Text

Inservice Insp Program for Welds & Supports,Revision 0. Fourteen Oversized Drawings Available in Central Files
	ML20136B967
Person / Time
Site:	FitzPatrick
Issue date:	05/31/1979
From:	Beakes J, Partridge M, Sorrentino A; GENERAL PHYSICS CORP., POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	;
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ML19208A313	List: ML19208A312; ML20136B967;
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	PROC-790531, NUDOCS 7909130361
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.

j JAMES A. FITZPATRICK '

NUCLEAR POWER PLANT i

INSERVICE INSPECTION PROGRAM FOR WELDS AND SUPPORTS Revision 0 May 1979 i

Prepared By: 47 Date: May 25, 1979 M. JgPartridgegeneral Physics Corporation Approved By: w Date: May 29, 1979 H. Beakes, General Physics Corporation i PASNY Approval:

Date: f, /. / k 7 9 .

/ jA.V[.Sorrentino /U

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f Power Authority of the State of New York

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INSERVICE INSPECTION PROGRAM FOR WELDS AND SUPPORTS l-j_ FOR THE JAME.S A. FITZPATRICK NUCLEAR POWER PLANT .

L TABLE OF CONTENTS Section Title Page i

TABLE OF CONTENTS . . . . . . . . . . . i L'

1.0 INTRODUCTION

. . . . . . . . . . . . . 1 1.l' _ Program Update Description . . . . . . 2 1.2 Technical Approach . . . . . . . . . . 3

, 1.3 Key Technical Points . . . . . . . . . 4 I~ l ~. 3.1 Code Exemptions , . . . . . . . . . 4 i 1.3.2 Alternate Examinations for Exempt Components . . . . . . . . . . . . . 4 1.3.3 Relief Requests . . .- . . . . . . .

4

.l.3.4' "In Lieu Of" Examinations . . . . .

4

.. 1.3.5 Containment Penetrations . . . . . .

5 1.3.6 Pressure Tests . . . . . . . . . . .

5 1

i 1.3.7 Class 3 Systems and Components . . . 8 1.3.8 Repair Provisions , , , , , , , , , 9 i

Appendices t

] A-1 EXAMINATION

SUMMARY

FOR ASME CLASS 1 SYSTEMS AND COMPONENTS . . . . . . .

l' A-2 EXAMINATION

SUMMARY

FOR ASME CLASS 2

, SYSTEMS AND COMPONENTS . . . . . . .

B PIPING WELD AND SUPPORT-EXAMINATION PROGRAM- . . . . . . . . .. . . . .

C INSERVICE DIAGRAMS (One set to be supplied with NRC Submittal) . . . .

i i

INSERVICE INSPECTION PROGRAM FOR WELDS AND SUPPORTS l

FOR THE l

JAMES A. FITZPATRICK NUCLEAR POWER PLANT 1.0 Introduction f

l In the past, there have been divergent opinions on the re-l quirements for Inservice Inspection of nuclear power plant com-ponents. As specified in 10 CFR 50, the current Code in effect

, is the 1974 Edition of the ASME Boiler and Pressure Vessel Code

Section XI through the Summer 1975 Addenda (hereafter designated as " Code"). There is a general consensus that the edition of

the Code accepted by the Nuclear Regulatory Commission (NRC) provides a reasonable level of inspection that will help to ensure the pressure boundary integrity of essential systems of a boiling water reactor plant such as James A. FitzPatrick. However, there are areas needing further refinement.

For example, the Code permits systems that perform an emergency core cooling function to be totally exempted from examination provided the control of chemistry of the contained

, fluid is verified by periodic sampling and t'est; whereas it re-quires volumetric examination of many fillet welds that are not inspectable by that examination method. Further, since the adoption of the Summer 1975 Addenda, the ASME Section XI has issued new requirements in its later editions and addenda, and the NRC has released several guideline letters relating to in-service inspection. The new Code requirements and the guidelines I

promulgated by the NRC will affect future updated inservice inspection programs for the James A. FitzPatrick Plant, and have been considered in developing the Program described herein. The Program conforms to the purpose and intent of performing the Code required inservice inspection and will provide assurance of the integrity of the pressure boundaries of essential systems.

l t

I This report contains the complete Inservice Inspection weld examination and component inspection program for'the second 40-

[ . month operating period. The technical bases for any deviations i

from the Code are also identified. In accordance with the current requirements of 10 CFR 50, this Inservice Inspection program will be applicable for a 40-month period ending March 28, 1982.1

, Subsequent review and update will be in accordance with the

10 CFR 50 requirements in effect at that time, f 1.1 Program Update Description n

, The specific areas to be examined and the extent of examina-g_ tions to be performed during the first 10-year operating interval are summarized in Appendices to this report as follows:

i i

Appendix A Examination Summary for ASME Class 1 Systems and Components

Appendix A Examination Summary for ASME Class 2 Systems and Components

?-

Appendix B - Piping Weld and Support Examination l Program

. To facilitate review, Appendices A-1 and A-2 are presented

! in a format consistent with that of Tables IWB-2600 and IWC-2600 respectively, of the Code. These summaries provide the Item Number, Examination Category, Areas to be Examined, Examination Method (s) and Extent of Examination (s) to be Performed, as identified in the Code. Information on accessibility and other related considerations have been included along with references a to Appendix B in the cases where Examination Method (s) and Extent I of Examination (s) to be Performed are presented in the Piping

, Weld and Support Inspection Program.

I 1

1 1 A proposed 10 CFR 50 rule change recently published for comment in the Federal Register would leave the Program Update described in this report in f effect for the remainder of the first full 120-month inspection interval i

which began with the commercial operation date of July 28, 1975. In the event that this proposed rule change is incorporated into 10 CFR 50, this Program Upddte will be effective until July 28, 1985.

2 ,

! l 1

' Appendix B. includes: descriptive information and definitions l-of (1) Code. Exemptions, (2) Relief Requests, and (3) Weld Summary

' -Sheet Terms; a-Weld Summary Sheet Index (listing of systems in-cluded in the Program) ; and Weld Summary Sheets for each system..

Appendix C. represents the color-coded Inservice Diagrams I (ISD's) which define the ASME Class 1, Class 2, and Class 3 L

boundaries for those systems listed in Appendix B.

1 The inspection program for ASME Class 3 systems and com-

, ponents is covered in-Section 1.3.7 of this report.

a j 1.2 Technical Approach j.

In general,.the inservice inspection requirements in the a' 1974 Edition through the Summer 1975 Addenda which are applicable to ASME Class 1 components and systems are considered to be l sufficient and workable to provide a reasonable and prudent level of inspection that will help to ensure the pressure boundary integrity of essential systems of a boiling water reactor plant.

However, the Code requirements applicable to ASME Class 2 com-

. ponents and systems are considered in many cases to need enhance-ment. The ASME has recognized various aspects that need improve-ment in the 1974 Edition through the Summer 1975 Addenda and has i subsequently made many improvements in its later Editions and j Addenda. These later Editions and Addenda (e.g., 1977 Edition, I. Summer 1978 Addenda) are not currently recognized by 10 CFR 50, and therefore, are not used directly in the Inservice Inspection

{ Program Update.

0-j The Inservice Inspection Program Update was prepared to the degree practicable in accordance with the Code requirements.

f,- Where the Code requirements were determined to be either incom-I plete or impracticable, specific requests for relief from' Code

, requiremepts are identified. Each request for' relief has been evaluated and an alternative examination is specified. In

' 3 i

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I l-- almost every case the alternative examination results in a higher level of confidence in system integrity than the j original Code requirement (the exceptions to this are welds that are physically inaccessible for any type of examination.

( .

~l 1.3- Key Technical' Points 1.3.1 Code Exemptions E Exemptions identified in IWB-1220 and IWC-1220 of the Code are . used in this Program with the exception of .lWC-1220 (c) ,

- wh'ich. exempts emergency core cooling systems II the' chemistry of their contained finid is controlled.

I 1.3'.2 Alternate Examinations for Exempt Components

~~' In accordance with Category B-PLof Table IWB-2500 for Class 11 and IWC-2510 for Class 2, components exempt from volu-i . metric and surface examination will be visually examined during 7

. pressure.t'est in accordance with Code requirements. In l' Appendix B, such examinations are listed under "In Lieu of Examination" where appropriate.

(

l.3.3 Relief Requests

t.

Where Code requirements are determined to be incomplete

.j' or impractical, requests for relief are documented and techni-

-t cally justified in the notes and remarks in Appendices A-1 and A-2 and in Table B-2 of' Appendix B.

1.3.4 "In Lieu of" Examinations Where relief is requested from examination of component, an "in lieu.of" examination is specified.

~

In most cases, the "in lieu of" examination results in a higher level of confi-dence in tystem integrity than the original Code requirements.

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1.3.5 Primary Containment Penetration Welds l Appendix B specifies a surface examination, if the weld j

is accessible, for all primary containment boundary to piping l welds in all high energy steam or water containing piping s

greater than three inches nominal pipe size. This exceeds the Code requirement in some cases, and is therefore an "aug-mented" examination, but is considered necessary because of the importance of the integrity of the primary containment boundary.

. The containment penetration is considered to extend to the first isolation valve outside containment and the first seismic restraint past that valve.

. In addition, system piping greater than 4 inches nominal 1

pipe size that is directly open to the primary containment atmosphere, i.e., Containment Air Dilution (CAD) and Drywell to Suppression Pool Vacuum Breakers, will have " augmented" surface examination out to the outer containment isolation valve and the first seismic restraint past the valve. (Note that since these systems are air systems, they are not within the scope of ASME B&PV Code,Section XI.) The " Areas Subject to. Examination" and the " Extent of Examination" of Examination Category C-G shall apply to all above augmented examinations.

The typical containment penetration is constructed such

, that one circumferential butt weld inside the penetration is completely inaccessible for either surface or volumetric in-I spection. This weld is shown in Figure 1-1. Each of these

, inaccessible welds is identified in Appendix B and an "in a

i lieu of" examination is specified.

I

- 1.3.6: Pressure Tests iI In the Weld Summary Sheets, three different types of pressure tests are used. Descriptions of the three types are given in l Table 1-h. The system " Pressure" test identified as the "In n

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1) g-Lieu of Test" for' Relief Request R2 (Class 2 systems that

. operate above moderate energy less than one percent of plant I

operating time) is intended to increase the overall confidence

-in.the pressure boundary integrity of those systems or portions.

of' systems using Relief Request R2. This test method will verify the integrity of 100 percent of the welds every 3 1/3 l

. years rather than a small portion (can typically be as small as 2 percent of the welds during the same 3 1/3 year period)

LI- of the welds as required by the Code.

Table 1.1 Pressure Test Descriptions Weld Summary Test Name Sheet Symbol Test Description Hydrostatic HYD The Code required hydrostatic pressure test l performed each interval as specified in Section XI Paragraphs IWA-5000, IWB-5000, IWC-5000, and IWD-5000, as applicable. The

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hydrostatic test pressure shall be based on the Code requirements; however, overpressuri-zation of the most' limiting component in a 4

system or portion of a system is not permitted.

For example, piping attached to the reactor

[

vessel will be tested with the reactor ves-sel rather than to their own test pressure.

Pressure PRS A pressure test performed on a system or portion of a system as the "In Lieu of Exam" j' a for Relief Request R2. The test shall.be performed every 3 1/3 years. For components

- that are not required to function during reactor. operation, the system test. pressure

.] .

shall not be less than 100 percent of the pressure developed during the conduct of a periodic system inservice test [IWC-5220 (c) ] .

-I i:

Flow- FLW A test performed to portions of systems that' cannot be hydros:atic pressure tested, such

]!- as lines connected to open tanks. The test shall be performed during system operation every 3 1/3 year'. The test pressure shall

.) be that pressa c attained during normal

- J, system operation.

l 9

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1.3.7 Class 3 Systems and Components Class 3 systems at the James A. FitzPatrick Plant fall into two categories: (1) the Reactor Core Isolation Cooling (RCIC) ,

system, and (2) cooling water systems. The RCIC system has been f

designed to be able to be pressure tested and therefore, will be j tested in full accordance with the Code requirements.

i The cooling water systems were designed and constructed prior to the issuance of the first Code Edition that addressed Class 3 systems and components (the 1974 Edition). Since the systems were designed and constructed without the current inspection require-ments in view, isolation valves that would permit hydrostatic testing to current requirements were not installed.

