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Forwards,For NRC Evaluation,Three Revised & Five Alternative Requirements Associated W/Preservice Insp Plan & Relief Requests Re Piping Sys,Reactor Vessel & Steam Generator 3
	ML20245B487
Person / Time
Site:	Comanche Peak
Issue date:	04/17/1989
From:	William Cahill; TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	TXX-89180, NUDOCS 8904260129
	Download: ML20245B487 (21)
	v • d • e

_

ME Log # TXX-89180 C

Fi1e #-10010 r

C 905.4.

TUELECTRIC Ref. # 10CFR50 55a(g)

April 17, 1989 W. J. Cahill Execuris VicePresident U..S. Nuclear Regulatory Commission Attn:. Document Control Desk

' Washington, D. C.

20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET N0. 50-445 UNIT-1, PRESERVICE INSPECTION

Gentlemen:

In.accordance with the requirements of'10CFR50.55a(g)

TV Electric is submitting for NRC evaluation three (3) revised and five (5) alternative requirements associated with the Unit 1, Preservice Inspection.(PSI) Plan.

These alternatives reflect the current state of the PSI program.

Revised' Alternatives New Alternatives B-10 Revision 1 B-13 C-4 Revision 1 B-17 C-6 Revision 1 C-7 C-8 C-9 Copies have also been-sent to the NRC Region IV office, CPSES NRC Resident inspector, Texas Department of Labor and Standards, and Hartford Steam Boiler for inclusion into their copy of the Unit 1 PSI Plan.

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s

8904260129 8PO417 9

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PDR ADOCK 05000445 Q

PDC 400 North Olive Street LB 81 Dallas, Texas 75201

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1 TXX-89180 April 17, 1989 i

l Page 2 of 2 Should any questions arise regarding this correspondence, please contact Mike Skaggs, CPSES ASME Section XI coordinator, at (817) 897-6063.

l Sincerely, j

t l

J William J. Cahill, Jr.

i DAR/ddm

Enclosure:

Relief Requests j

c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (1)

Texas Department of Labor and Standards Boiler Division E. O. Thompson State Office Building P. O. Box 12157, Capitol Station Austin, Texas 78701 Attn: George Bynog l

Hartford Steam Boiler 11104 West Airport Blvd., Suite 200 Stafford, Texas 77477 Attn:

Tom Barbara

6-L';' 3 Rev. 1 1 81 l

i 1.

RELIEF REQUEST B-10 CODE CLASS: 1-Component: Piping Systems Examination Requirement:

Table IWB-2500-1 Category B-J requires volumetric examination of branch pipe connection welds greater than 2 inches in diameter.and pipe circumferential welds 4 inches in diameter or greater.

l Basis for Relief:

The configuration of the pipe branch connections prevents meaningful volumetric examination of the entire weld and heat affected zone for welds listed in Table B-10.. Practical alternative techniques to volumetrically examining the entire areas of these welds which would produce meaningful results are not presently available.

Alternative Examination:

A volumetric examination will be performed on butt welded branch connections only.

A. surface examination will be performed as required.

Also see Table B-10.

Safety Impact:

There is no anticipated impact on overall plant quality and safety resulting from this relief request.

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RELIEF REQUEST B-16 Component:

Reactor Vessel CODE CLASS: 1 Examination Requirement:

Table IWB-2500-1, Category B A, Item No. Bl.21 requires volumetric examination of the reactor vessel circumferen*.ial bead welds.

Basis for Relief:

Interference from the reactor vessel head flange and lifting lugs allows only 62% examination of the closure head to flange weld.

Interference from the control rod drives and lifting lugs allows only 93% examination of the closure head dome weld.

Interference from the weld crown configuration and head curvature allows only 75% examination of the bottom head dome weld.

None of these welds are able to be examined using remote internal techniques.

These welds were however examined during fabrication using radiography and surface examination. Additionally, the closure head to flange weld was subjected to a surface examination (magnetic particle) as required by Secti>on XI.

Alternative Examination:

None Safety Input:

There is no anticipated impact upon overall plant quality and safety resulting from this relief request.

1

)

f J

L_____________

j

y ;- - ---------_--_ __ __-.__

i L ;

i.

RELIEF REQUEST B-17 Component: Reactor Vessel CODE CLASS: 1 Examination Requirement:

~ Table IWC-2500 1, Category B-0, Item B3.100 requires volumetric examination of Reactor Vessel nozzle inside radius sections.

l

' Basis for Relief:

Interference from the nozzle radius configuration and the clad surface allows t

only 914 examination of each of the eight nozzle inside radius sections.

