ML20094P787

Rev 7 to VEGP-1 ISI Program Document ISI-P-006 to ISI Program for Vogtle Electric Generating Plant,Unit 1

ML20094P787
Person / Time
Site:	Vogtle
Issue date:	11/17/1995
From:	GEORGIA POWER CO.
To:
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References
NUDOCS 9511300130
Download: ML20094P787 (60)

Text

O ENCLOSURE

' (REVISION 7 TO VEGP-1 ISI PROGRAM DOCUMENT ISI-P-006)

TO GEORGIA POWER COMPANY LETTER LCV-0667,

" REVISION 7 TO INSERVICE INSPECTION PROGRAM" VOGTLE ELECTRIC GENERATING PLANT, UNIT 1 NRC DOCKET 50-424

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9511300130 951117 PDR ADOCK 05000424 f -.=-.,_,. .._ _ PDR,,

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GEORGIA POWER COMPANY INSERVICE INSPECTION PROGRAM (ISI-P-006)

FOR V0GTLE ELECTRIC GENERATING PLANT UNIT 1 PREPARED BY SOUTHERN NUCLEAR OPERATING COMPANY INSPECTION AND TESTING SERVICES GROUP SNC GPC REV DATE DESCRIPTION PREP'D REV'D APPV. APPV. APPV. APPR BY BY BY VOGTLE MGR. GEN.

(ITS) (ITS) (ITS) PROJECT ENG. MGR.

NMS SUPP.

S T ON 1 7/23/87 ADDS RELIEF REQUEST FOR [

3

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1/20/89

= = ""

MS REMEF REQUEST FOR XXXXXX 4 4/06/90 DELETED RELIEF REQUEST RR-45, 47, 48, 54 REVISED RR-12, 32 5 6/10/91 INCORPORATES COMMENTS \ [

PER GPC LTR. MSV-00318, 9/13/90 y [

6 11/5/93 INCORPORATES COMMENTS PER PCR 93-017 AND ADD

GENERAL COMMENT

S R I D REMU REQUESU 7 8/11/95

.B )J H9 H ffi@ Wh &/k

Vogtla Electric Generating Plant (VEGP-1)

Inservice Inspection (ISI) Program

(ISI-P-006) f Revision 7 Summary of Channes l

fl

i. Affected ISI Program .

Document Panes Changes 1

Distribution List Changed to reflect current organization.

1-1 thru l-6 Added words for clarification and added RR-59 to the General Relief Request listing. Removed references to the Line and Equipment Designation Lists o'n page 1-1 since they were deleted from this document in revision 6.

j Referenced the Pre-VEGP Improved Technical Specification on pages 1-2,' l-4, and 1-5. Also, section was re-formatted.

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2-6, 2-15, 2-1 Sa, 2-22 Added applicable relief request numbers in table 2-23,2-23a and 2-23b and re-formatted the table resulting in extra pages.

3-2, 3-5, 3-Sa, 3-12 Added applicable relief request numbers in table and 3-12a and re-formatted the table resulting in an extra page.

4 l 4-2 thru 4-4a Added applicable relief request numbers in table and re-formatted the table resulting in extra pages.

a 6-1 thru 6-4 Added references to RR-58 through RR-62 and I re-formatted the table. On page 6-1 revised scope to reflect RRs prepared in addition to the pre-service  ;

I RRs.

c 6-39 and 6-40 Removed sentence for clarification. Page 6-40 intentionally left blank.

5- 6-41 and 6-41a Changed wall thicknesses to reflect appropriate nominal and actual thickness measurements. Also added implementation schedule.

6-43 Revised weld examination limitation for consistency with PSI and ISI examinations.

002842 Page 1 of 2 1

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_. - Vogtle Electric Generating Plant (VEGP-1)

. Inservice Inspection (ISI) Program I

(ISI-P-006) d i

Revision 7 Summary of Channes -

(Continued) 6-54 thru 6-56 Added two CVCS Charging Pump welds that were ,

inadvertently omitted from original relief request. Also [

made some editorial changes and changed item number on Discharge Pulsation Damper, 6-82 and 6-82a Changed relief request to note the relocation of snubber testing requirements to a licensee-controlled document.

6-100 Intentionallyleft blank.