An alternative inspection program described below is there-

[ fore implemented to insure the integrity of the pressure boundary of these cooling water systems. This program incorporates features of the 1977 Edition of the Code through the Summer 1978 Addenda for visual inspection of piping systems and supports. To provide

additional assurance of system integrity, these inspections will be conducted during system functional tests once per cycle (which

, j exceeds Code requirements). The inspection program for Class 3 cooling water systems is as follows:

Cooling Water System Components Examination

Subject to Examination Method Reference 1 Piping and Components (Not Buried) VT-2 IWA-2212 I

g Piping and Components (Buried) Flow Verification IWA-5244(c)

Piping Supports VT-3 IWA-2213 t

1 1

I All references are from the 1977 Edition of ASME Section XI through the l Summer 1978 Addenda.

(

I i

\

B 1.3.8 Repair Provisions Because of the vintage of the James A. FitzPatrick Nuclear 1

Power Plant, not all systems and components were originally de-signed and fabricated to the ASME Boiler and Pressure Vessel Code.

f' Systems and components re-classified herein in accordance with the inservice inspection requirements of 10 CFR 50, 50. 2 (v) , 50.55a(g)

and Regulatory Guide 1.26 as ASME Class 1, 2 and 3 shall be examined

, in accordance with this orogram. Consequently, relief is requested from the requirements of Articles IWA-4000 of ASME Section XI

' Repair Procedures and the subsequent Articles IWB-4000, IWC-4000, and IWD-4000.

In lieu of these requirements in order to assure quality and integrity of the repaired and/or replacement component, the following shall be accomplished:

?

1.3.8.1 Codes and Standards Repairs on the components of the systems classified in the inservice inspection program as ASME Class 1,2, and 3, shall be made in accordance with the Code or Standard used for the original fabrication (later approved Editions and Addenda may be used).

1.3.8.2 Quality Assurance

+

All work pertaining to repairs and replacements shall be performed in accordance with the requirements of the exist-ing James A. FitzPatrick Quality Assurance Program.

[ 1.3.8.3 Pressure Test i After repairs by welding on the pressare retaining boundary I

of components (except repairs on cladding), a pressure test

. shall be performed in accordance with the provisions of f

i IWA-5000, 1974 Edition, Summer 1975 Addenda.

( !

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.,. '1.3.8.4 Re-examination i

Re-examinations shall include the method that detected the flaw requiring repair and shall be used to establish a new preservice record.

}

l.3.8.5 Procedure Review l

' All repair procedures shall'be available for review by the enforcement authorities having jurisdiction at the plant site.

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APPENDIX A-1 EXAMINATION

SUMMARY

ASME CLASS 1 SYSTEMS AND COMPONENTS -

i

. ITEM EXAMINA110N COMPONF.NTS AND PARTS EXAMINATION EXTENT OF EXAMINATION

, NO.3 CATEGORYI TO BE EXAMINED METilODS3 PERCENT IN 10 YEARSI ACCESSIBILITY NOTES L

meactor Usesel

, 31.1 FA Reactor pressure vessel longi- Voltanetric Iong. S-10 The use of doors in the sacrifi- 1

tudinal and circumferential welds Cire. S-5 cial shield and thermal insula- +

in core region After exposure to 10 3' NVT tion provide O.D. access to $4 of of fast neutrons, both . the circumferential and 104 of the long. and cire. seams longitudinal welds.

require 50% esamination w 31.2 s-s closure hea2 circumferential and Volumetric Cire. S-5 -

meridional welds Merid. S-10

, meactor pressure vessel longi- Voltametric Iong. 5-10 2 y tudinal and circumferential welds Cire. S-5 4e above sacrificial shield .

>'. [

Meactor pressure vessel welds volumetric Long. S-10 0.D. access to the welds within 3 within sacrificial shield and Cire. S-5 the sacrificial shield will be above jet pump support plate provided by the opening of doors '

in the shield wall and plugs in the insulation.

Sottom head circumferential and Voltanetric Cire. S-5 Access to the bottom head welds -

meridional welds - head to Merid. S-10 outside the support skirt are

~

vessel weld and meridional welds- severely limited due to insulation, r outside the vessel support skirt structural interferences, and instrumentation leads.

Bottom head circtumferential and Volumetric Cire. S-5 0.D. access inside of the support 4 meridional welds inside support Merid. 5-10. skirt is provided by access ports skirt in the bottom head insulation and 4-18 in, access ports through the support skirt.

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w APPENDIX A-1.

EXAMINATION

SUMMARY

ASME CLASS 1. SYSTEMS AND COMPONENTS ITEM EXAMINA110N NO.1 COMPONENE AND PARE EXAMINATION EXTENT OP EXAMINATION '

CATEGORY 1 10 ItE EXAMINED METilODS1 PERCENT IN 10 YEARS 1 ACCESSIBILITY NOTES B1.3 D-C Vessel-to-flange circumferential

"'Id Volanetric 100 The vessel-to-flange weld is 5 o

accessible from the flange mating surface, Head-to-flange circumferential Volumetric 100 weld Head-to-flange weld is accessible =

from corresponding surfaces when the head is removed for refueling.

Bl.4 8-D Nozzle-to-vessel attachment welds: Volumetric 100 The O.D. by opening doors from -

Steam nozzle-to-vessel Feedwater nozzle-to-vessel sacrificial shield and thermal Core spray nozzle-to-vessel insulation.

Recir. inlet nozzle-to-vessel Recir. outlet nozzle-to-vessel T Control rod drive water return y nozzle-to-vessel os Jet pump instrument nozzle-to-vessel Nozzle-to-closure head attachment volusotric 100 welds .

Inner radius sections of the Voltanetric 100 vessel nozzles listed above Access to inner radius sections of 6 the various vessel nozzles is sub-ject to the same conditions as

stated above for nozzle-to-vessel welds.

Inner radius sections of the Voltanetric 100 closure head nozzle Closure head nozzle inner radii -

become accessible during refueling.

6

)

' Ta ble IWR-2500, ASME Rniler and Pregnure Vessel f%de, meetim XT, 1974 FAttim thrrumb the Miwr 1979 WWa

. . . ~ . . . . ,. . . .. .. ._ , - _. - - - ~.

APPENDIX A-1 EXAf.*lNATION

SUMMARY

AST.1E CLASS 1 SYSTEMS AND CO".PCNENTS IT D1 EXA%11NA'llON NO.3 COillt)NE.NTS AND PARTS CATEGORY 3 10 RE EN AMINED ENAMINATION EATENT OF EN.uttNATION M ETipODS1 PERCENT IN 10 YEARSI ACCESSIBILITY NOTES Bl.5 B-E Welds in vessel at control rod Visual 25 drive penetrations and in-core Access is provided by observation -

monitor housing ports in the bottom head insula-(Stub tube-to-housing and vessel) tion.

81.6 B-F Primary nozzles to safe-end welds: Visual, 100 Reactor pressure vessel safe-end Recirculation inlet surface, Recirculation outlet and welds are made accessible by re-Jet pump instrumentation moving thermal insulation and voltanetric Core spray sacrificial shield plugs.

CRD Return p 31.7/

4 e

Bl.8 B-G-1 Closure studs and nuts Volmetric W and 100 surface Closure head stud and nuts are 7 accessible during refueling Bl.9 B-G-1 Licaments between threaded stud Volenetric 100 holes Ligaments are exposed by removal -

of the vessel head during refueling Bl.10 B-G-1 Closure washers and bushings Visual 100 Washers and bushings are accessi- 8 ble upon removal of the studs.

81.11 B-G-2 Reactor vessel Visual 100 Accessibility is provided upon 9 removal of insulation.

B1.12 B-H Skirt-to-vessel weld volumetric 10 Access is possible frcan the vessel -

O.D. by openings in the sacrifi-cial shield wall and removable insulation panels.

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- APPENOlX A-1.

EXAMINATION

SUMMARY

ASME CLASS 1 SYSTEMS AND COMPONENTS ITEM EXAMINA110N NO.1

' COMPONEN1S AND PARTS EXAMINATION EXTENT OF EXAMINATION CATEGORY 2 TO BE EXAMINF.D ' Mt,1 HODS 3

~ ..

PERCENT IN 10 YEARS 3 ACCESSIBitJTY NOTES B1.13 3-I-1' Not applicable. n e closure -

. head is not clad. -

31.14 B-I-1 Vessel cladding - 6 patches, each Visual <

100 10

36 sq in. in area Bl.15 B-N-1 The interior surfaces of the. Visual reactor vessel and the space At the first refueling outage he lower plenssa is accessible by 11 and then at 3-year intervals. resoval of four fuel bundles, below the reactor core above the bottom head . control rod, fuel support piece and guide tube.

81.16 B-M-2 The internal supports and Y Visual 100% of visually accessible No additional provision is in- -

attachments welded to the vessel welds and surfaces of cost- cluded in the design to provide 7 wall and the internal cousponents ponents once at or near the

access to those internals that -

end of the inspection are not normally accessible from interval, the vessel flange during refuel-ing.

Bl.17 B-N-3 Not Applicable.

(PWR only) -

51.18 B-0 The CRD housing weld metal and Volumetric 100% of the welds in 10% of 12 base metal for one wall thick- or the peripheral CRD housings, ness beyond the edge of the weld Surface performed at or near the end of the inspection interval.

B1.19 B-P Welds and supports not otherwise Visual 100 examined , -

Table KuB-2500, AsME Boiler and Pressure vessel Code, section XI,1974 Edition through the Susmer 1975 Adde nda

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AI?EN0sX A-1 EXA*.91N AT:OM

SUMMARY

ASME Ct. ASS 1 SYSTWS AND COMIMENTS ITt31 EX.O!!YAMON CO\iPONf.NTS AND PARTS NO.3 EXAMINATIO.N EXTENT OF EXAMINATION l CATEGORYI TO BE EXAMINED METilODS' PERCENT IN 10 YEARS 1 ACCESS 1Bil,lTY NOTES .

- . =% _

Pre ssuriser B2.1-87.11 All Not applicable (PWR only) -

Heat Eschangers and Steam Generstors 83.1+33.10 All -Not applicable (PWR only) -

Piping Pressure Boundary

>s Y

w B4.1 B-F Piping pressure boundary safe- Visual, 100 Safe ends in branch welds and 13 ends in branch piping welds surface dissimilar metal welds are made s accessible by removing piping volumetric thermal insulation.

Piping pressure boundary welds

. between dissimilar metals (See Appendix B, Piping Weld and Support Examination Suissary for Details) 84,2/4.3/ B-G-1 Piping pressure boundary pressure -

4.4 retaining bolting. Not appli-cable. There is no bolting 2 in.

or larger in the piping.

g . .

Table ilm-2500. Amet poller and Pressure vessel Code,Section XI,1974 Edition through the Sumser.1975 Addenda

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APPENDIX A-1 EXAMINATION

SUMMARY

ASME CLASS 1 SYSTEMS AND COMPONENTS ITEM EXAMINATION COMPONENTS AND PARTS EXAMINATION EXTENT OF EX AMINATION NO.8 CATEGORY'l TO BE EXAMINED METilODS1 PERCENT IN 10 YEARS 1 ACCESSIBILITY NOTES B4.$/B4.6 B-J Longitudinal, circunferential, Visual, 25 Accessibility is provided by 13 B4.7/B4.8 branch, and socket welds in the Surface removable insulation to expose following systems: and/or , the circumferential welds and, Residual Heat Removal Volumetric wherever applicable,15 in. of Main steam the longitudinal welds.

Feedwater Core spray R W Cleanup R W Recirculation.

Control rod drive High Pressure Coolant Injection System Reactor Core Isolation Cooling System (See Appendix B, Piping Weld and Support Examination S a mary for details)

B-K-1 B4.9 Piping pressure boundary in- Surface 25 Access will be provided by re- 13 te<Jrally welded external support or movable insulation to expose the attachments (See Appendix B, Volumetric attachment welds.

