ML20154Q751

Rev 0 to ASME Section XI Preservice Insp Plan

ML20154Q751
Person / Time
Site:	Comanche Peak
Issue date:	02/24/1988
From:	Skaggs M TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
Shared Package
ML20154Q737	List: ML20154Q733 ML20154Q751
References
PROC-880224, NUDOCS 8806070109
Download: ML20154Q751 (71)

Text

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T COMANCHE P.EAK STEAM ELECTRI6~ STATION UNIT l00;.

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/~V ASME SE'CTION XI s.

PRESERVICE IifSPECTION PLAN 1.

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2[44fgg PREPARED BY: #-

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E Section XI CoordinatoT U

.i REVIEWED BY:

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in'ee r - Manager REVIEWED BY: If4 A)

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REVIEWED BY:

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APPROVED BY:

' Dill CR,'CPE V /

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-COMANCHE PEAK STEAM ELECTRIC STATION UNIT NO. 2 ASME SECTION XI' PRESERVICE INSPECTION PIAN TABLE OF CONTENTS REVISION 0 Section Content Page Number A

Introduction 1-5 B

Class 1 and 2 (IWB, IWC) 6 - 20 C

Class 3 (IWD)

?,1 9

' Class 1, 2 and 3 Component Supports (IWF) 22, 23 E

Examination Boundary Diagrams 24 (plus diagrams)

F Requests for Relief 25, 26 O

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7 3

INTRODUCTION (J

Ceneral Plant Description The Comanche Peak Steam Electric Station (CPSES) is a dual unit plant having Westinghouse pressurized water reactors each with an electrical output of 1150 MWe.

CPSES is located in North Texas in Somervell County, approximately forty-five miles southwest of Fort Worth.

Purpose The purpose of this Plan is to provide details pertaining to performance of the preservice inspection (PSI) at CPSES, Unit 2, and to fulfill the requirements of 10CFR50.55a.

Scope This Plan addresses the examinations to be performed on ASME Class 1, 2, and 3 systems and components as stipulated in the 1983 Edition of ASME Section XI (Code) (see Note).

Note:

Certain areas within the Unit 2 PSI boundary were examined prior to the adoption of the 1983 Code as the Edition to be utilized. These

-~g areas include the Reactor Vessel and 37 ASME Class 1 piping welds in

)

the reactor coolant and safety injection systems.

These areas were examined in accordance with the 1980 Code.

A review of the two Code Editions reveals that siinilarities exist r,uch that baseline documentation gathered under the 1980 Edition is acceptable under the rules provided in the 1983 Edition.

ASME Class 2 piping welds shall be selected in accordance with Code Case N 408.

The testing of pumps and valves as stipulated in subsections IWP and IWV of the code is not within the scope of this Plan.

Preservice Inspection Preservice inspection data shall constitute baseline documentation for inservice inspections and will be performed during the construction and startup phases o[

CPSES.

Examinations shall be performed in accordance with approved procedures.

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e Records Retention Documentation necessary to support the Unit 2 PSI shall be maintained as permanent 4,lant records at CPSES. This documentation shall include, as a minimum, the applicable records described in Subsubarticle IWA-6340 of Section XI.

Nondestructive Examination

- ASME Class 1 and 2 components and their supports shall be categorized in occordance with Tables IWB 2500 1, IWC-2500-1 and IWF-2500-1 and Code Case A-408.

Utilizing the nondestructive examination methods presc-ibed-in the appropriate Code table, non-exempt components and their supports shall be examined in accordance with the techniques and requirements of Article 200r

• the Code.

Exemptions The following comprise those exemptions applicable to CPSES Unit 2.

I.

For Class 1 components:

2 A.

piping of 1 inch nominal pipe size and smaller, e.xcept for steam generator tubing, is exempt from examination per IWB-1220 (b)(1);

B.

components and their connections in piping of 1 inch nominal pipe g

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size and smaller, are exempt from examination per IVB-1220(b)(2);

C.

reactor vessel head connections and associated piping, 2 inch nominal pipe size and smaller, made inaccessible by control rod

-drive penetrations are exempt from examination per IWB 1220(c).

II.

