j

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K E _

R E E E T _

0 A T T T O _

3 M O . O . O

N 1 E N2 N1 N _

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P ST ME % % %

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C _

S CM _

CAD SXE GET 7 7 I E I L 6 - 1 2 3 LXP 3 A

TTO M _

OCC TE S

D REC -

E NC BI S - -

MMG - - -

UAI T NX N E A

L P

I R DX O EY RE . .

WR ENN L O . R OA BI O O R 2 L D 2 - 2

_ N PM MMI V D - - O Y - -

O M UAT Y T V H T H

I RU NXC 2 V - V

_ TYAS EE 3 - 1 7 CRE S #_ 2 EALT PMCR SMUO NUNP . 7 0 I S P E . O 2 3 7 3 KU DQN / / / /

ERCS OE/ % - % % %

CAI CR% 5 5 5 5 I ERD 2 2 2 2 VYTN

_ R AA E0P S1 ZG N TN N I I I O

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C

/ _

M . 5 6 7 8 5 7 EO TN 4 4 4 4 4 4 I B B B B B B .

Y R :

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_ DG J J J J : J A

_ OE - - - - L - T A

CT B B B B B O T T A

C O T

M E 9 9 9 9 - 9 T 2 2 2 2 B 2 S / / / / U /

Y S S S S S S _

S M M M M M

I INSERVICE INSPECTION 10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

B-J SYSTEM MS/29 l

NOTE 11 i

Although only (1) one category B-J Item No. 4.7 weld was inspected, the category B-J percentage for Item No.'s 4,5, and 4.7 meets the ASME Section XI requirements.

NOTE 2:

Refer to Code Category B-P for examination summary.

Page 131 t

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OCO m .

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D m REC o.

ENC at BI S MMG - _

UAI T NX N E A

L I t _

P -

I R X EY D WR REN OA ENO 7 N PM BI I 1 O M MMT I RU UAC TYAS NXE CRE ES EALT

- PMCR S MUO

_ NUNP .

I S P E .O -

KU DQN % ._

ERCS OE/ 0 .,

CR% .,

. CAI 0 __

I ERD 1 _

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FP LI _

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M P A _

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OE G CT -

A B C

s M

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S 2 _

Y /

S S M

1ll i 1llllll llllIill i ; II

. 4 l

INSERVICE INSPECTION 10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT l PIPING & SUPPORT

SUMMARY

l B-G-2 SYSTEM MS/29 ,

l l

I

! NOfE 12 l l

Relief from Code requirements is requested. A visual examination of the valve bolting will be made when the j valves are disassembled for other reasons. (See Attachment I, l l page I-10, request 7). l l

l I

l a

1 i

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i Page 133 i

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S K E E ._

R T . T .

A O1 O . _

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XP 5 9 _

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. CAD SXE GET

_ I E 5 - -

_ I L 4 - -

5 LXP 2

_ A M

_ TTO

. OCC

- TE

_ S

_ D REC ENC -

BI S

- MMG - - - - -

UAI NX

- T N E A

L P

_ I R DX EY RE WR ENN OA BI O 3 5

N PM MMI 2 - -

5 O M UAT - -

I RU NXC TYAS EE S

CRE .

EALT PMCR SMUO NUNP .

I S P E .O KU DQN % 0 ERCS OE/ 5 - - 0 - -

. CAI CR% 2 1 I ERD VYTN R AA E0P S1 ZG N TN N I I I O FP LI AT ._

.I P TA _

A OL 6 0 0 8 0 0 TU 4 5 -

S P E O -

M P A

J S _

S A 1 1 1 1 1 1 L

C 0

M . 9 4 4 1 5 5 EO TN 4 5 6 4 5 6 I B B B B B B Y

R 1 1 1 2 2 2 EO - - - - - -

DG K K K K K K OE - - - - - -

CT B B B B B B A

C M

E T 9 9 9 9 9 9 S 2 2 2 2 2 2 Y / / / / / / -

S S S S S S S M M M M M M -

INSERVICE INSPECTION i 10 YEAR

SUMMARY

j JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

I l

r

( B-K-1 / B-K-2 SYSTEM MS/29 l l l NOTE la l

l l

This total includes two penetration to pipe welds classifed as I

! E-D in the later codes and the revised JAF ISI program. I NOTE 2:

Relief from Code requirements is requested.