6-101 thru 6-103_ Request approval to use ASME Code Case N-416-1 and l

augment the N-416-1 requirements with additional surface i

examination on the root pass layer of butt and socket 1 welds.

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6-104 thru 6-106 - Request approval to use ASME Code Case N-498-1.

6-107 thru 6-109 Request approval to use ASME Code Case N-509.

6-110 thru 6-111 Request that selected Class 2 components be excluded j from the surface and volumetric examination requirements as allowed by the 1989 Addenda through the 1992 Edition of ASME Section XI.

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_2_,2-3 --,4-- '" ~

- VEGP-1 ISI-P-006 List of Effective Pages  ;

Distribution, Rev. 7 iTable of Contents, Rev. 6

-Introduction: .

Page 1-1, Rev.7 r Page 1-2, Rev.7_

Page .1-3, . Rev. 7 Page 1-4, ' Rev. 7 Page 1-5, Rev.7

- Page 1-6, Rev.7 Class 1:

' Page 2-1, Rev.0  !

Page 2-2, Rev.5

- Page 2-3, Rev.0'

. Page 2-4, ' R.ev. 0 Page 2-5, , Rev.' O Page 2-6, Rev.7 Page 2-7, Rev.1

' Page 2-8, Rev.0

' Page 2-9, Rev.O Page 2-10, Rev. O Page 2-11, Rev. 0 Page 2-12, - Rev. O Page 2-13, Rev. I  ;

Page 2-14,' Rev. O Page 2-15, Rev. 7 Page 2-15a, Rev. 7

' Page 2-16, Rev. O Page 217, Rev. O Page 2-18, Rev. 0

Page 2-19, Rev. O Page 2-20, ' Rev. 0 Page 2-21, Rev. 0 -

i- Page 2-22, Rev. 7 j Page 2-23, Rev. 7 ,

Page 2-23a, Rev. 7  !

. Page 2-23b, Rev. 7

Page 2-24, Rev. 0.-

Class 2:

Page 3-1, Rev.O Page 3-2, . Rev. 7

. Page 3-3,- Rev.0 i Page 3-4, Rev.5.

l 002842 1of5 006 Rev. 7 1

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____.___ _ n = _-____ ________._ = = = =

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. Class 2 (continued):

P. age 3-5, - Rev. 7 Page 3-Sa, Rev. 7 Page 3-6, Rev.5 Page 3-7, Rev. O .

-Page 3-8, Rev.O Page 3-9, Rev. O Page 3-10, Rev. O Page 3-11, Rev. O Page 3-12, Rev. 7 Page 3-12a, Rev. 7 ,

Page 3-13, Rev. 0 Class 3:

Page 4-1, Rev.O Page 4-2, Rev. 7 Page 4-2a, Rev. 7 Page 4-3, Rev. 7 Page 4-3a, Rev. 7 Page 4-4, Rev.7 Page 4-4a, Rev. 7 Component Supports:

Page 5-1, Rev.O Page 5-2, Rev.O Page 5-3, Rev.O Page 5-4, Rev.O ReliefRequests: J Page 6-1, Rev.7 Page 6-2, Rev.7 Page 6-3, Rev.7

. Page 6-4, Rev. 7 Page 6-5, Rev.5 Page 6-6, Rev.1 Page 6-7, Rev.1 l

Page 6-8, Rev.1 Page 6-9, Rev.1 Page 6-10, Rev.1 Page 6-11, Rev.1 Page 6-12, Rev.1 Page 6-13, Rev.1 Page 6-14, Rev. 6

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Page 6-15, Rev.1

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002842 2 of 5 006 Rev. 7

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. ReliefRequests (continued):

, . Page 6-16, Rev.1 Page 6-17, Rev.1 -

Page 6-18, Rev. 4 .i Page 6-19, Rev.1 , l

. Page 6-20, Rev.1- )

j Page 6-21, Rev.1

Page 6-22, Rev.1 l

Page 6-23, Rev.1

Page 6-24, Rev. I j Page 6-25, Rev. I a Page 6-26, Rev.1

Page 6-27, Rev.1 Page 6-28, Rev.1 l . Page 6-29, Rev.1 Page 6-30, Rev. 5

- Page 6-31, Rev.1

. 'Page 6-32, Rev.1 i Page 6-33, Rev.1 l

- - Page 6-34, Rev.1

i. Page 6-35, Rev.1 i Page 6-36, Rev. 5 Page 6-36a, Rev. 5 i- Page 6-37, Rev. 5 1