For Class 2 components other than piping welds:

A.

components of systems or portions of systems that during normal plant conditions are not required to operne.e but remained flooded i

under static conditions at a pressure of at least 80% of the l

pressure that the component or system will be subjected to when required to operate, are exempt from examination per IWC-1220(1);

B.

components of systems or portions of systems, other than Residual Heat Removal Systems and Emergency Core Cooling Systems, that are not required to operate above a pressure of 275 psig or above a temperature of 2000F, are exempt from examination per IWC 1220(b);

C.

component connections (including nozzles in vessels and pumps) valves, and vessels and their attachments that are 4 inch nominal pipe size and smaller, are exempt froe examinaticn per IWC-1220(c).

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III. For Class 2 -piping welds in the Residual Heat Removal, Emergency Core Cooling and Containment Heat Removal systems:

A.

piping 4 inch nominal pipe size and smaller in all systems, except the high pressure safety injection system, is exempt from examination per N 408 (a)(1):

B.

piping 1-1/2 inch nominal pipe size'and smaller in the high pressure safety injection system is-exempt per N-408 (a)(2);

C.

component connections 4 inch nominal pipe size and smaller (including nozzles, socket fittings, and other connections) in vessels, piping, pumps, valves, and other components of any size in all systems except the high pressure safety injection system are exempt per N-408 (a)(3);

D.

component connecti.ons 1 1/2 inch nominal pipe size and smaller (including nozzles, socket fittings, and other connections) in vessels, piping, pumps, valves, and other components of any size

'in the-high pressure safety injection system, are exempt per N 408 (a)(4);

E.

piping and component connections of any size in statically pressurized, passive safety injection systems (i.e., accumulator.

discharge), are exempt per N-408 (n)(4);

F.

piping of any size beyond the last shutoff valve in open ended

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portions of systems that do not contain water during normal plant.

operating conditions, is exempt per N 408 (a)(6).

i IV.

For Class 2 -piping welds in systems other than Residual llent Removal, Emergency Core Cooling and Containment Heat Removal:

A.

piping and component connections 4 inch nominal pipe size and smaller, are exempt per N-408 (b)(1)'and (2);

B.

piping and camponent connections in systems or portions of l

s ntems that operate (when the system function is required) at a pressure equal to or less than 275 psig and at a temperature equal to or less than 2000F, are exempt per N 408 (b)(3);

C.

piping of any size beyond the last shutoff valve in open ended portiona of systems that do not contain water during normal plant operating conditions, is exempt per N-408 (b)(4).

i Relief Requests Where a particular examination requirement of the Code is determined to be l

impractical, a request for relief from the requirement shall be uuLnitted pursuant to the requirement of 10 CFR 50.55a(a)(3).

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Each request for relief shall contain the following information,' at a minimum:

A.

. Identification of the component (s) for which relief is requested;

.s B.

.Codo class of the component (s);

C.

Code examination requirement for the component (s);

D.

Basis for the request; E.'

Proposed alternative examinations, if any; and, F.

Anticipated impact on the overall level of plant quality and safety.

Requests for relief from impractical Code requirements that are presently known -

are contained within this Plan.

For those impractical Code requirements that may become apparent in the course of the PSI, a request for relief shall be prepared and submitted for each case.

Exar ination Boundaries In accordance with IWA-1400(a) of the Code, TU Electric has identified Code classification and boundaries of systems subject to examination. Tnese examination boundaries are provided in Section E of this Plan.

i To further enhance specific examination areas, isometric drawings are developed i

f to identify examination areas.

' Reactor Pressure Vessel Required volumes of the Reactor Pressure Vessel have been examined in accordance with the examination techniques of ASME Section V Article 4 and supplemented by additional requirements to address the intent of USNRC Regulatory Guide 1.150.

The program for examination of the Reactor Vessel was submitted in a letter to the NRC issued June 13, 1983 and is addressed in the CPSES SSER 4.

For continuity, the examination requirements of the Reactor Vessel are restated in this Plan.

' Code Case N-408 Tc provide baseline examination that is consistent to the maximum extent permissible, with the latest published Code Edition, TU Electric has elected to

~

adopt Code Case N-408 for determining components subject to examination and for establishing examination requirements for Class 2 piping.

Class 2 piping welds shall be selected for examination utilizing the exemption criteria and Tables 1 and 2 of N 408.

The examination method and extent of examination shall be determined from Tables 1 and 2 of N 408.

