ML20196B138

Forwards Rev 0 to ISI-P-014, Inservice Insp Program, for Review.Attachment a Lists Differences Between Rev 0 of Unit 2 Program & Rev 2 of Unit 1 Program

ML20196B138
Person / Time
Site:	Vogtle
Issue date:	11/30/1988
From:	Bailey J GEORGIA POWER CO., SOUTHERN COMPANY SERVICES, INC.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20196B143	List: ML20196B138 ML20196B155
References
GN-1514, NUDOCS 8812060202
Download: ML20196B138 (2)

Text

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~

I Georgia Fbwer Comptry F%t Off<e Oc.e 282

. Wynestcro, Geo'Ota 30830 g,.

.te:ephone 404 554 9961 404 724 8114 Southern Ccmcany Serv.ces, Inc Post Off<e Box 2625 te'e"?M%* P' '

Vogtle Project November 30, 1988 i

United States Nuclear Regulatory Commission l

ATTN: Document Control Desk File:

X7BC35 Washington, D. C.

20555 Log:

GN-1614 PLANT V0GTLE - UNIT 2 NRC DOCKET NUMBER 50-425 CONSTRUCTION PERMIT NUMBER CPPR-109 INSERVICE INSPECTION PROGRAM, REV. 0 Gentlemen:

Enclosed for your review are ten (10) copies of the Inservice Inspection Program for Vogtle Electric Generating Plant, Unit 2 ISI-P-014 Revision O.

This program contains eli known and anticipated relief requests.

The relief requests on Unit 2 are consistent with those requested for Unit 1.

i Attachment A lists the differences between Revision 0 of the Unit 2 Program and Revision 2 of the Unit 1 Program.

If any additional information is required, please do not hesitate to contact me.

Sincerely:

k.

t J. A. Bailey Project Licensing Manager l

JAB /wk1 Enclosure j

xc: NRC Regional Administrator NRC Resident Inspector

(

P. D. Rice, w/o enclosure t

J. P. Kane l

R. A. Thomas, w/o enclosure r

B. W. Churchill Esquire, w/o enclosure t

J. E. Joiner. Esquire, w/o enclosure J. B. Hopkins (2)

G. Bockhold, Jr.

/ 0A{

l R. J. Goddard Esquire, w/o enclosure L

k, go l

R. W. McManus I

Yogtle Project File t

8812060202 681130 1

PDR ADOCK 0500042

O PDC t

ATTACHENT A The following differences exist between the VEGP-1 and VEGP-2 Inservice Inspection Program Relief Requests.

GENERAL. DIFFERENCES 1)

In some cases the number of welds requiring relief vary due to configuration, the actual welds selected per ASME Section XI, etc.

2)

In some cases the examination coverage (%) will be different due to component orientation and/or limitation.

3) Editorial-tyre differences are throughout and are not being addressed incividually.

SPECIFIC DIFFERENCES

1) RR-1 The reactor pressure vessel mechanized examinations, RR-3 referenced in RR-1 and RR-3, did not achieve Code required coverage on the Unit 1 preservice inspection while Unit 2 did.

2) RR-23 VEGP-2 used actual wall thickness whereas VEGP-1 used nominal wall thickness.

3) RR-32 Further evaluation at VEGP-2 has determined:

1) the configuration described in the Code (IWC-2500-4(c))

is not the same as VEGP-2 RHR heat exchanger design and 25 the only appropriate Code Item Numbers are C2.31 and C2.33.

4)

RR-52 These relief requests have been incorporated into ISI-P-014 RR-53 and will be added to the next revision of the VEGP-1 Inservice Inspection Program.