Page 6-38, Rev. 2 1 Page 6-39, Rev. 7 Page 6-40, Rev. 7 Page 6-41, Rev. 7 Page 6-41a, Rev. 7 Page 6-42, Rev.1 Page 6-43, Rev. 7 Page 6-44, Rev.1

Page 6-45, Rev.1

Page 6-46, Rev. 5

. Page 6-47, Rev. 5 Page 6-48, Rev. 5 i Page 6-49, Rev. 5 Page 6-49a, Rev. 5 Page 6-49b, Rev. 5 Page 6-49c, Rev. 5 j

Page 6-49d,Rev. 5 Page 6-50, Rev.1 i

002842 3 of 5 006 Rev. 7 i i

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Reli:fRequests (continued):  ;

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Page 6-51, Rev.1 Page 6-52, - Rev.1 '

Page 6-53, .Rev. I  ;

' Page 6-54, . Rev. 7 ' '

' Page 6-55, ' Rev. 7

< Page 6-56, Rev. 7 ,

Page 6-57, Rev. 5

" . Page 6-57a, Rev. 5 Page 6-58, Rev. 4 - ,

Page 6-58a, Rev. 4 Page 6-59, Rev. 4 Page 6-60, Rev. 2 i Page 6-61, Rev,1 l Page 6-62, Rev.1 Page 6-63, Rev.1 - ,

,. Page 6-64, Rev.1 '

. Page 6-65, Rev. 0

Page 6-66, . Rev. 0 .

i .Page 6-67, Rev. 0

' Page 6-68, Rev. 0

, Page 6-69, Rev. O  !

' Page 6 70, Rev. 0 Page 6-71, Rev. 5 -

Page 6-72, Rev. O '

Page 6-73, Rev. 0 Page 6-74, . Rev. O I

Page 6-75, Rev. O Page 6-76, Rev 0 Page 6-77, Rev. O Page 6-78, Rev. 0 y Page 6-79, Rev. O

Page 6-80, Rev. O i Page 6-81, Rev. 2 Page 6-81a, Rev. 2 Page 6-82, Rev. 7 Page 6-82a, Rev. 7 ,

Page 6-83, Rev. I j Page 6-84, Rev.1 Page 6-85, Rev. 4 Page 6-86, Rev.1 Page 6-87,- Rev. 4 Page 6-88, Rev. 4 T

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002842 4 of 5 006 Rev. 7 l 1.

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ReliefRequests (continued):

Page 6-89, Rev. 4

- Page 6-90, Rev. 6 Page 6-90s, Rev. 6 ,

Page 6-90b, Rev. 6 Page 6-91, Rev.1 Page 6-92, Rev. 5

- Page 6-93, Rev. 5

Page 6-94, Rev. 5 Page 6-95, Rev. 3 Page 6-96, Rev. 4

, Page 6-97, Rev. 4 Page 6-98, Rev 4 Page 6-99, Rev. 6 Page 6-100, Rev. 7 Page 6-101, Rev. 7

. Page 6-102, Rev. 7 '

Page 6-103, Rev. 7 Page 6-104, Rev. 7 Page 6-105, Rev. 7 Page 6-106, Rev. 7 Page 6-107, Rev. 7 Page 6-108, Rev. 7 Page 6-109, Rev. 7

, Page 6-110, Rev. 7 Page 6-111, Rev. 7 i ,

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s 002842 5 of 5 006 Rev. 7 i

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VEGP-1 INSERVICE INSPECTION PROGRAM (ISI-P-006) r DISTRIBUTION LIST

HOLDER MANUAL NUMBER i

J. J. Churchwell 4 i

Deleted 6 l

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• L.L.Rowe 14 1

l A. E. Cardona 18 l 1

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K. G. Lowery 20 l 1

L. K. Mathews 22 L. A. Ward 26 l

Supervisor, Engineering Support 29 j

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002842 006 Rev. 7 a i i

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1,0 INTRODUCTION 1.1 General This document details the scope ofinservice inspections for the Vogtle Electric Generating Plant (VEGP) Unit I and includes the following points ofinterest:

• Frequency ofinspections.