Piping Weld and Support Exami-nation Staunary for details)

B4.10 B-K-2 Piping pressure boundary hangers, Visual 100 Access of supports is available 13 snubbers, absorbers, and other for visual examination without supports whose structural in- providing special removable tegrity is relied upon to sections withstand design loads and seismic induced displacements (See Appendix 8, Piping and '

Support Examination Supunary for details) 4 84.11 B-P belc.s and supports not otherwise visual 100 -

examined B4.32 B-G-2 Piping pressure bomJary pres- Visual 100 Accessibility is provided'upon 14 sure-retainin.; bolting removal of insulation.

I Table IWB-2500 ASME Boiler and Pressure Vessel Code,Section XI,1974 Edition through the Sumer 1975 Addenda

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. APPENDIX A-1 EXAMINATION

SUMMARY

ASME CLASS 1 SYSTEMS AND COMPONENTS ITEM EXAMINA110N COMPONENTS AND PARTS EXAMINATION EXTENT OF EXAMINATION NO3 CATEGORY 1 TO BE EXAMINED METilODS1 PERCENT IN 10 YEARSI : ACCESSIBILITY NOTES -

Pup Pressu re Boundary B5.1/35.2/

B5.3 3-G-1 Pap pressure boundary pressure- Voluumetric 100 Reactor recirculation pusp casing 15 retaining bolting and bolting is accessible during an Surface outage.

35.4 s-E-1 Pump integrally-welded support Surface or 25 Access will be provided by re- <3 attachments (See Appendix B, Volumetric movable insulation to expose the Piping weld and Support Examina- attachment welds.

tion Summary for details)

> 35.5 3-K-2 Pe p hangers, snubbers, absorbers, Visual 100 Access of supports is available 13

$ type supports whose structural for visual examination without

$ integrity is relied upon to with- providing special removable stand design loads and seismic sections induced displacements (See

, Appendix B, Piping weld and Support Examination Sussmary for details) 85.6 3-L-1 Not applicable. 1here are no psaaps with pressure retaining welds in the pump casing -

35.7 3-Ir2 Internal pressure boundary sur- Visual 50 Internal surfaces are accessible 16 faces of recirculation pumps for the required visual examina-tion upon disassembly of the pumps. Removable insulation will be provided for pump disassembly.

a5.8 B-P welds and supports not otherwise Visual 100 examined Table Imp-2500, ASME Boiler and Pressure vessel Code,'Section XI,' 1974 Edition through the Staurr 1975 Addenda m

,. . _ . . , - -- __ _- . . _ . . . .. -_. _ . - ~ ,_. -

APPENOfX A-1 EXAMINATION

SUMMARY

ASME CLASS 1 SYSTEMS AND COMPONENTS ITEM - EXAMINATION COMPONENTS A.ND PARTS FXAMINATION EXTENT OF EXAMINATION NO.I CATEGORY 3 70 RE EXAMWED METilODS3 PERCENT IN 10 YEARS 1 ACCESSIBILITY NOTES

B5.9 . B-G-2 Pump pressure boundary boltinn visual 100 The recirculation pump mechanical 17 seal bolting is accessible during an outage.

Valve Pressure Bound ya 86.1/B6.2/ B-G-1 not applicable, n ere is no -

B6.3 pressure retaining bolting 2 in.

or larger on valves 86.4 B-K-1 Integrally welded support attach- Surface or 25 13 ments (See Appendix B, Piping Volumetric arm! Support Examination Stanary y for details)

Y 86.5 B-K-2 valve hangers, snubbers, absorb- Visual 100 Access of supports is available 13 ers, type supports whose for visual examination without structural integrity is relied providing special removable upon to withstand design loa!s sections.

and seismic induced displace-ments (See Appendix B. Piping

, and Support Examination sumary for details) 86.6 B-M-1 Not applicable. There are no -

valves with pressure retaining welds in the valve bodies B6.7 B-M-2 Internal pressure boundary sur- Visual one valve of each of these Internal surfaces are accessible le faces of valves exceeding 4 in. groups of valves of the for the required visual exam 8 a-nominal pipe size in main steam, same construction, design, tion upon disassembly of the feedwater, core spray, high manufacturing method, manu- valves. Removable insulation pressure coolant injection, facturer, and performing will be provided.

residual heat remov.11 and similar functions in the recirculation piping systems system I

Table IWB-2500, ASME Boiler and Pressure vessel Code, fection XI, 1974 Edition through the Su..wer 13 5 Addenda

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APPENDIX A-1.

NOTES L NOTE 1: Relief from Code Requirements is requested.

g With the core in place, high radiation ~ levels in the vicinity of the subject welds make it impractical to attempt examination. Therefore, these welds will be examined in accordance with the Code only .,

7Y if and when the entire core is removed for any reason. Additionally, due to limited external

, accessibilitytothecircumferential-andlongituggnalweldsbecauseofstructuralinterferences,the,,

50% examination requirement after exposure to 10 NVT of fast neutrons cannot be performed. Vessel ~

~

internal examination is impractical because the necessary scanning equipment is not yet available,

- positioning is extremely difficult, and accurate interpretation of test results is impossible due '

f to the cladding.

various inspections and tests are performed and operational constraints are strictly observed '

to assure the integrity of this vessel. These include:

Item Reference (a) Visual examination during hydrostatic test Code required hydrostatic test y each inspection interval Y (b) Minimum pressurization temperature restric- Technical Specification Paragraph 3.6.B g

tions and associated surveillance program (c) Thermal transient restrictions Technical Specification Paragraph 3.6. A (d) Reactor coolant system leakage monitoring Technical Specification Paragraph 3.6.D NOTE 2: Examination from the vessel internal surface is theoretically possible, but is not presently practical as indicated in Note 1, above.

NOTE 3: Relief from Code requirements is requested.

With the core in place, high radiation levels in the vicinity of the subject welds make it impractical to attempt examination. Therefore, these welds will be examined in accordance with the code only if and when the entire core is removed for any reason. Examination from the vessel internal surface is theoretically possible, but is not presently practical as indicated in Note 1, above.

._ , _ , _ , -.m s_ _ . .

. . . ., ._ ., .- .~ a : --. . - . . --- ~. - - . -----~ --

NOTE 4: . Relief from Code requirements is requested. '

f' Only visual examination during the 10-year interval hydrostatic test will be' performed because.

the large number of penetrations in this area makes volumetric examination impractical.

NOTE 5: During refueling ultrasonic examination can be performed from the flange-mating surface..

NObf 6: Relief from Code requirements is requested. .,

. No acceptable procedure exists for examination of the inner radii'from the nozzle O.D. due to ,

technical problems with interpretation of results. Automated equipment is not available to 2

perform examinations from the nozzle I.D.

NOTE 7: Closure head bolting will be examined under tension,-when bolting.is removed or when the bolting connection is disassembled. When bolting is examined under tension, no surface exam is required.

l Surface examination will only be performed in conjunction with volumetric exam when bolting is' removed.

NOTE 8: Visual examination will be performed only.when studs are disassembled.

T NOTE 9: Visual examination will be performed only when the equipment is disassembled for maintenance'or 7 overhaul.

U NOTE 10: Relief-from Code requirements is requested.

The requirement for this examination has been dropped from later addenda of the. Code, such as the Summer 1978 Addenda. Visual examination of the internal surfaces of the reactor vessel is covered in Examination Category B-N-1.

NOTE 11: Visual examination of the-lower plenum was performed at the first refueling outage. During subsequent refueling outages if this area is made accessible during normal refueling operations, the lower' plenum area shall be examined. These examinations shall not be made more frequently than at approximately 3-year intervals.

NOTE 12: Relief from Code requirements is requested for the examination of the stub tube to CRD housing welds,

,1 i

The stub tube to CRD housing peripheral welds are inaccessible due to structural interferences and cannot be surface or volumetrically examined. The CRD housing to flange welds are accessible and will be examined in accordance with Code requirements.

1 6

=

4

_ __ _ _ _ . ._ , ._ . . . _ . _ _ _.- ~, . . - - _

- -~ --~

NOTE 13: Specific relief requests are identified, as applicable, in Appendix B, Piping Weld and Support Summary.

NOTE 14: Relief from Code requirements'is requested.

Visual examination of relief valve and RHR system flange bolting will be made during disassembly for maintenance. Visual examination of the recirculation system decontamination flange bolting shall be_made whenever the flange is removed. Examinations need not be conducted more frequently.

than every 10 years.

NME 15: Reactor recirculation pump casing bolting will be examined under tension, or when removed or disassembled. When bolting is examined under tension, no surface exan. is required. Surface examination will only be performed in conjunction with volumetric exam een bolting is removed.

NME 16: Relief from Code requirements is requested. 1 Visual inspection of the ' internal surfaces will be made only when recirculation pumps are disassembled for other reasons.

p E NME 17: Relief from Code requirements'is requested.

E Visual examination of recirculation pump mechanical . seal bolting shall be done when disassembled for maintenance. Examinations need not be conducted more frequently than every.10 years.

NME 18: Relief from Code requirements is requested.

Visual examination of the internal surfaces of valves will be made when valves are disassembled for other reasons. Examinations need not be conducted more frequently than every 10 years.

NOTE 19: Relief from Code requirements is requested.

Visual examination of the valve bolting will be made when the valves are disassembled for other reasons. Examinations need not be conducted more frequently than every 10 years.

__ s - > +

-m. 4

, _, _. , n ., . ' . , , < - - n.-- . < ~ ~ - . - " - _ _

q_ --- .

APPENOlX A-2 EXAYINATION SU'. WARY .

ASME CLASS 2 SYSTEMS AND COMPONENTS ITEM EXAMINATION COMPONENTS AND PARTS EX.' MINATION EXTENT OF EXAMINATION NO.3 CATECORY3 TO BE EXAMINED METIIODS3 PERCENT IN 10 YEARS 3' ACCESSIBILITY NOTES Pressure Vessels C1.1 C-A Ciretsaferential butt welds on the Volumetric RHR Heat Exchangers which are Stof one equivalent heat Accessible with removal of -

exchanger, distributed among persanent insulation gross structural discontinuities three areas on each of the as defined in ASME Section Ill, two heat exchanaers Para. NB-3213.2 C1.2 C-B Nozzle-to-vessel welds on the Voltunetric PRR Heat Exchangers 25% of one equivalent Accessible with removal of -

heat exchanger perlmanent insulation C1.3 C-C Integrally welded supports on the Surface 4

RHR Heat Exchangers

' 25% of one equivalent Accessible with removal of -

heat exchanger permanent insulation

p e

DJ

$ Cl.4 C-D Not Applicable.

There is no pressure retaining bolting on the RHR Heat Exchangers i

Pining C2.1, C2.2, C- F, C-G Circumferential, longitmlinal, and Volumetric C-F, 25% of one equivalent Generally accessible with removal 1 and C2.3 branch piping system welds. (See stream of permanent insulation Apperdix B, Piping Wold and C-G, 12.5% of one equivalent Support Examination Summary for stream details.)

C2.4 C-D Pressure retaining bolting Visual and Visual,100% of one equiva- Generally accessible with removal 2 either lent stream of permanent insulation Surface or Surface or volumetric, 25%

volumetric of the bolted joints with 10% of each joint bolting examined 4

I Table JWP-2500, ASMS Boiler an! T ressure vess**1 Code, f.ection XI, 1974 F.dition through the Sumener 1975 Addenda

__ _-r -

. ;-- - - - - * ~' ~~

_. . . - - ~

APPENDIX A-2 EXAVINATION SU!.iMARY ASME CLASS 2 SYSTEMS AND COMPONENTS ITEM EXA\!!NA110N NO.3 COMPONENTS AND PARTS EXAMINATION EXTENT OF EXAMINATION CtTEGORY3 'IO BE EXAMINED MEntODS1 PERCENT IN 10 YEARS 1 ACCESS!8tLITY NOTES C .5 C-E-1 Piping pressure boundary integrally Surface loot of one equivalent Generally accessible with removal welded external support attach- stream of permanent insulation I

monts (See Appendix B, Piping Weld and Support Examination Simonary for details. )

C2.6 C-E-2 Piping pressure boundary hangers, Visual 100% of one equivalent Access is p;ovided snubbers, absorbers, and other stream 1 supports whose structural integrity is relied upon to withstand design loads and seismic induced dis-placements (See Appendix B, piping Weld and Support Examination Sununary for details.)