1 i

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Page 135 l t

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CA

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I

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_ LXL A P -

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D

. REC ENC BI S _

M' G -

T UMI NX N E A -

L $4 P

I -

R X -

EY D -

WR REN .

OA ENO 7 -

N PM BI I -

O M MMT -

I RU UAC .

_ TYAS NXE -

ES

_ CRE

- EALT PMCR S MUO NUNP .

I S P E .O KU DQN %

ERCS OE/ 0 CAI CR% 0 1 -

I ERD .

VYTN R AA E0P S1 ZG N TN N I I I O -

FP LI I AT

.P TA 9 A OL 1 TU S P E O M P A

J t I ! _

S S

A

- 1 L

C M .

EO 7 TN I 6 B _

Y R

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A B C

M E

T 9 S 2 Y /

S S M

. =

INSERVICE INSPECTION 10 YEAR

SUMMARY

q JAMES A. FITZPATRICK NUCLEAR POWER PLANT !

PIPING & SUPPORT

SUMMARY

1 Code Category B-M-2 j SYSTEM MS/29 l 1

NOTE 1:

Relief from Code requirements is requested in Attachment I.

Visual examination of the internal surfaces of valves will be made when valves are disassembled for other reasons. (See ,

Attachment I, page I-18, request 10). l l

i l

l l Page 137 l

l.

l

8 3 S 1 K R

e A g M a E P R k

D E

ST ME %

%AL 0 XP 0 EM 1 O

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CM CA SXD GEE I T %

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D REC ENC

- BI S MMG -

UAI T NX N E A

L -

P I

R X EY D WR REN OA ENO %

N PM BI I 0 O M MMT 0 I RU UAC 1 TYAS NXE CRE ES EALT PMCR .

SMUO NUNP .

I S P E .O KU DQN %

ERCS OE/ 0 CAI CR% 0 -

I ERD 1 -

VYTN R AA E0P S1 ZG N TN N S _

I I I O T FP LI N I AT L E

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S -

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Y -

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I L 5 - - 5 LXP 3 A M TTO OCC TE S

REC ENC D _

BI S MMG - - - -

T N

UAI NX E

A L

P I

R DX .

EY RF O O WR EN? I R R OA BI O D 2 - D 2 N PM MMI 3 Y - - Y -

O M UAT 3 H T H T -

I RU NXC - V - V EE 5 TYAS S 2 -

CRE EALT +

PMCR SMUO NUNP . _

I S P E .O -

KU DQN % %

ERCS OE/ 5 - - 5 CAI CR% 2 2 I ERD _

VYTN R

E0P AA _

S1 ZG -

N TN N I I I O FP LI AT

.IP TA 0 5 A OL 5 0 TU 7 S P E O -

M P -

A J

S _

S A 1 1 1 1 L

C -

_ M . 5 6 7 8 EO 4 TN 4 4 4 B B I B B ,

Y R

EO DG ' J J J OE ~ - - -

CT B B B B -

A C

M 4 E 4 4 4 T 3 3 3 3 S / / / /

Y W W W W S F E F F i I lI lll

. a ;

INSERVICE INSPECTION 10 YEAR

SUMMARY

JAMES A. FIT" PATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

FW/34 l

B-J NOTE 1:

Refer to Code Category B-P for examination summary.

I 1

l l

Page 340 4

S K E -

R T A O . -

N1 M

E -

1 R * -

4 -

1 D -

E -

e ST g ME %

a %AL 0 -

P XP 5 -

EM -

O -

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S CM CAD SXE GET I E I L 3 LXP A M TTO OCC TE S

D REC ENC BI S MMG -

UAI T NX N E -

A -

L P

R EY WR RE ENN DX I

OA BI O N PM MMI 3 O M UAT RU NXC I

TYAS CRE EE S

EALT PMCR ,

SMUO NUNP .