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• Identification of all areas to be examined.

. ReliefRequests.

The contents of this document are subject to change (with approval) during the course ofinservice inspections.

- The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, i

1983 Edition through the Summer 1983 Addenda is currently used for inservice inspection (ISI). The l actual edition applicable to ISI is the latest edition approved by the Nuclear Regulatory Commission 12 months prior to the date ofissuance of the operating license per 10 CFR 50.55A. Additionally, inspection program B will be used as defined by IWA-2400 of Section XI.

i 1.2 Scope 1

This document is a description of the Inservice Inspection Program for Class 1,2, and 3 components.

1.3 Component Unarading

All plant components have been reviewed to determine the appropriate classification for inservice inspection. The classification information is given in the Line Designation List and Equipment

! Designation List located in the VEGP Unit 1 Inservice Inspection Plan, ISI-P-005. It must be noted, l however, that the classification of components as ISI Class 1, 2, or 3 for inservice inspection does 4

not imply that the components were designed or constructed in accordance with the same ASME classification requirements. The component design codes remain as stated in the VEGP Final Safety Analysis Report (FSAR).

1,4 Responsibility i

Georgia Power Company bears the overall responsibility for the performance of the inservice inspections. Certain nondestructive examinations will be performed by a qualified inspection 1

, 000849 l-1 006 Rev. 7 l

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agency. The results of such examinations will be reported to Georgia Power Company for final evaluations and disposition.

1.5 Records -

r Records and documentation of all information and inspection results, which provide the basis for evaluation and which facilitate comparison with results from subsequent inspections, will be available for the active life of the plant.

i l 1.6 Methods of Examination 1 -

. - The method of examination planned for each area is delineated in subsequent sections. Personnel i performing nondestructive examinations will be trained in accordance with the American Society for Nondestructive Testing (ASNT) and the ASME Code.

I 1.6.1 Eddy Current Eddy current examinations will be performed on the steam generator tubing in accordance with

] the Pre-VEGP Improved Technical Specification Section 4.4.5.0 and Regulatory Guide 1.83, l l Rev.1. The alternative techniques used for this examination, as permitted by paragraph .

IWA-2240, either satisfy or exceed the requirements of Appendix IV of ASME Section XI and/or Article 8, Appendix I of ASME Section V.

} 1.6.2 Liauid Penetrant  ;

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Dye penetrant inspections will be performed whenever a surface examination is required on l nonmagnetic components.

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1.6.3 Magnetic Particle  ;

Magnetic particle tests will usually be used when surface examination of carbon steel components l

! is required. j i i l.6.4 Radioarachic

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l Radiographic techniques may be used as an alternative method to ultrasonic examinations. 1 1

1 i I 1.6.5 Ultrasonic i' Ultrasonic examinations will be conducted in accordance with the provisions of Articles 4 and 5 of Section V, ASME, or Appendix III of Section XI, ASME, as applicable. The reactor vessel will be examined to the requirements ofRegulatory Guide 1.150, Rev. I to the extent practical.

000849 l-2 006 Rev 7

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l 1.6.6 Visual Tests A visual test (VT) inspection will be employed to provide evidence ofleakage or to provide a report of the general condition of the component.

,I A. The VT-1 inspection shall be performed to determine corrosion, erosion, wear, cracks, or physical damage of the part, component, or surface being inspected. ,

B. The VT-2 inspection shall be performed to determine and locate leakages from pressure retaining components or excessive leakage from components without 4 leakage collection systems.

I C. The VT-3 inspection shall be performed to determine the structural, general, and physical conditions of components or their supports.

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! - D. The VT-4 inspection shall be performed to ensure the operability of components and their mechanical or hydraulic devices.

4 y l 1.7 Evaluation of Examination Results Examination results are evaluated per IWA-3000, IWB-3000, and IWF-3000 of the ASME Code,Section XI. Articles IWC-3000 and IWD-3000, " Acceptance Standards for Flaw Indications,"

i are in the course of preparation and, as yet, are not available for use. Therefore, the mies of

IWB-3000 may be utilized for ISI Class 2 and 3 components.