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All examinations which would be applied to components within the piping boundary

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I as determined by IWC-1220 and Category C-F of the 1983 Code shall be applied to the piping selected in accordance with N-408 (e.g.,

integral attachments, bolting, valves, supports).

It is the intent that two times the minimum number of Class 2 piping welds required to be examined by Code Case N 408 be examined.

This is to provide a buffer beyond the required number of Class 2 piping welds to be examined, should inservice conditions dictate selection of Class 2 piping welds outside the required baseline scope. Approximately 15% of all non-exempt Class 2 piping welds are to be examined and in no case shall fewer than the minimum 7.5% be examined.

Note:

For the purpose of this Code Case, the high pressure safety injection system is defined as the discharge piping from each safety injection pump and each centrifugal charging pump. This piping i.a illustrated in Section E, as the Class 2 piping, 4 inch nominal pipe size and smaller, shown en the Safety Injection and Chemical and Volume Control Inservice Inspection Boundary Diagrams.

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CPSES UNIT 2 ASME CIASS 1 AND 2 PRESERVICE INSPECTION All items listed below are to be examined, as indicated, in accordance with the requirements of Subsections IWB and IWC of the 1983 Edition of Sec. lon XI of the ASME Boiler and Pressure Vessel Code except for Class 2 piping which is selected for examination and the examination methods determined in accordance with Code Case N 408.

IWB-2500 1 Area To Be Examination Percent To Item Number Examined Method

,Be Examined REACTOR VESSEL Bl.10 Shell Welds B1.11 Circumferential Vol.

100 Bl.12 Longitudinal Vol.

100 Bl.20 Head Welds Bl.21 Circumferential Vol.

100 Bl.22 Meridional Vol.

100 Bl.30 Shell to Flange Vol.

100 Weld

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B1.40 Head-to-Flange Vol. & Surf.

100 g.ld ss Bl.50 Repair Welds Bl.51 Beltline Region Vol.

Note (2)

PRESSURIZER B2.10 Shell to Head Welds B2.11 Circumferential Vol.

100 B2.12 Longitudinal Vol.

Note (1)

B2.20 Head Welds B2.21 Ci rcum fe rent ial Vol.

Note (2)

B2.22 Meridional Vol.

Note (2)

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Examination Percent To IWB-2500 Area To Be Item Number

' Examined Methed Be Examined STEAM GENER/. TOR (Primary Side)

B2.30 Head Welds

-B2.31 Circumferential Vo.'.

Note (2)

-B2.32 Meridional Vol.

Note (2) 82.40 Tubesheet-to Head Vol.

100~

Weld HEAT EXCHANGERS (Primary Side) Head B2.50 Head' Welds B2.51 Circumferential Vol.

Note (2)

B2.52 Meridional-Vol.

Note (2)

HEAT EXCHANGERS (Primary Side) Shell I(

L2.60 Tubesheet-to Head Vol.

Note (2)

Welds 82.70 Longitudinal Weldt, Vol.

Note (2)

B2.80 Tubesheet-to-Shell Vol.

Note (2)

Welds RFACTOR VESSEL B3.10 Nozzle-to-Vessel Vol.

Note (3)

Welds B3.20 Nozzle Inside Vol.

Note (3)

Radius Section PRESSURIZER 33.30 Nozzle to-Vessel

<al.

Note (3)

Welds 83.40 Nozzle Inside Vol.

Note (3)

Radius Section

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IWB-2500-1 Area To Be Examination Percent To Item Number Examined Method Be Examined STEAM GENERATORS (Primary Side)

B3.50 Nozzle to Vessel Vol.

Note'(3)

Welds 83.60 No.czle Inside Vol.

Note (3)

Radius Section HEAT EXCHANGERS (Primary Side)

B3.70 Nozzle to-Vessel-Vol.

_ Note (3)

Welds B3.80 Nozzle Inside Vol.

Note (3)

- Radius Section REACTOR' VESSEL B3.90 Nozzle to-Vessel Vol.

100

' Welds O

100 B3.100

- Nozzle Inside Vol.

Radius Section PRESSURIZER B3.110 Nozzle-to-Vessel Vol.

100 Welds B3.120 Nozzle Inside Vol.

100 l

Radius Section STEAM GENERATORS (Primary Side) j B3.130 Nozzle to Vessel Vol.

100 1

Welds B3.140 Nozzle Inside Vol.