I S P E .C KU DQN %

ERCS OE/ 0 CAI CR % 0 I ERD 1 VYTN -

R AA E0P S1 ZG N TN N I I I O FP

.P I

LI AT TA 6 A OL TU S P E O M

A J

P S

S A 1 L

C M . 9 EO TN 6 I B Y

R 2 EO -

DG G OE -

CT B A

C M

E T 4 S 3 Y /

S W l

F

, 4 INSERVICE INSPECTION 10 YEAR

SUMMARY

l JAMES A. FITZPATRICK NUCLEAR POWER PLANT l PIPING & SUPPORT

SUMMARY

B-G-2 SYSTEM FW/34 j NOTE 3:

l Relief from Code requirements is requested. A visual examination of the valve bolting will be made when the valves are disassembled for other reasons. (See Attachment I, page l

I-10, request 7).

l l

l i

)

(

1 i

i i

4 Page 142 I

I i

a p

- S 3 K E

_ 4 R T .

1 A O1 M N e E g R

a P D E

ST %

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%AL 1 - - 0 - - _

XP 6 0 _

EM 1 .

O _

_ C S

_ CM

_ CAD SXE GET I E - _

_ I L 1 - - 6 LXP 1 2 A M TTO

_ OCC

_ TE S

_ D REC ENC - -

BI S -

MMG - - _

UAI ._

T NX _

N E _

A _

L -

P -

I DX R

EY WR RE ENN OA BI O 1 6 0 0

_ N PM MMI 1 - - 2 O M UAT I RU NXC -

TYAS EE CRE S EALT PMCR SMUO NUNP .

I S P E .O %

KU DQM % 0 ERCS 0 0 0 -

OE/ 5 - -

CAI CR% 2 1 I ERD VYTN R AA _

E0P S1 ZG N TN N -

I I I O FP LI I AT

.P TA 8 6 -

A OL 1 0 0 2 0 0 TU S P E O M P A

J S

S A 1 1 1 1 0 0 L

C 0 -

M . 9 4 4 1 5 5 EO -

TN 4 5 6 4 5 6 I B B B B B B Y

R 1 1 1 2 2 2 EO - - - - - -

DG K K K K K K OE - - - - - -

CT B B B B B B A

C M .

E T

S 4

3 4

3 -

Y / / / / / /

S W W W W F

W W F F F F F .

{f l!ll ll

' INSERVICE INSPECTION 10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT PIPING & SUPPORT

SUMMARY

FW/34 -l B-K-1 l

NOTE 1:

This total includes two penetration to pipe welds classified as E-B in the later Codes and the revised JAF ISI program.

NOTE 2:

Relief from Code requirements is requested. (See Attachment j I, page I-12, request 8).

i f

i l

i j

Page 144 I

l l

l i l

lfII' S

K R E A T M O .

E N 1 R

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%AL

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I T _

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D .

REC +.

ENC _

BI S _

MMG -

UAI T NX N E ._

A L

P I _

R X EY D WR REN _

OA ENO 1 2 N PM BI I -

O M MMT I RU UAC TYAS NXE CRE ES EALT PMCR 3 SMUO NUNP . .

I S P E .O KU DQN ERCS OE/ 0 CAI CR% 0 I ERD 1 VYTN R AA E0P S1ZG N TN N I I I O FP LI m AT I _

.P TA 6 _

A OL _

TU S P E O M P u_

A m.

J _

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A B C

M E

T 4 S 3 Y /

S W F w m

i ! i l11l l! llIll l E

L

INSERVICE INSPECTION 10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAP POWER PLANT PIPING '& SUPPORT

SUMMARY

-j i

r FW/34 Code Category B-M-2 j i

NOTE _11 1

Relief from Code requirements is requested in Attachment I. A visual examination of internal surfaces of values will be made when valves are disassembled for other reasons. -(See l Attachment I, page I-18, request 10).

l l'

i l

l-l l

Page 146 I

l

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I _

R X EY D WR REN %

OA ENO 0 N PM BI I 0 O M MMT 1 I RU UAC TYAS NXE CRE ES _

EALT PMCR SMUO NUNP . _

I S P E .O % _

KU DQN 0

_ ERCS OE/ 0 CAI CR% 1 I ERD VYTN R AA __

E0P S1 ZG N TN N

_ I II O S FP LI T _

_ I AT N

.P TA L E _

_ A OL L N _

TU A O S P P _

E O M M P O

_ A C J

S

_ S

_ A 1

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_. C M .