. 1.8 Reoair and Replacement Procedures p Repair and replacement procedures have been developed by Georgia Power Company.

1.9 Limitations of Examinations Certain limitations to nondestructive examination of welds due to geometric configuration or

. inaccessibility were identified during the Preservice Inspection. During ISI the required ,

examination will be accomplished to the maximum extent possible and limitations will be documented in relief requests. Known relief requests are contained in the Relief Request section ,

of this document. Additional relief requests will be submitted as necessary, i

i The inservice inspection program outlined in the attached tabulations have been developed as a result of a design review and the Preservice Inspection.

000849 l-3 006 Rev. 7 a

1.10 Auamented Examinations The Nuclear Regulatory Commission (NRC) has required certain augmented examinations to assure structural reliability. The areas ofinterest and the examinations to be performed are discussed below.:

1.10.1 The Reactor Coolant Pump flywheels shall be examined per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14 Revision 1, August 1975. (

Reference:

Pre-VEGP Improved Technical Specification Section 4.4.10.2.)

1,10.2 The four main steam lines and feedwater lines from the containment penetration flued head outboard welds up to the first five-way restraint shall be examined. The extent of the inservice examinations completed during each inspection interval (ASME Code Section XI) shall provide 100 percent volumetric examination of circumferential and longitudinal pipe welds to the extent practical. (

Reference:

Pre-VEGP Improved Technical Specification Section 4.4.10.3.) l 1.10.3 During each ten year inspection interval, a minimum of 7.5 percent of the required welds in the engineered safety systems (safety injection, containment heat removal, and residual heat removal) will be subjected to an ultrasonic examination. For VEGP-1 this commitment will require that 70 J welds be ultrasonically examined each ten-year interval. These added welds are mostly in thin- I walled or small-diameter piping that Section XI exempts from volumetric weld examinations because of size, thickness, pressure, or temperature.

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000849 l-4 006 Rev. 7 2

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1.10.4 Snubbers installed on safety-related systems as well as snubbers whose failure of the system on which they are installed would adversely affect a safety-related system shall be a=minaA

(

Reference:

Pre-VEGP Improved Technical Specifications Section 3/4.7.8.)

1.10.5 Georgia Power Company letter GN-1345 dated February 9,1987, to the U. S. Nuclear j 1

Regulatory Commission requires that a walkdown for visual observation ofleakage be performed on accessible ASME Code Class 3 portions of the nuclear service cooling water system. This ,

visual observation is required to be performed with the system at operational pressures during each refueling interval for the first ten years of service. In addition, an ultrasonic examination of

- two representative welds which are in piping 24 inches in diameter, one in each unit, will be

- performed every 40 months for the first 10 years of service.

'l.I1 ReliefReauests During the course of the preservice inspection, examination areas were identified where total i

compliance with the requirements of the ASME Code were not achieved. Relief requests were prepared for each of these areas. Relief requests were also added post-PSI in order to take advantage of ASME Section XI Code Cases. The relief requests address the area of relief, ASME Code examination requirements, Code item no. and category (if applicable), basis for relief, alternate examination (if any), and implementation schedule (if applicable). Each relief request is l >

identified by a unique number and is contained in Section 6 of this document. Relief requests that pertain to a particular category and code item no. are listed opposite the appropriate item no. in the IWB, IWC, IWD, or IWF Table. General relief requests that do not apply to a unique item no, are identified below. l 4 Relief Reauest No. Examination Area

! RR-18 Use of Section XI, Appendix III for austenitic i

! and dissimilar metal pipingwelds i

i i RR-22 Technique for UT examination of welds in centrifugally cast piping and static-cast elbows

RR-23 Use of a single calibration block for examination of -

three sizes of centrifugally cast piping and three  ;

sizes of static-cast elbows l RR-31 Use of piping calibration blocks to examine thin-wall

! vessel welds ,

, 000849 l-5 006 Rev. 7 f

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s Relief Request No. Examination Area RR-35 Technique for volumetric exam of thin-wall piping.

4 RR-36 UT examination of thin-wall Class 2 piping RR-37 UT examination of small-diameter Class 2 piping i

RR-38 Subsection IWE i RR-40 Notch length in basic ultrasonic calibration blocks for examination ofvessel welds RR-59 ' Alternative pressure test requirement for welded i repairs or installation of replacement items by 4

welding on Class 1,2, and 3.