100 Radius Section HEAT EXCHANGERS (Primary Side) e B3.150 Nozzle to-Vessel Vol.

Note (2)

Welds B3.160 Nozzle Inside Vol.

Note (2)

Radius Section 8-i

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IWB-2500-1 Area To Be Examination Percent To Item Number Examined Method Be Examined REACTOR VESSEL B5.10 Nominal Pipe Size Vol. & Surf.

100' 2 4 in.

Nozzle to Safe End Butt Welds B5.20 Nominal Pipe. Size Surf.

Note (2)

< 4 in.

Nozzle-to Safe End Butt Welds B5.30 Nozzle to Safe End Surf.

Note (2)

Socket Welds PRESSURIZER B5.40 Nominal Pipe Size Vol. & Surf.

100 2 4 in.

Noz-le to Safe End Bute Welds

>. U B5.50 Nominal Pipe Size Surf.

Note (2)

< 4 in.

Nozzle to Safe End Butt Welds l-B5.60 Nozzle to Safe End Surf.

Note (2)

Socket Welds STEAM CENERATOR B5.70 Nominal Pipe Size Vol. & Surf.

100 l

2 4 in.

Nozzle to Safe End Butt Welds l

B5.80 Nominal Pipe Size Surf.

Note (2) l

< 4 in, i

Nozzle to Safe End Butt Welds B5.90 Nozzle to Safe End Surf.

Note (2)

Socket Welds 9

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IWB-2500-1 Area To Be Examination Percent To Item Number Examined Method Be Examined-i HEAT EXCHANCERS B5.100 Nominal Pipe. Size Vol. & Surf.

Note (2).

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.2 4 in.

o Nozzle to Safe End Bute Welds.

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B5.110 Nominal Pipe Size Surf.

Note (2).

< 4 in.

Nozzle to Safe End 4

Butt Welds B5.120 Nozzle to Safe End Surf.

Note (2)

Socket Welds PIPINC B 5.13

Nominal' Pipe Size Vol. & Surf, 100 2 4 in.

Dissimilar Metal i.-

Butt Welds B5.140 Nominal Pipe Size Surf.

Note (2)

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< 4 in.

Dissimilar Metal Butt Welds i

B5.150 Dissimilar Metal Surf.

Note (2) l Socket Welds l

REACTOR VESSEL 1-l B6.10 Closure Head Nuts Surf.

100 I

B6.20 Closure Studs, Vol.

Note (4)

In Place l~

l B6.30 Closure Studs, Vol & Surf.

100 l

Removed I

B6.40 Threads in Flange Vol.

100 B6.52 Closure Washers, VT-1 Note (5)

Bushings l

r IVB 2200 1 Area To Be Examination Percent To Item Number Examined Method Be Examined PRESSURIZER B6.60 Bolts and Studs Vol.

Note (2)

B6.70 Flange Surface, VT-1 Note (2)

Disassembled B6.80 Nuts, Bushing, VT-1 Note (2) and Washers STEAM CENERATORS B6.90 Bolts and Studs Vol.

Note (2)

B6.100 Flange Surface, VT-1 Note (2)

Disassembled B6.110 Nuts, Bushing, VT 1 Note (2) and Washers

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HEAT EXCilANGERS w,/

B6.120 Bolts and Studs Vol.

Note (2)

B6.130 Flange Surface, VT-1 Note (2)

Disassembled B6.140 Nuts, Bushing, VT-1 Note (2) and Washers PIPING B6.150 Bolts and Studs Vol.

Note (2)

B6.160 Flange Surface, VT-1 Note (2)

Disassembled B6.170 Nuts, Bushing, VT-1 Note (2) and Washers j

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'IVB-2500-1 Area To Be Examination-Percent To 1

Item Number Exsmined Method Be Examined PUMPS B6.180

. Bolts and Studs Vol.

Note (2) 86.IPO Flange Surface, VT-1 Note (2)

Disassembled t

j B6.200-Nuts, Bushing, VT 1 Note (2) and Washers VALVES B6.210 Bolts and Studs Vol.