>e y Puers co C3.1 C-F, C-G Not Applicable.

There are no pressure retaining .

welds in pismps C3.2 C-D Pressure retaining bolting in pumps

visual and Visual, 2004 of one equiva- Generally accessible with renoval 2 either stream of permanent insulation Surface or Surface or voltanetric, 25%

Voltanetric of the bolted joints with 10% of each joint bolting examined C3.3 C-E-1 Not Applicable.

There are no integrally welded -

supports on pumps C3.4 C-E-2 pump support components Visual 100% of one equivalent necess is provided -

stream 1

Table IWB-2500, AsME Boiler and Pressure vessel code,Section XI, 1974 Edition through the Summer 1975 Addenda

_ _ . _ . a .. * .u- ~ -

-~ "" *~ ~~ -

APPENDIX A-2 EXAMINATION

SUMMARY

ASME CLASS 2 SYSTEMS AND COMPONENTS ITEM EXAMINAT10N NO.3 COMPONENTS AND PARTS EXAMINATIO.N EXTENT OF EXAMINATION CATECORY3 TO BE EXAMINED METilODS1 PERCENT IN 10 YEARSI ACCESSIBILITY NOTES-

.. Va ,ves C4.1 C-r, C-G Itot Applicable.

There are no pressure retaining -

welds in valves C4.2 C-D Pressure retaining bolting in Visual and Visual,100% of one equiva- Generally accessible with removal valves either 2 lent stream of permanent insulation Surface or Surface or Volumetric, 254-Voltanetric of the bolted joints with 10% of each joint bolting examined

n, C4.3 C-E-1 Integrally welded valve supports i

4 surface 100% of one equivalent Accessible with removal of (See Appendix B. Piping Weld and stream permanent insulation 4 Support Examination Stemmary for 1 details.)

C4.4 C-E-2 i l

Valve support components (See Visual 100% of one equivalent Appendix 3 Piping Weld and Access is provided 1 l stream Support Examination Sussnary for details.)

i i

I Table IWB-2500, ASME Boiler and Pressure Vessel Code,'Section XI, 1974 Edition through the Summer 1975 a Addend

--- _ ~.

.i,- . . _ _ _.a. _ . . _ , _ , .

APPENDIX A-2' ,

NOTES

1. Specific relief requests are identified, as applicable, in Appendix B, Piping Weld and Support Examination Summary.

2. Relief =from Code requirements is requested.

The Code requirement is to either surface-or volumetrically examine bolting exceeding 1 inch in diameter. This requirement is inconsistent and more restrictive than the Class 1 requirement (examine bolting 2 inches and greater) and later Section XI Addenda, such as the Summer 1978 Addenda (examine bolting exceeding.2 inches in diameter).

The in-lieu-of examination for Class 2 bolting will be to surface or volumetrically y examind oolting exceeding 2 inches in diameter.

i

_ v1

l: APPENDIX B I-4.

PIPING WELD AND SUPPORT EXAMINATION PROGRAM I

1- TABLE OF CONTENTS Table Number ~ Subject Page TABLE OF CONTENTS . . . . . . . . . . . B-i B-1 Code Exemptions . . . . . . . . . . . . B-1 l B-2 Relief' Requests . . . . . . . . . . . . B-2 B-3 Weld Summary Sheet Terms . . . . . . . B-5 i B-4 Weld Summary Sheet Index and Cross Reference to Inservice Diagrams . . B-8

-i. B-5 Weld Summary Sheets and Notes . . . . . B-9 i'

s $-

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1 c.

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i 1

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b Table B-1

/

l Code Exemptions Code Exemption Identifier El Class 2 component connections, piping and associated valves, vessels (and their supports) in systems where both the design pressure and temperature are equal to or less than 275 psig and 200*F, respectively, are exempted from volumetric and surface examinations.

Reference:

Para IWC-1220 (a).

E2 Class 1 component connections, piping and associated valves, vessels (and their supports), that are three-inch nominal

! pipe size and smaller are exempted from volumetric and

' surface examinations. (Sufficient normal makeup capacity using onsite power exists for greater than a three-inch break.)

Reference:

Para IWB-1220 (b) (1) .

s E3 Class 2 component connections, piping and associated valves, j

and vessels (and their supports), that are four-inch nominal pipe size and smaller are exempted from volumetric and surface examination.

Reference:

Para IWC-1220 (d) .

E4 Open-ended portions of Class 2 lines in a non-closed system (e.g., suction line from a storage tank, or discharge line of a containment spray header) extending to the first shutoff valve are exempted from hydrostatic and pressure test require-ments.

Reference Para IWC-5220 (d).

1 E5 Class 2 circumferential welds that are not structural dis-continuities nor within 3 pipe diameters of the centerline of rigid pipe anchors, or anchors at the penetration of the.

primary reactor containment, or at rigidly anchored components are exempted from volumetric and surface examination.

Reference:

Table IWC-2520, Examination Categories C-F and C-G.

l i

NOTE: References are to the indicated portion of ASME Boiler and Pressure 1

Vessel Code,Section XI, 1974 Edition through the Summer 1975 Addenda.

l-I i

i B-1

'l Table B-2 l'

Requests for Relief

, w: .

Relief Request Code Required In Lieu of Identifier Relief Request Exam Exam R1 Class 2 component connections, Volumetric Surface piping and associated valves, (if nominal l and vessels, that are 0.5 pipe size inches nominal wall thickness exceeds 4 in.)

i. or less, i

Basis for Relief i

l' Volumetric examination of thin '

walled pipe does not produce reliable results. In recogni-I tion of this, later Addenda of

! Section XI (e.g., 1977 Edition, Summer 1979 Adder.da) establish

! I the volumetric examination cut-off point as 0.5 inch for Class 2 systems.

R2 Class 2 components of systems Volumetric System or portions of systems that are (if nominal' pressure not required to operate above pipe size test every.

a pressure of 275 psig or exceeds 4 in.) 3 1/3 yrs.

-l temperature of 200*F except for limited periods which are far J

less than one percent of normal

{

plant operating time.

' Basis for Relief This relief request encompasses-the intent of Exemption El, as provided by IWC-1220(a). Opera-i ting conditions are specified in lieu of design conditions since the latter are often overly con-servative. As a result, no additional burden is accrued in the form of added examinations which would normally be excluded had the designer not given extra consideration to conservatism.

I B-2 i- -

I h Relief Code Required In Lieu of 4

Request Identifier Relief Request Exam Exam i.

3 R2 Situations where the stated (Cont.). pressure and temperature condi-tions are exceeded bY a modest l_

amount will be addressed on a case-by-case basis if.the period where the threshholds are breached is of very small duration.

I Further amplification will be provided in such cases.

i Component welds whose physical volumetric Surface or R3 location within the plant Visual, as restricts access to the weld appropriate due to such factors as: being located within a wall slee've or penetration, in a high radiation area, very high in

a room, adjacent to a wall or Surface Visual during other restriction without hydrostatic sufficient clearance to perform testing once

examinations. every 10 yrs. ,

Basis for Relief l

Specific reasons for requesting exemption from an examination requirement will be provided in each instance.

~* R4 Branch pipe to pipe welded Volumetric Surface i

3 joints that are Class 1 and greater than 6 inches in diameter or are Class 2.

Basis for Relief a"

The physical design of branch connections does not permit meaningful volumetric examina-tion. This fact has been recognized by ASME Section XI and the requirement for volu-metric examination of branch l connections has been dropped from later Addenda of the Code (e.g., 1977 Edition, Summer 1978 Addenda).

l r I '

i B-3 i

-fi

'. l l Relief

-Request Code Required In Lieu of Identifier Relief Request Exam Exam j g-

.6 R5 Integrally welded supports volumetric Surface in Class 1 systems. ,

Basis for Relief

.l. The physical design of integrally i welded supports (fillet or partial penetration welds) 1- does not permit meaningful j volumetric examination _. This fact has been recognized by ASME Section XI and the require-i ment for only volumetric examina-

' tion of integrally welded supports has been-dropped from later Addenda'of the Code (e.g., 1977 a- Edition, Sumer 1978 Addenda) .

j R6 Class 1 component connections, Volumetric Surface

,' piping and associated valves, (if nominal ,

and vessels that are 0.375 pipe size )'

inches nominal wall thickness exceeds 3 in.)

or less.

Basis for Relief 4 Volumetric examination of thin walled pipe does not produce

, a reliable results based on the material geometry and on the operator's ability, experience and other " human factors" intangibles that make the examination results nonreproduci-ble. In order to provide a ji greater factor of safety for Class 1 systems compared to Class 2 systems, the cutoff point for volumetric examina-tion is established as 0.375 inch for Class 1 systems.

I i

' t B-4

l^

l-I

-t Table B-3 i

Weld Summary Sheet Terms The following information is presented in the Weld Summary Sheets:

Item Description

" System" Identifies the system name.

"ISD No." Identifies the Inservice Diagram (ISD) number which corresponds to the subject system.

"ISD Rev." Identifies the revision of the ISD used to prepare

-; the program.

"Line Number" Identifies a discrete portion of the system with

- piping having the same function, pressure / tempera-l ture ratings, size,'and pipe tchedule. This number is the identifying number on the ISD's.

I "Line Description" Describes the beginning and end of that particular line number.

i

" System Class" Identifies the ASME Class for the subject line.

Possible entries are:

1 -

ASME Class 1 2 - ASME Class 2 3 -

ASME Class 3 2(A) - Augmented Class 2 (These systems are not within the scope of ASME B&PV Code Section XI, but do receive inspection because of their function as containment penetrations. )

"ISD Coordinate" Identifies the coordinates on the ISD where the

'l subject line is located. Where only one ISD is associated with the system only one coordinate is givent e.g., C-8. Where more than one ISD is associated with the system, the unique part of the ISD number is given together with the coordinate; e.g., 20B/D-4.

" Weld Type" Identifies each type of weld found in the subject line. Possible entries ares

! CIRCUM -

Circumferential butt welds t BRANCH - Branch welds in ASME Class 2 systems f

B-5 L

Table B-3 (continued)

Item Description

" Weld Type" BRANCH - Branch welds in ASME Class 1 (continued) DIA < 6 IN systems with the branch less than or equal to 6 inches nominal pipe size.

l 1

BRANCH - Branch welds in ASME Class 1 DIA > 6 IN systems with the branch greater l than 6 inches nominal size g

, SUPPORT - The weld between a pressure retaining component and its j support LONGITUDINAL -

Longitudinal fabrication welds CIRCUM -

Circumferential butt welds that BIMETALLIC are also bimetallic.

"No. of Weld" Identifies the number of welds of that particular weld type for the subject line number.

I .f'

" Required Code Exam" Identifies the examination that would be required by the Code (i.e.,1974 Edition of Section XI through the Summer 1975 Addenda) taking into account the permissible Code exemptions, but not the Requests for Relief from Code requirements. The possible entries are:

VOL -

Volumetric examination SUR - Surface examination

'- HYD - Hydrostatic pressure testing NONE - Applies to augmented systems that have no Code required examinations l

" Code Exemption" Identifies the applicable Code Exemption Identifier from Table 3-2 of the Inservice Inspection Program description report. Possible entries ares El, E2, E3, E4, and E5.

l i i

" Request for Relief" Identifies those welds for which a request for relief from Code requirements is made.

"No. of Welds" Identifies the number of welds of that particular l

weld type for which relief from Code requirements

is requested.

B-6 l .

L.

l

.p

.)