EO 1 TN 1 I

4 B

Y R

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CT B A

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l I l4lll t1

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4 M O 1 E N R

_ eg D

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D REC ENC BI S MMG 0 UAI T NX .

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A -

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I R DX EY RE WR ENN OA BI O 2 N PM MMI O M UAT I RU NXC TYAS EE -

CRE S EALT PMCR SMUO NUNP .

I S P E .O KU DQN 0 ERCS OE/ 0 CAI CR% 1 I ERD VYTN R AA E0P -

S1 ZG N TN N I I I O FP LI I AT

.P TA A OL 2 TU S P E G M P A -

J -

S S

A 1 L

C -

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EO TN l I

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OE -

CT B A

C M .

E u T P r S T Mt Y E U s S J P n I

i g -

e S

K R E A T

M O 9 E N 4 R 1

D e E g ST a ME P %AL XP 0 EM O

C S

CM CAD SXE GET I E I L 0 LXP _

A M TTO OCC TE S

D REC ENC BI S -

MMG 0 _

UAI T NX N E A

L P

I DX R _

EY RE -

WR ENN OA BI O 0 N PM MMI O M UAT I RU NXC _

TYAS EE _

CRE S -

EALT PMCR SMUO NUNP .

I S P E .O KU DQN %

ERCS OE / 5 .

CAI CR% 2 I ERD VYTN R AA E0P S1 ZG N TN N I I I O FP LI I AT

. P TA A OL 6 TU S P E O M P A

J S

S A 1 _

L _

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M . 6 L EO _

TN 4 I B Y _

R _

EO DG J OE -

CT B _

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C M

E T P S T M Y E U S J P

4 INSERVICE. INSPECTION 10 YEAR

SUMMARY

JAMES A. FITZPATRICK NUCLEAR POWER PLANT l PIPING & SUPPORT

SUMMARY

B-F JET PUMP INSTRUMENT NOTE 1:

A visual examination (VT-1) was performed on weld N-8A-SE in lieu of the Code requirement surface examination due to excessively high radiation levels of approximately 40 rem /hr.

on contact (1985 Refuel Outage).

Attachment 3 details the radiation curve performed at that time. (See Attachment I, page I-7, request 3).

NOTE 11 The required percentages shall be examined during the next scheduled refuel outage. (See Attachment I, page I-7, request 3).

i l,

l i

Page 150

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.-.~..y ,,g a i o, . ATTACHMENT IV TO JPN-87-043 ) IFSERVICE INSPECTION PROGRAM FOR WELDS & SUPPORTS FIRST TEN-YEAR INTERVAL ; I l !l l l HYDROSTATIC AND PRESSURE TESTS l l l l l New York Power Authority James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 DPR-59 } , s. ATTACHMENT IV HYDROSTATIC AND PRESSURE TESTS i l CLASS I One hydrostatic test of the pressure retaining components, including the Reactor Vessel, was performed in 1985 in accordance with IWA 5000 and i l IWB 5000 of the 1974 Edition through Summer 1975 l I Addenda of ASME Section XI. CLASS II Hydrostatic tests have been partially completed as and RCIC detailed in Reference 5. These tests are to be Class III completed during the next refueling outage. l Piping CLASS II Pressure tests were performed in accordance with Table 1.1 of the JAF weld and support ISI Program. These tests were performed at a frequency of once every 3-1/3 years from May 1979 until 1985. Accordingly, each of the following systems was tested at least twice during that six year period. Residual Heat Removal (RHR) Core Spray High Pressure Coolant Injection (HPCI) CLASS III System Inservice and Functional Tests were performed in accordance with IWD 5000 of the 1978 Addenda of ASME Section XI at a frequency of 4 times per 10 year interval from May 1979 until 1985. Each of the following systems was tested at least three times during that interval: RHR Service Water Control Room Service & Chilled Water Reactor Building Closed Loop Cooling Water; l Emergency Service Water; and Service Water. Emergency Diesel Generator (EDG) Air Start System j 4 EDG Fuel Oil Piping i EDG Cooling Water Fuel Pool Cooling The RCIC Class III piping was flow tested at least 3 ! times and had one pressure test performed, in j accordance with the 1974 Edition through Summer ' 1975, Addenda of ASME Section XI, during this j interval. I i I L l

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