Note (2)

B6,220 Flange Surface, VT-1 Note (2)

Disassembled B6.230 Nuts, Bushing, VT-1 Note (2) and Washers REACTOR VESSEL p

B7.10 Bolts, Studs, VT-1 Note (2) t and Nuts I

e PRESSURIZER B7.20 Bolts, Studs, VT-1 100 j

and Nuts

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STEAM GENERATORS 6

i B7.30 Bolts, Studs, VT 1 100 and Nuts i

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HEAT EXCHANGERS B7.40 Bolts, Studs, VT 1 Note (2) and Nuts i

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PIPING I

B7 50 Bolts, Studs, VT 1 100 t

and Nuts 12-j 1

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IWB-2500-1 Area To Be Examination Percent To Item Number Examined Method Be Examined PUMPS B7.60 Bolts, Studs, VT-1 100 and Nuts VALVES B7.70 Bolts, Studs, VT-1 100 and Nuts CRD HOUSINGS B7.80 Bolts, Studs, VT-1 100 and Nuts REACTOR VESSEL B8.10 Integrally Welded Vol. or Surf.

Note (2)

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PRESSURIZER B8.20 Integrally Welded Vol. or Surf.

100 Attachments STEAM GENERATOR B8.30 Integrally Welded Vol, or Surf.

Note (2)

Attachments HEAT EXCHANGERS B8.40 Integrally Welded Vol. or Surf.

Note (2)

Attachn.ents N

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4 IWB-2500-1 Area'To Be Examination Percent To Item Number Examined Method Be Examined PIPING 89.10 Nominal Pipe Size Vol & Surf.

> 4 in.

B9.11 Circumferential.

100 Welds B9.12 Longitudinal Welds Note (2)

B9.20 Nominal Pipe Size Vol. & Surf.

< 4 in.

!B9.21 Circumferential 100 Welds B9.22 Longitudinal Welds Note (2)

B9.30 Branch Pipe Connection Welds 89.31 Nominal Pipe Size Vol. & Surf.

100

> 4'in.

l 89.32 Nominal Pipe Size Surf.

-100

< 4 in.

i 4

- U 89.40 Socket Welds Surf.

100 1

3 l

PIPINC l

B10.10 Integrally Welded

.Vol. ot' Surf.

100 Attachments j

PUMPS i

B10.20 Integrally Welded Vol, or Surf.

Note (2)

Attachments P

VALVES B10.30 Integrally Welded Vol. or Surf.

Note (2)

Attachments

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PUMPS B12.10 Pump Casing Welds Vol.

Note (2)

B12.20 Pump Casing VT-3 100 t

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(m IWB 2500-1 Area To Be Examination Percent To Item Number Examined Method Be Examined VALVES B12.30 Valves, Nominal Pipe Size < 4 in.

Valve Body Welds Surf.

Note (2)

B12.40 Valves, Nominal Pipe Size > 4 in.

Valve Body Welds Vol.

Note (2)

B12.50 Valve Body > 4 in.

VT-3 Note (6)

Nominal Pipe Size REACTOR VESSEL B13.10 Vessel Interior VT 3 Note (7)

B13.50 Interior VT-1 Note (8)

Attachments Within Beltline g)

Region LL 813.60 Interior VT-3 Note (8)

Attachments Beyond Beltline Region B13.70 Core Support VT 3 Note (9)

Structure REACTOR VESSEL B14.10 Welds in CRD Vol. or Surf.

Note (10)

Housing Oi V

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IWC-2500 1 Area To Be Examination Percent To Item Number Examined Method Be Examined VESSELS C1.10 Shell Circumferential Welds Vol.

100 C1.20 Head Circumferential Welds Vol.

100 C1.30 Tubesheet-to-Shell Welds Vol.

100 VESSEL N0ZZLE WELDS C2.10 Nozzles in Vessels 5 1/2 in.

Nominal Thickness C2.11 Nozzle-to-Shell Surf.

100 (or Head) Weld C2.20 Nozzle Without Reinforcing Plate in Vessels > 1/2 in.

Nominal Thickness I

}

C2.21 Nozzle to Shell Vol. 6 Surf.

100 C/

(or Head) Weld C2.22 Nozzle Inside Radius Vol.

100 Section C2.30 Nozzles With Reinforcing Plate in Vessels

> 1/2 in. Nominal Thickness C2.31 Reinforcing Plate Surf.

Note (2)

'lelds to Nozzle and Vessel C2.32 Nozzle-to Shell (or Vol.