Table B-3 (continued) l-Item Description

" Reason" Identifies the generic Relief Request Identifier from Table 3-3 of the Inservice Inspection Program description report. Possible entries are:

R1, R2, R3, R4, RS, and R6

, "In Lieu of Identifies the examination to be performed in lieu r ! Examinations of the Code required examination for those welds for which relief is requested. Possible entries are:

SUR -

Surface examination HYD -

" Hydrostatic" pressure testing i PRS - " Pressure" testing FLW - " Flow" testing l

! NONE - No examination or testing is to be performed.

Identifies the note number which presents supple-

" Notes"

' mental or explanatory information for the Request for Relief or examinations performed in excess of Code requirements, I

r .

e m.

c :

i I

l t i 1

l t

! B-7 I

J

l 1

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Table B-4 i

f Weld Summary Sheet Index l and

\

Cross Reference to Inservice Diagrams i

' Inservice Diagram Weld Summary System Number Sheet Pages i

Drywell Inerting and Purge 11825-FM-18A, Rev. 18 1-3 Residual Heat Removal 11825-FM-20A, Rev. 15 4-13 ll825-FM-20B, Rev. 15

- ll825-FM-20C, Rev. 14 ll825-FM-20D, F,av. 14 Reactor Core Isolation Cooling 11825-FM-22A, Rev. 13 14-15 1

Core Spray ll825-FM-23A, Rev. 13 16-19 Reactor Water Cleanup .1825-FM-24A, Rev. 12 20-21 s

High Pressure Coolant Injection 1.825-FM-25A, Rev. 12 22-24 ll325-FM-25B, Rev. 11 Reactor Water Recirculation ll325-FM-26B, Rev. 9 25-28 Control Rod Drive Return 1 825-FM-27A, Rev. 8 29-30

{

, Main Steam 11825-FM-29A, Rev. 13 31-33 Feedwater ll825-FM-34A, Rev. 15A 34-35 4

i f

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of 35

~

JAMES A. FITZPATRICK- Page 3 NOTES-System: Drywell- Inerting and Purge

1. Containment inerting and purge lines are not within the scope of ASME Boiler & Pressure Vessel Code,.Section XI. These lines are designated as Class 2 - Augmented,'and all structural discontinuity.

circumferential, support and.5 ranch (greater than 4 inch) . welds will be surface examined. The pipe wall thickness is 0.375 inches.

2. Vacuum breaker lines are not within the- scope of ASME Boiler & Pressure Vessel Code,Section XI.

These lines are designated as Class 2 - Augmented, and all structural discontinuity circumferential, support, and branch (greater than 4 inch) welds will be surface examined. The pipe wall thickness is 0.375 inches. ,

O a

_ ~ . -

- .- . - ~. . , _ . . . . . .. - . . - . . - - - -- - -_

Plus 4 of 35 llWSERVICE IterECTIOpf PROGRm g Synesso RE510UAL HEAT REMOVAL ISD No. Il825-FM-2cA, w,14 WELD SUR884ARY SHEET Apped g H. H. ASWITH, CHIEF ENGINEER M'[

12-4-78 James A. FitrPetrick Nuclear Power Plant a 8, C, D g Request for Relwf System ISD No. of Code Code No. of In Lieu of IJoe Numaber Line Decription Class Coordmate Weld Type Welds Exam Exemption Welds Reason Examination Notes 16"-W20-302-78 FROM RHR PUMP P-38 TO LINE 2 D-5/200 CIRCUM 10 VOL 10 R2 PR$ I 20"-W20-302-88 BRANCH 4 VOL 4 R2 PRS I SUPPORT 1 SUR I R2 PRS I 6"-W20-302-7D FROM RHR PUMP P-3D TO LINE 2 0-3/200 CIRCUM 9 VOL 9 R2 PRS I 20"-W20-302-88 BRANCH 4 VOL 4 R2 PRS I SUPPORT 1 SUR 1 R2 PRS I 20"-W20-302-88 FROM LINE 16"-W20-302-78 TO 2 E-5/200 CIRCUM 6 VOL 6 R2 PR$ 1 LINE 24"-W20-302-Il8 BRANCH 8 VOL 8 R2 PRS I SUPPORT 3 SUR 3 R2 PRS I y 16"-WS-302-568 FROM VALVE RHR-1778 TO LINE 2 J-1/200 CIRCUM 1 VOL I R2 PRS I U 24"-W20-302-118 16"-W20-302-98 FROM LINE 20"-W20-302-88 TO 2 F-5/200 CIRCUM 2 VOL 2 R2 PR$ I

, VALVE 10-MOV-658 BRANCH 2 Vol 2 R2 PR$ 1 16"-W20-302-108 FROM RHR HEAT EXCHANGER E-28 2 G-5/200 CIRCUM 14 V0L I4 R2 PR$ I TO LINE 20"-W20-302-88 CIRCUM 2 HYD ES - - -

BRANCH % V0L 4 R2 PR$ 1 SUPPORT 3 SUR 3 R2 PRS 1 2 F-5/20C CIRCUM 9 VOL 9 R2 prs 1 16"-W20-302-7A FROM RHR PUMP 3A TO LINE 20"-W20-302-8A BRANCH 4 VOL 4 R2 PR$ 1 ,

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Peer 6 ef 15 g Systeen RESIDUAL HEAT REMOVAL Prepami By W. J. NEWELL 9-7-78 WELD SURARAARY SHEET a ISD No. Il825-FM-20A Rev.14 Approved By M. H. ASKWITW, CHIEF ENGINEER 12-4-78 8, C D James A. FitrPatrick Blucisar Power Plant g Request for Relief System ISD No. of Code Code No. of in Lieu of

@ Nunatw Line Description Class Coordmate Wekt Type Wekts Exam Exeunption Welds Reason Esamination Notes 24"-W20-302-Il8 FROM LINE 20"-W20-302-88 TO 2 1-2/200 CIRCUM 13 VOL 13 R2 PRS 1 LINE 2%"-W20-902-I%A CIRCUM 2 HYD ES -

SUPPORT I Suk i R2 PRS I BRANCH 6 VOL 6 R2 PRS I 16"-W20-302-15A FROM LINE 24"-W20-302-IIA TO 2 G-3/20A SUPPORT I SUR I R2 PRS 1 FIRST SEISMIC SUPPORT 16"-W20-302-158 FROM LINE 2%"-W20-302-IIB TO 2 E-3/208 SUPPORT 1 $UR I R2 PRS I FIRST SEISMIC SUPPORT 16"-W20-302-ISA FROM LINE 24"-W20-302-IIA TO 2 G-3/20A CIRCUM I HYD ES - - - -

12"-W20-302-13A CIRCUM 5 VOL 5 R2 PRS I b

BRANCH 2 VOL 2 R2 PRS I SUPPORT 4 SUR 4 R2 PRS 1 12"-W20-302-13A FROM LINE 16"-W20-302-15A TO 2 G-3/20A CIRCUM 6 HYD E5 - - -

LINE 10"-W20-302-12A CI RCUM 16 VOL 16 ' R2 PRS I BRANCH % VOL 4 R2 PRS I SUPPORT 1 SUR I R2 PRS 1 10"-W20-302-12 A FROM LINE 12**-W20-302-13A TO 2 G-3/20A CIRCUM 28 VOL 22 R2 AIR FLOW l.2 CONTAINMENT SPRAY HEADER 6 R2 SUR 1.3 BRANCH 2 VOL 2 R2 PRS .I SUPPORT 4 SUR I R3 $UR 4 ONE $1DE 16"-W20-302-158 FROMLINE2%"-v20-302-Il[To 2 E-3/208 CIRCUM 1 HYD ES -

12"-W20-302-138 CIRCUM 8 VOL 8 R2 , PRS I BRANCH 2 VOL 2 R2 PRS I SUPPORT 8 $UR 8 R2 PRS 1

~

Peer 7 af 35 INSERVICE INSPECTION PROGRAM n Sysessa RESIDUAL HEAT REMOVAL Prepared By W. J. NEWELL I'7,7g WELD SUR0hlARY SHEET ISD No. It825-FM-20A Itse.14 Appromi By H. H. ASlDitTH, CHIEF ENGINEER 12-4-78

8. C, D ""

g Request for Relief System ISD No.of Code Code No. of In lieu of IJpe Number Line Deeription Class Coordmate Weki Type Welds Exam Excemption Welds Reason Examination Notes 12"-W20-302-138 FROM LINE 16"-W20-302-l58 TO 2 E-3/208 CIRCUM 4 HYD ES - - - -

LINE 10"-W20-302-12A CIRCUM 15 VOL 15 R2 PRS 1 8 RANCH 4 V0L 4 R2 PRS I SUPPORT 7 $UR 7 R2 PRS 1 10"-W20-302- 128 FROM LINE 12"-W20-302-138 TO 2 D-3/208 CIRCUM 31 VOL 6 R2 SUR I.)

CONTAINMENT SPRAY HEADER 25 R2 AIR FLOW 1,2 8 RANCH 2 VOL 2 R2 PRS 1 SUPPORT 4 $UR I R3 SUR 4 ONE $1DE 8"-W20-152-39 FROM VALVE FPC-34 TO LINE 2 C-2/20D CIRCUM 23 HYD El - - - -

20"-W20-152-28 BRANCH 3 HYD El - - - -

b, w

SUPPORT 7 HYD El - - - -

24"-W20- 152-38 FROM PENETRATION X-2258 TO 2 0-8/208 CIRCUM 2 HYD E5 - - - -

LINE 20"-W20-152-68 CIRCUM 8 VOL 6 R2 PRS 1 E4 2 R2 SUR 1,10 BRANCH 3 VOL 3 R2 PRS 1 SUPPORT 2 SUR I R2 PRS I 20"-W20-152-68 FROM LINE 24"-W20-152-38 TO 2 8-4/200 CIRCUM 9 VOL 9 R2 PRS I RNR PUMP 38 SRANCH I VOL 1 R2 PRS I 20"-W20-152-6D FROM LINE 24"-W20-152-38 TO 2 A-3/20D CIRCUM 9 VOL 9 R2 PRS l RHR PUMP 3D SRANCH I VOL 1 R2 PRS I 20"-W20-152-28 FROM LINE 20"-W20-152-2C TO 2 H-2/20C CIRCUM 3 HYD ES - - - -

LINE 20"-W20-152-68 CIRCUM 9 V0L 9 R2 PRS I 8 RANCH 5 VOL 5 R2 , PRS I SUPPORT 4 $UR 4 R2 PRS 1

s .

Page 8 et 35 INSERVICE INSPECTION PROGRAM W. J. NEWELL 9 7,7g .

e Syseena RESIOuAL HEAT REMOVat Prepe m i By WELD

SUMMARY

SHEET Q ISD No. 11825-FM-20A Rev.14 APprowl By H. H. ASRWITH. CHIEF E10CINEER 'I2-4-78

8. C, D James A. FitrPatrick Nuclear Power Plant one.

Request for Relief gg System ISD No.of Code Code No. of In Lieu of Line Nmaber Line Description Class Coordinate Weld Type Welds Exam Exemption Welds Reasom Enamination Notes 20"-W20-152-20 FROM LINE 20"-W20-152-2B TO 2 C-3/200 CIRCUM 10 VOL 10 R2 PRS 1 LINE 20"-W20-152-60 BRANCH 3 VOL 3 R2 ' PR$ 1 SUPPORT 1 SUR I R2 PRS I 24"-W20- 152-3A FROM PENETRATION X-225A TO 2 H-7/20A CIRCUM 9 VOL 7 R2 PRS I LINE 20"-W20-152-6A En 2 R2 suR 1,10

. BRANCH 3 VOL 3 R2 PRS I 4 SUPPORT 2 SUR I R2 PR$ . I 20"-W20-152-6A FROM LINE 24"-W20-152-3A TO 2 1-5-20C CIRCUM 9 VOL 9 R2 PRS 1 RHR PUMP 3A BRANCH 3 VOL 3 R2 PRS I 20"-W20-152-6C FROM LINE 24"-W20-152-3C TO 2 1-3/20C CIRCUM 9 VOL 9 R2 PRS 1 to RHR PUMP 3C BRANCH 2 V0L 2 R2 PR$ 1 20"-W20- 152-2A FROM LINE 20"-W20-152-2C To 2 G-3/20C CIRCUM 8 VOL 8 R2 PRS 1 LINE 20"-W20-152-6A BRANCH 3 VOL 3 R2 PR$ 1

$UPPORT 1 SUR 1 R2 PRS I j 20"-W20-1,52-2C FROM LINE NEAR MOV-10-NOV-17 TO 2 A-8/208 CIRCUM 3 HYD E5 - - - -

LINE 20"-W20-152-6C CIRCUM 8 VOL 8 R2 PRS 1 BRANCH 7 VOL 7 R2 PRS 1 SUPPORT 7 SUR 7 R2 PRS 1 20"-W20- 152-28 FROM LINE 20"-W20-152-2C TO NEAR 2 H-2/20C CIRCUM 3 HYD ES - - - -

LINE 20"-W20-152-68 BRANCH I VOL I R2 PRS 1 SUPPORT 3 $UR 3 R1 PRS 1

_ ' . - . .- ~. . . - . .s... . - -- . - - - . - - - - - -~.