1.12 Code Cases To Be Used During ISI 4

The guidance of the Code Cases listed in Regulatory Guide 1.147, Revision 4, and subsequent approved revisions, may be used during Inservice Inspections.

000849 l-6 006 Rev. 7

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Vogtle Electric Genera 6;; Plant Unit No.1 Inservice Inspection 006 Rev. 7 -

Table IWB-2500-1 Examination Categories t

B-E, PRESSURE RETAINING PARTIAL PENETRATION WELDS IN VESSELS Extent and Frequency of Evamination ,

Examination Requirements / Examination 1st 2nd,3rd,4th Relief Figure No. Method' Interval Intervals Reauest Comments Item No. Parts Examined B4.10 - Partial Penetration Welds B4.11 VesselNozzles External VT-2 25% nozzles Same as for RR-60 Surfaces 1st interval External VT-2 25% nozzles Sanz as for RR-60 l B4.12 Control Rod Drive Nozzles Surfaces 1st interval B4.13 Instrumentation External VT-2 25% nozzles - Same as for - RR-60 -l Nozzles Surfaces 1stinterval Pressurizer .

B4.20 Heater Penetration External VT-2 All nozzles Same as for RR-60 l Welds Surfaces 1st 'mterval NOTES:

(1) The examinations shall be performed during conduct of the system hydrostatic test (IWB-5222).

4 000841 2-6

b Vogtle Electric Generating Plant Unit No.1 InserviceInspection Table IWB-2500-1 Examination Categories 006 Rev. 7 B-H, INTEGRAL ATTACHMENTS FOR VESSELS Extent and Frequency of Examination Examination Requirements / Examination 1st 2nd,3rd,4th Relief l Item No. Parts Examined' Figure No. Method Interval Intervals Request Comments Reactor Vessel B8.10 Integrally Welded IWB-2500-13, PT/MT* Weld 2

Weld2 RR-52,61 l Attachments -14, and -15 i

Pressurizer 2

B8.20 Integrally Welded IWB-2500-13, PT/MT* Weld2 Weld RR-10,16, Attachments -14, and -15 61 l Steam Generator B8.30 Integrally Welded IWB-2500-13, N/A N/A N/A N/A to VEGP, Attachments -14, and -15 Heat Exchanners B8.40 Integrally Welded IWB-2500-13, N/A N/A N/A N/A to VEGP.

Attachments -14, and -15 l

000841 2-15 l

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Vogtle Electric Generating Plant Unit No.1 Inservice Inspection Table IWB-2500-1 Examination Categories 006 Rev. 7 B-H, (continued) t NOTES:

(1) Weld buildup on nozzles that is in compression under normal conditions and provides only component support is excluded from examination.

Examination is limited to those integrally welded attachments that meet the following conditions:

(a) the attachment is on the outside surface of the pressure retaining component; l (b) the attachment provides component support es defined in NF-1110; (c) the attachment base material design thickness is 5/8 in. or greater, and (d) the attachment weld joins the attachment either directly to the surface of the vessel or to an integrally cast or forged attachment to the vessel.

(2) The extent of the examination includes essentially 100% of the length of the attachment weld at each attachment subject to examination. ,

(3) In case of multiple vessels of similar design, size, and service, the examination is limited to the attachment welds of one vessel. Applies only to Item No. B8.30 and B8.40.

(4) For the configuration shown in Fig. IWB-2500-14, a volumetric examination ofvolume A-B-C-D from one side (B-C) of the circumferential weld may be performed in lieu of the surface examination.