Note (2)

Head) Welds When Inside of Vessel is Accessible C2.33 Nozzle to Shell (or VT-2 Note (2)

Head) Welds When Inside of Vessel is Inaccessible rx E

i 1

IWC-2500 1 Area To Be Examination Percent To Item Number:

Examined Method Be Examined PRESSURE VESSELS C3.10 Integrally Welded Surf.

100 Attachments PIPINC C3.20 Integrally Welded Surf.

100 Attachment PUMPS C3.30 Integrally Welded Surf.

100 Attachments VALVES C3.40 Integrally Welded Surf.

Note (2)

Attachments PRESSURE VESSELS l,,

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C4.10 Bolts and Studs Vol.

Note (2)

PIPING C4.20 Bolts and Studs Vol.

Note (2)

PUMPS C4.30 Bolts and Studs Vol.

Note /2)

VALVES C4.40 Bolts and Studs Vol.

Note (2)

PI PIN _C C5.10 Piping Welds > 3/8 in.

Wall Thickness for Piping > NPS 4 C5.11 Circumferential Welds Vol. & Surf.

7.5 C5.12 Longitudinal Welds Vol. & Surf.

Note (11)

(Mk.)

17-

gm

)

IWC 2500 1 Area To Be Examination Percent To s'

Item Number Examined Method Be Examined C5.20 Piping Welds > 1/5 in. Nominal Wall Thickness for Piping

> NPS 2 and < NPS 4 (High Pressure Safety Inj ection)

C5.21 Circumferential Welds Vol. & Surf.

7.5 C5.22 Longitudinal Welds Vol. & Surf.

Note (11)

C5.30 Socket Welds surf.

7.5 C5.40 Pipe Branch Connections of Branch Piping > NPS 2 C5.41 Circumferential Welds Surf.

7.5 C5.42 Longitudinal Welds Surf.

Note (11)

C5.50 Piping Welds > 3/8 in.

Nominal Wall Thickness for Piping > NPS 4 C5.51 Circumferential Welds Vol & Surf.

7.5 7-ss

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C5.52 Longitudinal Welds Vol. & Surf.

Note (11)

C5.60 Piping Welds > 1/5 in.

Nominal Wall Thickness for Piping > NPS 2 and < NPS 4 (High Pressure Safety Injection)

C5.61 Circumferential Weld Vol. & Surf.

Note (2)

C5.62 Longitudinal Weld Vol. & Surf.

Note (2)

C5.70 Socket Welds

Surf, 7.5 C5.80 Pipe Branch Connections of Branch Piping > NPS 2 C5.81 Circumferential Welds Surf.

7.5 C5.82 Longitudinal Welds Surf.

Note (11)

PUMPS C6.10 Pumps Casing Welds Surf.

Note (2)

VALVES

\\x-C6.20 Valve Body Welds Surf.

100

(^N, NOTES

,/

(1) 1 foot of all longitudinal velds intersecting the circumferential weld is to be examined.

(2)

There are no items of this type within the PSI boundary (3)

TU Electric has elected to utilize inspection program B and therefore this item does not apply.

(4)

Reactor Vessel studs shall be removed for examination (5) 100 percent of closure washers shall be examined.

There are no bushings in the reactor vessel.

(6)

Examinations are limited to one valve within each group of valves of the same constructional design and manufacturing method and that perform similar system functions.

See Attachment i for a group listing.

(7) 100 percent of accessible areas are examined.

(8) 100 percent of accessible welds are examined.

(9) 100 percent of accessible surfaces are examined.

(n)

(10) 100 percent of peripheral CRD housing welds are examined, v

(11)

The examinacion area includes 2.5 times the thickness from the circumferential weld selected for examination.

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ATTACHMENT 1-Class i Valve Bodies > 4 in. NPS Croup 1 - Forged Pressurizer Relief Valves 2 8010A 2-8010B 2 8010C Group 2 - Forged Cate Valves Isolating the RC System from the RilR System 2-8701A 2-87018 2 8702A 2-8702B Croup 3 - Forged Check Valves Isolating the RC System from the SI System 2 8948A 2 8948B 2 8948C l

2 8948D fs

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4 2 8956A

'N l 2-8956B 2 8956C

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2-8956D 2 8818A 2-8818B 2 8818C 2 8818D 2-8949A 2 8949B 2-8949C 2 8949D 2-8841A 2-8841B l

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9 CPSES UNIT 2 ASME CIASS 3 FRESERVICE INSPECTION Relief has been requested from the requirements for preservice inspection of Class 3 systems and components. This relief request, titled D-1, may be found in the relief request section of this Plan (Se; tion F).