Page 9 eE 35 s

i G RM -

n Synem RE580JL

EAT etr0 VAL Preparal By W. J. NEWELL 9-7-75 w,

M ISD No. H E25-FM-20A Rec.IL -

WELD SURARSARY SHEET Approved By **.M. A5lOntTae. CMIEF E%GINEER "'- B. C. D

.h A Med W Power M w, I ' I' Requured System ISD No.of Code Code No. of In Lwu of Line Number Line Desenpten Class Coordmate Weld Type Welds Exam Exemption Welds Reason Exame.ation Nm 20" W20-902-1 FROM VALVE RHR-88 TO I A-5/208 CIRCUM 9 VOL 1 R3 HYD $

VALVE 10-MGV-17 BRANCH 2 SUR - - - -

DIA < 6 th SUPPORT 5 VOL 5 R5 Sum -

4"-W20-902-36 FROM VALVE 10-MOV-32 TO 2iA) C-1/208 CIRCUM 7 HYD E3 6 -

SUR &

VALVE 10-MOV-33 BRANCH I HYD E3 - - - - ;

SUPPORT 2 HYD E3 2 -

SUR E ',

I F-4/20A '

24"-W20-902- 14A FROM VALVE RHR-81A TO VALVE CIRCUM 13 VOL I R3 NYD 10 MOV-25A CIRCUM 3 VOL & - - - -

BINETALLIC SUR SUPPORT 6 VOL 5 R5 Sun -

T BRANCH 2 SUR - - - -

U DIA < 6 IN 24"-W20-902-148 FROM VALVE RHR-BIB TO VALVE I E-3/205 CIRCU't 14 VOL I R3 HYD 10 Mov-258 CIRCUM 3 VOL s - - - - '

BIPETALLIC SUR SUPPORT 6 VOL 5 R5 Sun -

BRANCH SUR - - - -

3 OlA < 6 IN 16"-W20-302-9A FROM LINE 20"-W20-302-8A TO 2 E-5/20C CIRCua 1 MYD E5 - - - -

LINE 20"-5LP-302-33A CIRCUM 12 VOL 12 RI $UR -

SUPPORT 3 $UR - - - -

BRANCH 2 V0L 2 R4 $UR -

20'*-W20-1504-42 FROM RECIRC LINE 02-28"-WM-GE-18 i B-5/235 CIRCUM 4 VOL - - - -

TO VALVE RHR-88 BRANC* I 5'e R - - - -

31A < 6 14 ,

CIRCUM i V0L & - - - -

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. 9 Puer il at 35 syense RESIOUAL HEAT REMOVAL IN8ERVICE IlfrECTIOld PROGRA88 g3 15-78 n Proposed By M. J. PARTRIDGE a

ISD No. 18825 FM-20A g,,' 14 Approved py H. H. ASRWITH . CHIEF EIIGINEER 82-4-78 B. C. 0 James A. FitrPetrack 90mdsor Posser Plant g Request for Ratief System ISD No. of Code Code No. of in Lieu of p Nunniser IJne Descriptaon Class Coordmate Weld Type Welds Esarn Emeseption Welds Reason Enamunetion Notes .

16"-W20-302-98 FROM LINE 20"-5LP-302-338 TO 2 G-3/20D C IRCUM 12 VOL 12 RI SUR -

VALVE 10-MOV-658 CIRCUM 2 NYD - = = -

BRANCH 2 VOL 2 R4 $UR -

SUPPORT 3 $UR - - - -

20"-5LP-302-338 ASSEMBLY ON TOP OF RHR HEAT 2 G-3/23D CIRCUM 3 VOL - - - -

EXCHANGER E-28 SRANCH 3 VOL 3 R4 $UR -

8"-5HP-902-328 FROM LINE 23-10"-$HP-902-34 TO 2 1-3/200 CIRCUM 27 VOL 27 RI SUR -

VALVE PCV-698 CIRCUM 2 HYD ES - - - -

8 RANCH I VOL I R4 $UR -

SUPPORT 3 SUR - - - -

?

8"-5LP-302-378 FROM VALVE PCV-698 TO 2 H-3/200 CIRCUM 4 VOL 4 RI SUR -

LINE 20"-5LP-302-338 BRANCH I V0L I R4 $UR -

4N 5LP-302-868 FROM LINE 20"-5LP-302-338 TO 2 G-4/20D CIRCUM I HYD E3 - - - -

VALVE SV-748 6"-5LP-302-348 FROM VALVE SV-748 TO 2 G-4/200 CIRCUM 18 VOL 18 R1 SUR -

16"-w20-152-58 CIRCUM 2 NONE E4. ES - - - -

BRANCH 2 V0L 2 R4 $UR -

SUPPORT 4 $UR - - - -

16"-W20-302-158 FROM VALVE 10-MOV-348 TO 2 E-3/208 CIRCUM 3 HYD El - - -

8 VALVE lo-MOV-348 BRANCH I HYD El - - -

8 SUPPORT 2 HYD El - - - 8 i

i e

l

= . J

- _ _ . _ . _. _ . _ - _ "[ / __. __ -

4 her 12 et 35

""" "" N M. J. PARTRIDGE Il-20-78 n armes REslouAL 1+ EAT REMOVAL W By nm.

y ISD No. 11825-FM-20A Itee. 34 WELD gasaansaalY SHEET Approved By H. H. ASKWITH , CHIEF EIIGINEER 12-4-78

~ , C, D Janses A. FitrPatrick % clear Pouser Plant g Itequest l'or Rehef System ISD No.of Code. Code No. of In Lieu of Igne Nussbar f.Jne Descriptaon Class Coordinate Weld Type Welds Exam Exeunption Welds Reason Examination Notes 6"-W20-302-168 FROM LINE 16"-W20-302-158 To 2 G-3/20s CIRCUM 'p. 3 HYD El - - -

8.

I HYD El - - - '- d VALVE !0-MOV-388 BRANCH e

6"-W20-152- H e FROM VALVE 10-MOV-388 TO 2 G-6/208 CIRCUM 10 FLW Et, E4 - - -

8 SUPPRE$$lyd CHAM 8ER BRANCH I FLW Et, E4 - - -

8 PENETRATION X-2llB $UPPORT I FLW Ei, E4 1 -

SUR 8,9 16"-W20-151-58 FROM LINE 16"-W20-302-158 TO 2 G-6/208 CIRCUM 10 FLW Et, E4 - - - 8

$UPPRESSION CHAM 8ER BRANCH 7 FLW El, E4 - - -

8 PENETRATION X-2108 $UPPORT 2 FLW Et, E4 1 -

SUR 8,9 16"-W20-302-15A FROM VALVE 10-MOV-39A TO 2 G-3/20A CIRCUM 5 HYD El - - -

8 VALYE lo-M0V-34A BRANCH 3 HYD El - - - 8 0 $UPPORT 4 HYD El - - - 8 6"-W20-302-16A FROM LINE 16"-W20-302-15A TO 2 E-4/20A CIRCUM 3 HYD El - - -

8 VALVE 10-60V-38A 6"-W20- 152-44A FROM T sVE 10-MOV-38A TO 2 E-5/20A CIRCUM 11 FLW Et, E4 - - - 8

$UPPRESSIC*f CMAMBER BRANCH I FLW Et, E4 - - - 8 PENETRATION X-218A SUPPORT I FLW El, E4 1 -

SUR 8,9 16"-W20-151-5A FROM LINE 16"-W20-302-15A TO 2 E-6/20A CIRCUM 7 FLW Et, E4 - - -

8 SUPPRESSION CHAM 9ER BRANCH 8 FLW Et, E4 - - - 8 PENETRATION X-210A SUPPORT 3 FLW El, [4 I -

SUR 8,9

JAMES A. F1TZPATRICK Page 13 of 35 NOTES System: Residual Heat Removal

l. Design temperature is 280*F, design pressure' is 325 psig; however, in this portion of the system, the system ,

operating pressure exceeds 275 psig for only approximately five (5) . minutes in the low pressure coglant w

~

.Jnjection mode of operation with unassisted _ low pressure coolant injection for medium size (0.3 ft ) breaks.

~

Accordingly, this portion of the RHR system is considered to be a moderate energy system since it does not normally operate at this elevated pressure during normal operation, cold shutdown, or refueling modes of

- ~

operation. This portion of the system is normally maintained at a low nominal pressure and a mechanism for piping failure is unlikely. This portion of the system is constructed of carbon steel and, therefore, is not subject to intergranular stress corrosion cracking and is nog subjected to cyclic stresses or high.

stresses that would result in a piping failure. This portion of the system during the residual heat removal mode of operation also exceeds 200*F for only approximately four (4) hours at the beginning of operation in this mode. This elevated temperature operation represents less than one percent of system operating- time and, therefore, also qualifies as a moderate energy system. This portion of the system will be " Pressure" tested every 3 1/3 years to confirm piping system integrity. .

2. " Pressure" test or " flow" test not feasible for containment spray line from inside drywell penetration to spray ring. An " airflow" test is conducted periodically.

to h3 Surface exam will be performed as augmented inspection of 6 circumferential welds near Penetration X-39A.

4. Penetration to pipe fillet welds are inaccessible from the side next to containment. ~ Perform surface examination on outside weld only.

5 One circumferential weld is located inside containment penetration X-12 and is inaccessible for volumetric or surface examination.

6. Six circumferential welds and two support welds will have augmented surface examination. One circumferential weld is locat'ed inside containment Penetration X-17 and is inaccessible for volumetric or surface examination.

7 One circumferential weld is located inside each of containment Penetrations X-13A and X-138 and is inaccessible for volumetric or surface examination.

8. Design pressure is 150 psig and design temperature is 187"F.

9 Augmented surface examination will be performed at Penetrations X-210A, X-2108, X-211 A and X-211B.

10. Augmented surface exam will be performed on two welds near each of the suppression chamber Penetrations X-225A and X-2258.

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t JAMES A. FITZPATRICK Page 15 of 35 NOTES System: Reactor Core Isolation Cooling e

1. Fabrication welds on thermal sleeve.

2. Pipe is 8-inch std. wall pipe with a wall thickness of 0.322 inches.

3 Augmented inspection is being performed at Penetration X-10.

4. Augmented inspection is being performed at Penetration X-224.

to O 5 Pipe is 4-inch Schedule 80 pipe with a wall thickness of 0.337 inches.

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JAMES A. FITZPATRICK' Page 19 of 35 i

l NOTES System: Core Spray 17 Design pressure is 50 'psig and design tenverature is 150*F.

2. From suppression chamber penetrations to first isolation valve, augmented surface examination will be performed.

3 Design temperature is 150*F, design pressure is 400 psig; however, system operating pressure exceeds 275 psig for only approximately six (6) minutes in the unassisted Core Spray Operating Mode for the j

worst case small break. Accordingly, this portion of the Core Spray System is considered to be a moderate energy system since it does not normally operate during normal operation, cold shutdown, or i refueling modes of operation. This system is normally maintained at a low nominal pressure and a mechanism for piping failure does not exist. -The system is constructed of carbon steel, and therefore, is not subject to' intergranular stress corrosion cracking and is not subjected to cyclic stresses or high stresses that would result in a_ piping failure. This portion of the system will be " Pressure" e tested every 3 1/3 years to confirm piping system integrity. ,

~

! 4. One circumferential weld is located inside Containment Penetration X-16A and is inaccessible for ,

volumetric or surface examinations.

i 5 Design pressure is 150 psig and design temperature is 150*F.