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I 000841 2-15a l l

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Vogtle Electric Generating Plant Unit No.1 -

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Inservice Inspection ' . *'

Table IWB-2500-1 Examination Categories 006 Rev 7 B-P, ALL PRESSURE RETAINING COMPONENTS Extent and Frequency of-Ewaminating Tert Examination 1st 2nd,3rd,4th - - Relief Item No. Parts ErmmiH Reauirements' Metixxf Interval Intervals Recuest Comments Reactor Vessel -

.- B15.10 ' Pressure Retaining System lealt- VT-2 Each refuel- Each refuel-

Boundary age test' ' ing outage' ing outage' (IWB-5221)

L B15.11 Pressure Retaining System VT-2 One test' One test RR-60 'l 2

Boundary hydro test perinter-(IWB-5222) val'  ;

Pressurizer VT-2 Each refuel- Each refuel-  :

B15.20 Pressure Retaining System leak-Boundary age test' ' 'mg outage' ing outage' l (IWB-5221)

B15.21 Pressure Retaining System VT-2 One test' One test RR-60 l 2

Boundary hydro test per 'mter-(IWB-5222) val'

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Steam Generators

' l B15.30 Pressure Retaining System leak- VT-2 Each refuel- Each refuel-

! Boundary age test' ing outage' ing outage' (IWB-5221) 2-22 i 000841 1

_._ ____.__m_ _ _ . _ _ _ _ _ _ _ _ . . _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ -_ _ _ , . _ _ . _

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

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Vogtle Electric Generating Plant Unit No.1 -

' Inservice Inspection Table IWB-2500-1 Examination Categories 006 Rev. 7-i.

- B-P, (continued) l Extent and Frequency.of Examination Test Examination 1st 2nd, 3rd,4th . Relief; i Item No. Parts Examined Reauirements' Method" Interval Intervals Request Connr.ents l Steam Generator (Continued)

' B15.31' Pressure Retaining System VT-2 One test' One test RR-60 2

Boundary hydro test perinter-(IWB-5222) val' 1

! Heat Exchenaers

( ,

i B15.40 Pressure Retaining System leak- N/A N/A N/A N/A to VEGP.

Boundary age test' '

(IWB-5221) l B15.41 Pressure Retaining System N/A .N/A N/A N/A to VEGP.

Boundary hydro test' '

(IWB-5222) l L Piping B15.50 Pressure Retaining System leak- VT-2 Each refuel- Each refuel- '

Boundary age test' ' ing outage' 'mg outage' l (IWB-5221)

B15.51 Pressure Retaining System VT-2 One test' One test RR-60 l perinter-Boundary ' hydro test

• L (IWB-5222) val' l

000841 2-23

- . . . . . , =- . . . . . . .- . .-. . .

Vogtle Electric Generating Plant Unit No.1 Inservice Inspection

- Table IWB-2500-1 Examination Categories 006 Rev. 7 -

B-P, CONTINUED Extent and Frequency of Examination Test Examination 1st 2nd,3rd,4th ' Relief

. Item No Parts Examined Requirements Method

• Interval Intervals Request Ccs w =4s-Pumps B15.60 Pressure Retaining System leak- VT-2 Each refuel- Each refuel-Boundary age test' 7 ing outage' ing outage'-

(IWB-5221)

B15.61 Pressure Retaining System VT-2 One test' One test RR-60 'l 2

Boundary hydro test per inter-(lWB-5222) val' Valves B15.70 Pressure Retaining System leak- VT-2 Each refuel- Each refuel-Boundary age test' 7 ing outage' ing outage' (IWB-5221)

B15.71 Pressure Retaining System VT-2 One test' One test RR-60 l 2

' Boundary hydro test perinter-(IWB-5222) val' 000841 2-23a ;l

Vogtle Electric Generating Plant Unit No.1 Inservice Inspection Table IWB-2500-1 Examination Categories 006 Rev. 7 B-P, CONTINUED NOTES:

(1) The pressure retaining boundary during the system leakage test shall correspond to the reactor coolant system boundary, with all valves in the normal position, which is required for normal reactor operation startup. The VT-2 examination shall, however, extend to and include the second closed valve at the boundary extremity.

(2) The pressure retaining boundary during the system hydrostatic test shallinclude all Class I components within the system boundary.

(3) System pressure tests of the reactor coolant system shall be conducted in accordance with IWA-5000. System pressure tests for repaired, replaced, or altered components shall be governed by IWA-5214(c).

(4) Visual examination ofIWA-5240.

. (5) The system leakage test (IWB-5221) shall be conducted prior to plant startup following each reactor refueling outage.

(6) The system hydrostatic test (IWB-5222) shall be conducted at or near the end of each inspection interval.