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CPSES UNIT 2

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ASME CLASS 1, 2 AND 3 COMPONENT SUPPORT PRESERVICE INSPECTION All ASME Class 1, 2 and 3 component supports within the boundaries of inspection identified in Section E which are required to be constructed in accordance with NF shall be examined, as indicated, in accordance with Subsection IWF of the 1983 Edition of Section XI of the ASME Boiler and Pressure Vessel Code.

IWF-2500-1 Examination Item Number Area To Be Examined Method PLATE AND SHELL TYPE SUPPORTS F1.10 Mechanical connections to VT-3 pressure retaining components and building structure F1.20 Weld co.inections to building VT-3 structure

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F1.30 Weld and mechanical VT 3 connections at intermediate joints in multiconnected integral and nonintegral supports F1.40 Component displacement VT 3 settings of guides and stops, misalignment of supports, assembly of support items LINEAR TYPE SUPPORTS F2.10 Mechanical connections to VT 3 pressure retaining components and building structure e

N.

1 IWF 2500 1 Examination

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Item Number Area To Be Examined Method F2.20 Weld connections to building VT 3 structure F2.30 Weld and mechanical VT-3 connections at intermediate joints in multiconnected integral and nonintegral supports F2.40 Component displacement VT-3 settings of guides and stops, misalignment of supports, assembly of support items COMPONENT STANDARD SUPPORTS F3.10 Mechanical connections to VT-3 pressure retaining components and building structure

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F3.20 Weld connections to building VT-3 N-structure F3.30 Weld and mechanical VT-3 connections at intermediate joints in multiconnected integral and nonintegral supports F3.40 Component displacement VT 3 settings of guides and stops, misalignment of supports, assembly of support items F3.50 Spring type supports, VT-4 constant load type supports, shock absorbers, hydraulic and mechanical type snubbers s_ -

23-

3-EXAMINATION BOUNDARY DIACRAMS

' This section contains diagrams depicting the bounds within which the examination requirements of ASME Section XI, and Code Case N 408 for Class-2 piping welds, are applied. These are those Class 1, 2 and 3 systems and components which are not exempt (exemption criteria is provided in Section A).

Examination Boundary Diagrams Auxiliary Feedwater. (f.h.1, 2, 3)

Chemical & Volume Control Component Cooling Water (Sh. 1, 2, 3)

Containment Spray Diesel Cenerator Feedwater i

Main Steam Reactor Coolanc (Sh. 1 & 2)

Residual Heat Removal Safety Injection (Sh.1 6)

Station Service Water (Sh.1 & 2)

LECEND

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A solid line indicates that the rules of the Code or N-408 are applied to select examination areas.

I A phantom line indicates Class 2 piping which is > 4 in. NPS and < 3/8 in, nominal wall thickness. This piping is not subject to examination but is included in the total weld count to which the sampling' rate is applied.

A dashed line indicates piping not in the system for which the diagram applies or exempt piping and is shown for clarity only, i

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REQUESTS FOR RELIEF i

4 In this section are requests for relief from impractical =ASME Section XI requirements.

It is determined that performance of these examinations would result in hardship or unusual difficulties without a compensating increase in-the level of quality and safety. Thus, relief is requested from the Code requirements as described in this section.

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RELIEF REQUEST-D-l

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Item for which relief is' requested:

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Integral Attachments, j

B, Item Code Class:

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3.

C.

Examination requirement from which relief is requested:

l The VT-3 examinations of Table IWD-2500-1.

i D.

Basis for Relief Request:

Visual examinations conducted during construction ensure that conditions qualifying as unacceptable under a VT-3 examination do not exist, i

Personnel performing these examinations are trained and certified under a program which meets the requirements of ANSI N45.2.6 as endorsed and t

supplemented by Regulatory Cuide 1.58, Revision 1.

These exaininnt iorm a re l

documented and the records maintained as permanent plant records.

P Additionally. Table IWD 2500-1 allows for the examination of only one of the multiple components within a system of similar design, function and service whereas the visual examinations conducted during construction are conducted on all Class 3 integral attachments.

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i E.

Alternative examinations:

None.

F.

Anticipated impact on* the overall level of plant quality and safety:

l None.

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