6. One circumferential weld is located inside containment Penetration X-16B and is inaccessible for volumetric or surface examinations.

7 Eight circumferential welds, two 3/4 inch branch welds, and one support weld are located on a pipe 15 feet above floor level in a room housina the RWCU sludge tanks and non-regenerative heat exchangers. .

There is limited access to this room and radiation levels exceeding 10,000 mR/ hour exist. Since the configurations and service conditions of Lines 10"-W23-902-5A and 10"-W23-902-58 are essentially identical, generic problems would be identified on Line SA. The pressure test specified will yield little reduction in detection of flaws and will minimize the unnecessary radiation exposure to inspec-tion personnel .

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's JAMES A. FITZPATRICK Page 21 of 35 NOTES System: Reactor Water' Cleanup

1. One 'circumferential weld is located inside containment Penetration X-14 and is inaccessible for volumetric or surface examination.

to I

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__ _ _ , _ ~ . , . - ,

Page 22 of 35 INSERVICE INSPECTION PROGRAM g Systeme HICH PRESSURE COOLANT Gg INJECTION WELD

SUMMARY

SHEET o Approved By H. H. ASKWITH. CHIEF ENGINEER 12-4-78

-M 5 R James A. Fit Petrack Nuclear Power Plant Request for Relief

. . System ISD No. of Code Code No. of In Lieu of line Number Line Description Class Coordmate Weld Type Welds Ezam Exemption . Welds Reason Examination Notes 10"DHP- 902- 19A FROM MAIN STEAM LINE I B-2/25A CIRCUM 16 VOL I R3 HYD I 29-24"-$HP-902-IC TO VALVE BRANCH 3 SUR - - - -

23-MOV-16 DIA < 6 IN SUPPORT 4 VOL 4 R5 $UR -

10"-SHP-902-19 FRO 1 VALVE 23-MOV-16 TO HPCI 2 0-3/25A CIRCUM 26 VOL - - - -

TURBINE 23-TU-2 CIRCUM I HYD ES - - - -

B RANCH 7 VOL 7 R4 $UR -

SUPFORT 6 SUR - - - -

10"-SHP-902-34 FROM LINE 10"-SHP-902-19 TO 2 C-2/25B CIRCUM 8 VOL - - - -

LIN1! 10-8"-SHP-902-32A AND 318 BRANCH I VOL I R4 SUR -

Y t

14"-W25-902-3 FROM HPCl PUMP 23P-IA TO 2 C-3/25B CIRCUM 20 VOL 20 R2 PR$ 2 VALVE 23-Mov-19 CIRCUM 4 HYD E5 - - - -

BRANCH 7 VOL 7 R2 PRS 2 SUPPORT 6 $UR 5 R2 PRS 2 14"-W25-902A-3A FROM VALVE 23-MOV-19 TO I E-5/25A CIRCUM 9 VOL - - - -

LINI! 34-18"-WFP-902A-48 BRANCH 2 SUR - - - -

DIA < 6 IN 10"-W25-902-4 FROM LINE 14"-W25-902-3 TO 2 F-5/25A CIRCUM 8 VOL 8 R2 PRS 2 VALVE 23-MOV-21 CIRCUM 1 HYD ES - - - -

BRANCH I VOL 1 R2 PRS 2 SUPPORT I SUR 1 R2 PRS 2

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o Pues 23 et - 35 g Syearum MIGH PRESSURE COOLANT Prepared By M. J. PARTRIDGE 11-20-78 g ISD No.

INJECTION Il825-FM-25A Rev. 12 WELD

SUMMARY

SHEET H. H. ASKWITH, CHIEF ENGINEER 12-4-78 Approved By Il825-FM-258 Rev. II James A. FitrPatrick Nucteer Power Plant o Required "# I" System ISD No. of Code Code No. of In Lieu of EJne Number Line Description Class Coordinate Weld Type Welds Exara Exemption Welds Reason Examination Notes 18"-SLP-152-37 FROM HPCl TUR81NE EXHAUST TO 2 D-4/258 CIRCUM 1 VOL 1 R2 FLW 3 LINE 20"-$LP-352-25 20"-SLP-152-25 FRON LINE 18"-SLP-352-37 TO 2 D-4/258 CIRCUM 13 VOL 11 R2 FLW 3 LINE 16"-SLP-152-25A 2 R2 SUR 3,4 BRANCH 13 VOL 13 R2 FLW 3

$UPPORT 4 SUR 3 R2 FLW 3,4 16"-SLP-152-25A FROM LINE 20"-SLP-352-25 TO 2 8-5/25A CIRCUM 4 V0L 4 R2 SUR 3,4 LINE 24"-SLP-152-26 BRANCH I VOL 1 R2 FLW 3 24"-SLP-352-26 FROM LINE 16"-SLP-152-25A TO 2 8-5/25A CIRCUM 2 VOL 2 R2 SUR 3,4 Y PENETRATION X-214 BRANCH 1 VOL 1 R2 FLW 3 SUPPORT- 1 SUR I R2 SUR 3,4 16"-W25-152-17 FRO 1 SUPPRESSION CHAMBER 2 C-8/25A CIRCUM 12 HYD El 2 -

SUR 5.6 PENETRATION X-226 TO BRANCH 3 HYD E1 - - -

5 VAL'f E 23-MOV-57 SUPPORT 2 HYO El 1 -

SUR 5,6 16"-WCP-152-1 FRO 1 VALVE 23-MOV-17 TO 2 1-2/25A CIRCUM 24 HYD E1 - - -

5 HPCI PUMP 23P-1A BRANCH 8 HYO El - - -

5

$UPPORT 2 HYD El - - -

5 e

. .- - ~.- _ . - - - . . . _ - -_. . . - _ ,

JAMES A. FITZPATRICK - Page 24 of 35 NOTES System: High Pressure Coolant injection I. One circumferential weld is located inside containment Penetration X-11 and is inaccessible for volumetric or surface examination.

2. This portion of the HPCI system is considered to be a moderate energy system since it does not normally operate during normal operation, cold shutdown, or refueling modes' of operation. This system is normally maintained at a low nominal pressure and a mechanism for piping failure does not exist. The system is constructed of carbon steel and, therefore, is not subject to inter-granular stress corrosion cracking and is not subjected to cyclic stresses or high stresses that would result in a piping failure. This portion of the system will be " Pressure" tested every 3 1/3 years to confirm piping system integrity.

3 Same as Note 2 except that a " Flow" test must be performed Instead of a " Pressure" test since these :

m lines are open to the suppression chamber.

O

4. Augmented surface exam will be performed on circumferential and support welds from Penetration X-214 through valve HPI-65 including the first seismic support past valve HPI-65 5 The design pressure is 100 psig and the design temperature is 140*F.

6. Augmented surface examination will be performed on two circumferential welds and one support weld between Penetration X-226 and Valve 23-MOV-58.

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- ~, - ~. _ _ _ -

~ , _ _ . . . _ _ _ - - _ _ __ .

. o Page 25 of 35 INSERVICE INSPECTION PROGRAM q System REACTOR WATER RECIRCULATION Prepared By M. J. PARTRIDGE 11-3-78 m

y ISD No. 11825-FM-268 Rev. 9 WELD

SUMMARY

SHEET Approved By H. H. ASKWITH. CHIEF ENGINEER 12-4-78 James A. FitrPetrick Nucteer Power' Plant o, g Request for Relief System ISD No. of Code Code No. of In Lieu of Line Number Line Description Class Coordinate Weld Type Welds Exam Exemption Welds Reason Examination Notes 28"-WM-GE-IA FROM REACTOR VESSEL N0ZZLE N-IB 1 E-5 CIRCUM 1 VOL &- - - - -

BIMETALLIC SUR TO RECIRC PUMP 02-2-P-IA CIRCUM 10 VOL - - - -

SUR -

BRANCH 5 - - -

DIA < 6 IN SUPPORT 3 VOL 3 R5 SUR -

RECIRC PUMP RECIRCULATION PUMP 02-2-P-IA 1 C-5 $UPPORT 7 V0L 4 R5 $UR -

02-2-P-IA 28"-WH-GE-2A FROM RECIRC PUMP 02-2-P-IA I B-7 CIRCUM 7 VOL - - - -

TO LINE 28"-WM-GE-3A BRANCH 3 SUR - - -

DIA < 6 IN Y SUPPORT 4 VOL 4 R5 SUR -

0 22"-WH-GE-3A RECIRC RETURN HEADER FROM 1 D-4 CIRCUM 4 VOL - - - -

LINE 28"-WH-GE-2A BRANCH 4 VOL 4 R4 $UR -

DIA > 6 IN SUPPORT 4 V0L 4 R5 $UR -

12"-WH- GE-4 A FROM LINE 22"-WH-GE-3A TO I D-4 CIRCUM I VOL & - - - -

BIMETALLIC SUR REACTOR VESSEL N0ZZLE N-2A CIRCUM 4 V0L - - - -

BRANCH I SUR - - - -

DIA < 6 IN 82"-WH-GE-5A FROM LINE 22"-WH-GE-3A TO I D-4 CIRCUM .I VOL & - - - -

BIM TALLIC SUR REACTOR VESSEL N0ZZLE N-28 CIRCUM 4 VOL - - -

BRANCH I SUR- - - - -

DIA < 6 IN

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Page 27 at 35 INSERVICE INFECTION PROGRAM synessa REACTOR WATER RECIRCULATION Prepared By M. J. PARTRIDGE 11-5-78 y ISD No. Il825-FM-268 ge,. 9 WELD

SUMMARY

SHEET Approved By H. H. ASKWITH, CHIEF ENGINEER n=

12-4-78 James A. FitrPetrick Nucteer Pouver Plant m Required D# I '

System ISD No. of Code Code No. of In Lieu of IJne Nunober Line Description Class Coordinate Weld Type Welds Exam Exemption Welds Reason Examination Notes 28" WM-GE-28 FROM REClRC PUMP 02-2-P 'S TO 1 H-8 CIRCUM 7 VOL - - - -

LINE 28"-WH-GE-3A BRANCH 5 SUR - - - -

DIA < 6 IN SUPPORT 4 VOL 4 R5 SUR -

22"-WH-GE-38 RETURN RECIRC HEADER FROM I G-4 CIRCUM 4 VOL - - - -

LihE 28"-WH-GE-28 DI > IN ; 4 VOL 4 R4 SUR -

SUPPORT 4 VOL 4 R5 SUR -

12"-WH-GE-48 FRCM LINE 22"-WH-GE-38 TO 1 G-4 CIRCUM i V0L & - - - -

IM A SUR REACTOR VESSEL N0ZZLE N-2F CIRCUM 4 VOL - - - -

BRANCH I SUR - - - -

Y DIA < 6 IN t:

12"-WM-GE-$8 FROM LINE 22"-WH-GE-38 T3 1 G-4 CIRCUM i VOL & - - - -

OI" # I $U" REACTOR VESSEL N0ZZLE N-2G CIRfUM 4 VOL - - - -

BRANCH I SUR - - - -

UIA < 6 IN 12"-WH-GE-6B FRCM LINE 22"-WH-GE-28 70 I G-4 CIRCUM I VOL & - - - -

^

REACTOR VESSEL NOZZLE N-2H CIRCUM 4 VOL - - - -

BRANCH I SUR - - - -

DIA < 6 IN

._ ,, _,, _ _ , , .. . . - ,_ ~~ ,-_ ._ . ~ . - - - - --.