These examinations were conducted from the internal surface using manual techniques.

Alternative Examination:

None Safety impact:

There is no anticipated impact upon overall plant quality and safety resulting

-from this request.

4

_ _ - - - = _ - _ _ _ _ _

=

Rev. 1 1

RELIEF REQUEST C-4 1

1 Component: Steam Generator #3 CODE CLASS: 2 32" Main Steam Nozzle Inside Radius Section 18" Feedwater Nozzle Inside Radius Section Containment Spray Heat Exchanger #2 16" Inlet Nczzle Inside Radius Section Examination Requirement 1 Table IWC-2500-1, Category C-B requires volumetric examination of the nozzle inside radius section on nozzles >12 in. NPS (Ref. Fig. IWC-2500-4).

Basis for Relief:

The configuration of the nozzle to vessel at the inner radius section prevents meaningful volumetric examination. ' Practical alternative techniques to volumetrically examining these areas are not presently available.

Alternative Examination:

A visual examination of the inside radius section will be performed only if the steam generators are opened for other types'of examinations or for maintenance purposes, otherwise none.

Safety Impact:

There is no anticipated impact upon overall plant quality and safety resulting from this relief request.

l l

4 l

L____________

l

n' a

Rev. 1

(

s W

RELIEF REQUEST C 6 Component: Vessels CODE CLASS: 2 Examination Requirement:

Table IWC 2500-1 Category C-A requires 1006 volumetric examination of the pressure retaining, vessel welds.

Basis for Relief:

Ceometric restrictions prevent meaningful examination of 100% of the required inspection volume for welds listed in Table C 6.

Alternate Examinations:

See Table C-6.

Safety Impact:

There is no anticipated impact upon overall plant quality and safety resulting from this' relief request.

4

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RELIEF REQUEST C-7 Component:

Integral Attachment CODE CLASS: 2 Examination Requirements:

l Table IWC-2500-1, Category C-C, Item No. C3.40 requires surface examination of integral attachments to piping.

,P asis for Relief:

The (8) welded lugs (see attached drawing) were liquid,)enetrant examined to the maximum extent possible without removing an adjacent weided clamp.

The clamp prohibits examination of the 1/2" examination zone on o.ne side of each of the lugs. These lugs were 100% liquid penetrant examined during the construction phase prior to installation of the clamp.

Alternative Examination:

None Safety Impact:

There is no anticipated impact on overall plant quality and safety resulting from this relief request.

4

(.

RELIEF REQUEST C-8 Component:

Steam Cenerator #3 CODE CLASS: 2 Examination Requirement:

Table IWC-2500-1, Category C-B, Item No. C2.21 requires volumetric and surface examination of' nozzle to vessel welds in vessels greater than 1/2" thick.

Basis for Relief:

[

Ceometric restrictions preclude 100% examination-of the steam generator nozzles. The required surface examination was performed'on each nozzle.

Additionally, these welds were subjected to radiographic and magnetic particle examination during fabrication.

See Table C-8 for additional information.

Alternate Examination:

None Safety Impact:

There is no anticipated impact upon'overall plant quality and safety resulting from this relief request.

i 1

i i

l 4

-1__________-

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T ll il l

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4 I

RELIEF REQUEST C 9 Component:

32" Main Steam CODE CLASS: 2 Examination Requirements:

l' Table IWC-2500-1, Category C-F, Item No. C5.22 requires the surface and volumetric examination of 2.5T of all longitudinal welds at the point where they intersect a circumferential weld selected for examination.

Basis for Relief:

The (4) 32" Main Steam nozzle-to-pipe circumferential welds have bee selected for examination.

Adjacent to each circumferential weld is a 3" long pipe

]

section.

These pipe sections contain longitudinal seams.

The location of these

)

seams has been inhibited by a weld overlay of each pipe section.

Efforts to j

positively identify the location of these seams, via acid etching the surface, j

reviewing vendor radiographs and the review of other vendor documentation, were not successful.

The longitudinal seams of each of these pipe sections have been subjected to radiographic examination and hydrostatic testing during fabrication and construction.

Alternative Examination:

None Safety Impact There is no anticipated impact upon overall plant quality and safety resulting from this relief request.

.

ML20245B487

Text

SUBJECT:

Enclosure:

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