Page 28 of 35 INSERVICE INSPECTION PROGRAM q - sysesen REACTOR WATER RECIRCULATION Preposed By M. J. PARTRIDGE- 11-5-78 gy ISD No. II825-FM-268 Rev. 9 WELD

SUMMARY

SHEET D*

Approved By H. H. ASKWITH. CHIEF ENGINEER 12-4-78 James A. FitzPatrick Nuclear Power Plant om

. Required I"

System ISD No. of Code Code No. of In Lieu of line Number Line Description Class Coordinate Weld Type Welds Exam Exemption Welds Reason Examination Notes 12"-WH-GE-7B FROM LINE 22"-WM-GE-3B TO 1 G-4 CIRCUM 1 VOL & - - - -

REACTOR VESSEL N0ZZLE N-2J 8IMETALLIC SUR CIRCUM 4 VOL - - - -

BRANCH I SUR - ' - - -

DIA < 6 IN 12"-WH-GE-88 FROM LINE 22"-WH-GE-38 TO 1 G-4 CIRCUM I VOL & - - - -

REACTOR VESSEL N0ZZLE N-2K

'" ^ $

CIRCUM % VOL - - - -

BRANCH I SUR - - - -

DIA < 6 IN 4"-WH- G E-98 BYF' ASS LINE AROUND VALVE I l-7 CIRCUM 10 VOL - - - -

y 02-MOV-538 4

.. . _ - - - . ~ ~.., - .- ~. . . . - , . - ~ . - - -- ~

Pues 29 af 35 I ICE I M W M m m m g Systeam CONTROL ROD DRIVE RETURN Prepared By M. J. PARTRIDGE 11-15-78 M ISD No. Il825-FM-27A - Rev. 8 WELD

SUMMARY

SHEET Approwl ry H. H. ASKWITH. CHIEF ENGINEER 12-4-78 m.

A7 ,

m

,g Request for Relief System ISD No.of Code Code No. of in Lieu of

'une Number Line Description Class Coordmate Weld Type Welds Exam Exemption Welds Reason Examination Notes 3" C-IS02-30 FROM VALVE CRD-Il0 TO I l-5 CIRCUM i VOL s - - - -

VALVE CRD-Il4 B METALL I C, M CIRCUM IO HYD E2 9 -

SUR 1 BRANCH I HYD E2 - - - -

DIA < 6 IN SUPPORT 2 HYD E2 2 -

SUR I 3"-C-1504-31 FROM VALVE CRD-Il4 TO REACTOR 1 J-5 CIRCUM 1 VOL & - - - -

BlMETALLIC SUR VE5SEL CIRCUM. , 14 HYD E2 - - - -

DIA < 6 IN 1 HYD E2 - - -

SUPPORT I HYS E2 - - - -

Y 0

4 s

-- ~~ - --- -- - . . . - . . . . . . _ , . _ . _ _ , _ _ ._

JAMES A. F1TZPATRICK Page 30 of 35 NOTES t

i Sys, tem: Control Rod Drive Return

1. Nine circtmferential welds and two support welds in between contalhment isolation valves CRD-110 and CRD-114 will have augmented ' inspection by surface examination. One circumferential weld is located inside Penetration X-36 and is inaccessible for surface examination. A

?

a i

I

[

1 1

- .. - _ _ ~ .. - . - . _ .. .. - .__ _ -. _

Pues 31 et 35 INSERVICE INSPECTION PROGRAM g Synom MAIN STEAM Prepend By M. J. PARTRIDGE 10-29-78 om y ISD No. II825-FM-29A Rev. 13 WELD

SUMMARY

SHEET Approved By H. H. ASIQilTH CHIEF ENGINEER 12-4-78 James A. FitzPetrick Nuclear Pouver Plant o.

Required eq f r RM System ISD No.of Code Code No. of In Lieu of IJae Number Line Demeription Class Coordinate Weld Type Welds Exam Exemption Welds Reason Examination Notes 6"-hP-902-5 FROM LINE 24"-SHP-902-IC I D-3 CIRCUM 2 VCL - - - -

TO VALVE 29-RV-7tG 6"-SHP-902-55 FROM LINE 24"-SHP-902-IC I D-3 CIRCUM 2 VOL - - - -

TO VALVE 29-RV-7IE 6"-SHP-902-ST FROM LINE 24"-SHP-902-IC I D-3 CIRCUM 2 VOL - - - -

TO VALVE 29-RV-71F 24"-SHP-902-ID FROM REACTOR VESSEL TO MAIN I E-4 CIRCUM 19 VOL 1 R3 HYD 2 STEAM ISOLATION VALVE 29-A0V-860 BRANCH 10 SUR - - - -

SUPPORT 10 V0L 10 R5 SUR -

?.

i 6"-SHP-902-5Q FROM LINE 24"-SHP-902-ID 1 E-3 CIRCUM 2 VOL - - - -

TO VALVE 29-RV-71H 6"-SHP-902- 5R FROM LINE 24"-SHP-902-ID 1 E-4 CIRCUM 2 V0L - - - -

TO VALVE 29-RV-7tJ 6"-SHP-902-5W FROM LINE 24"-SHP-902-ID 1 E-4 CIRCUM 2 VOL - - - -

TO VALVE 29-RV-71L l

..- - . . . _ ... _. - - . .- . . - __ . . - ~-. - - - - -

Pues 32 of 35 MAIN STEAM INSERVICE INSPECTION PROGRAM n sygegen Prepared By M. J. PARTRIDGE 10-29-78 y ISD No. Il825-FM-29A WELD

SUMMARY

SHEET om Ree. 33 Approved By H. H. A510f1TH, CHIEF ENGINEER 12-4-78 James A. FitrPetrick Nuclear Posser Plant om Required I' System ISD No. of Code Code No. of In Lieu of line Number Line Description Class Coordinate Weld Type Welds Exam Exemption Welds Reason Examination Notes 24"DNP-902-IA FROM REACTOR VESSEL TO MAIN 1 F-3 CIRCUM 20 V0L 1 R3 HYD I STEAM ISOLATICN VALVE 29-A0V-86A BRANCH ll SUR - - - -

SUPPORT 10 V0L 10 R5 SUR -

6"-SHP-902-5N FROM LINE 24"-SHP-902-1A I G-3 CIRCUM 2 VOL - - - -

TO VALVE 29-RV-718 .

4?

6"-SHP-902-5P FROM LINE 24"-SHP-902-1A 1 F-3 CIRCUM 2 V0L - - - -

TO VALVE 29-RV-7IA 6"-SHP-902-5X FROM LINE 24"-SPP-902-IA 1 F-3 CIRCUM 2 VOL - - - -

TO VALVE 29-RV-71K Y

C 24"-SHP-902-1B FRCM REACTOR VESSEL TO MAIN STEAM 1 F-4 CIRCUM 25 VOL I R3 HYD 1 ISOLATION VALVE 29-A0v-868 BRANCH 9 SUR - - - -

SUPPORT ll VOL 11 R5 SUR -

6"-SHP-902-5U FRCH LINE 24"-SHP-902-IB TO I F-4 CIRCUM 2 VOL - - - -

. VALVE 29-RV-71C 6"-SHP-902-SV FRCM LINE 24"-SHP-902-1B TO I F-4 CIRCUM 2 VOL - - - -

VALVE 29-RV-710 24"-SHP-902-IC FROM REACTOR VESSEL TO MAIN STEAM 1 E-3 CIRCUM 25 VOL 1 R3 HYD 2 ISCLATION VALVE 29-A0V-86C BRANCH 9 SUR - - - -

SUPPORT 11 VOL 11 R5 SUR -

.. .-- - . , , .- .... . - . - .. .- - - --- -~

JAMES A. FITZPATRICK. Page 33 or 35 NOTES System: Main' Steam e

1. One -circumferential weld is located inside each of containment Penetrations X-7A and X-7B and is inaccessible for volumetric or surface examination.

2. One circumferential weld is located inside each of containment Penetrations X-7C and X-7D and is inaccessible for volumetric or surface examination.

m e

8 8 s 7 ,.

- m7- m t e 1 - - 2 - - - - I - - - - - -

5 o4 o 5 -

3 1 2

- N 1 1 f

o f n R oito E

E u

ea n D R R R D R R R 4 N f i i Y - U - - U - U Y - U - U - U 3 I e Lma H S S $ H S S S i

e G l g N e nx a E R I E

P r F o E f n I

o 3 5 5 5 3 5 5 5 H t s s R - R - - R - R R - R - R - R E

C e ae G u q R D H, e I

T R R I f T

R V osd R .l

- - - 3 -

A S oe 1 - 3 - 1 5 1 I - 5 P

J A

H NW M. H n

. et io y d p B

y B Ceom d x d ev E e

r a r o

p p

. e p P

r A gem L R L L L L L L L R L L L L L d a O O O ox 0 U O O O 0 0 O V V O U V S V O O V V V V CE V S V V V V t f

. n o s a d M l 9 3 3 2 8 1 2 5 6 3 3 8 I 2 5 P o. el A 1 1 1 1 R r e NW G T s O E ou L .

_ R E P e N A "

P H p T N T T T T T N

S ae r y M H I

R I

D M R MR M H' O R M R M R lc T U C6 O U U O U O U C U O U O O YR u d C N R A P

P T C P R P C P R P C N R A P

P C P R P C P R P I

T A N l e I R< U I

G I U I C S U I C

R U S

I U I C S U

C W C 8A S N C S B"' C S E

P M M k I D O icr L S

N US a t I

Pr e E

C LD i F t

t a

n I E Di 5 4 4 4 4 4

. V W .A Sr d - - - - - -

. R I o C A A C 8 8 E o S

s e C N m I

a J

ms tes a I I 1 I 1 I sl yC S

. A

_ IS

. e O S O O e S O E T T E T T R N 8 A N C D I A 4 A 4 I 8 4 8 4 L 4 - 4 - L 4 - 4 -

. R n - N - N - N - N

. E o O A A O A A

. T A i T 2 E 2 E T 2 E 2 E A 4 t

p 0 L 0 L 0 L 0 L W 3 i A D 9 Z 9 Z 8 D 9 Z 9 Z D - r l N - Z - Z 1 N - Z - Z E M c A P 0 P 0 l A P 0 P 0 s l N F N WN WN F I E F e I F - D - A C W- L

- 8 D V 5 5 - L W- L 5 V 5 L -

2 e R E E R - - E E 8 n N A2 A2 B" S 8" S N A A 8" S 8" S S 1 S 2 2 1 S 1 S iL I

l I E 0 0 E E E 0 0 E E V 9 9 E V E V V 9 9 E V E V L - N N L - - N N _

A P p I R I R A P P I R I R

o. O V O L O n

e N le V F r W y H - ,

L M

T L O 4 0 T

1 WF- -

W L H C T

H C T

s D O n O A 0 A O O A O A _

y S R "2 2 R E R E R "2 "2 R E R E _

S I F 1 3 F R F R F 1 1 F R F R _

A A C 8 8 0 r 4 5 S 4 5 5 e - - - - - -

A A A A n b A A 2 2 2 2 2 2 m 0 0 0 0 0 . 0 u 9 9 9 9 9 9 N - - - - - -

y i L

e n , W-P F

8" P

W-

"2 P

W-

"2 P

W-8" 1

P W-2 1

P W-

"2 1

1 1 1 s

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_ __ _ ~_= . _ _ . _ _ ._

~ - -

--~

^

" ~ ~~ . _ . . _ . _ , ' '

el" w + W g - ,

JAMES A. FITZPATRICK page 35 of 35 NOTES l

System: Feedwater

1. One circumferential weld is located Inside each of containment Penetration X-9A and X-9B and' is -

inaccessible for volumetric or surface examinations. 'e.

2. Fabrication welds on thermal sleeve.

I b

w 1

4 I

I t

L h

s e

1 i

I i

l' 4 s APPENDIX C

}.

INSERVICE INSPECTION DIAGRAMS f

i

! One set of Inservice inspection Diagrams color-coded to show the ASME Class 1, Class 2,-and Class 3 boundaries is included i in one copy of this report being submitted to the Nuclear Regulatory Comission.

I i

f i

, I e

p i

1.

. _ . . _ . . _ . . _ _ _ __ , .

ML20136B967

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ML20136B967

Text

1.0 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

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Reference:

Reference:

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