(7) A system hydrostatic test (IWB-5222) and the accompanying VT-2 examination are acceptable in lieu of the system leakage test (IWB-5221) and VT-2 examination.

l 000841 2-23b l

I .

l l

Vogtle Electric Generating Plant Unit No.1

( Inservice Inspection Table IWC-2500-1 Examination Categories 006 Rev. 7 l

l C-A, PRESSURE RETAINING WELDS IN PRESSURE VESSELS Extent and Frequency of l

l Examination

Examination Requirements / Examination 1st 2nd,3rd,4th Relief 5

Item No. Parts Examined Figure No. Method Interval Intervals Reaues_t Comments C1.10 Shell Circum- IWC-2500-1 UT Welds' at Same as for RR-29,30, erential gross 1st interval' 62 l Welds stmetural discon-tinuity2 only C1.20 Head Circum- IWC-2500-1 UT Head-to-shell Same as for RR-30,62 l ferential weld' Ist interval

• Welds C1.30 Tubesheet-to- IWC-2500-2 UT Tube- Same as for RR-29,30, ShellWeld sheet-to- 1st interval

• 62 l shell weld' NOTES:

(1) Includes essentially 100% of the weld length.

(2) Gross stmetural discontinuity is defined in NB-3213.2. Examples arejunctions between shells ofdifferent thicknesses, cylindrical shell-to-conical shell junctions, shell (or head)-to-flange welds, and head-to-shell welds.

(3) In the case of multiple vessels of similar design, size, and service (such as steam generators, heat exchangers), the required examinations may be limited to one vessel or distributed among the vessels.

(4) The vessel areas selected for the initial examination shall be reexamined over the service lifetime of the component.

000841 3-2

Vogtle Electric Genertting Plant Unit No.1 Inservice Inspection . ,

- Table IWC-2500-1 Examination Categories ' 006 Rev. 7 -

C-C, INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS, AND VALVES Extent and Frequency of Examination Examination Requirements / Examination Ist 2nd,3rd,4th Relief Item No. Parts Examined Figure No. Method Interval Intervals Reauest Comments -

Pressure Vessels C3.10 Integrally Welded IWC-2500-5 PT/MT 100% of re- Same as for. RR-61,62 28 Attachments quired areas ist interval ofeach weld-23 ed attachment Piping C3.20 Integrally Welded IWC-2500-5 PT/MT 100% of re- Same as for RR-61 l Attachments quired areas 1st interval' ofeach weld-

. ed attachment

• Pumps C3.30 Integrally Welded IWC-2500-5 PT/MT 100% of re- Same as for - RR-30,61 Attachments quired areas Istinterval'

• of each weld-ed attachment ' * '

000841 3-5

-l

- , - . . - . , - - -- . . . - - . = - . ,- .- - - - - - - . . . . - - - . - - . . - . . . . -. - - --- - - - - ..- -

Vogtle Electric Generating Plant Unit No.1 Inservice Inspection Table IWC-2500-1 Examination Categories 006 Rev. 7 C-C, (continued)

Extent and Frequency of Examination Examination Requirements / Examination 1st 2nd, 3rd,4th Relief Item No. Parts Examined Figure No. Method Interval Intervals Request Comments Valves C3.40 Integrally Welded IWC-2500-5 N/A N/A N/A N/A toVEGP.

Attachments NOTES:

(1) Examination is limited to those integrally welded attachments that meet the following conditions:

(a) the attachment is on the outside surface of the pressure retaining component; (b) the attachment provides component support as defined in NF-1110; (c) the attachment base material design thickness is 3/4 in. or greater, and (d) the attachment weld joins the attachment either directly to the surface of the component or to an integrally cast or forged attachment to the component.

(2) In case of multiple vessels of similar design rad service, the required examinations may be conducted on only one vessel. Where multiple vessels are provided with a number of similar attachments; the examination of the attachments may be distributed among the vessels.

-(3) The areas selected for the initial examination shall be reexamined over the service lifetime of the component.

(4) Limited to attachments of those components required to be examined under Examination Categories C-F and C-G. ,

4 l

i

)

000841 3-Sa l 4

4

= , , ._ . -.-.-.m., - - . - - - ,_. --m__ -,,,,_m-...,. . - . , . _ . , . .-.,w .m. ., , - , . _ , - -.m..

Vogtle Electric Generating Plant Unit No.1 -

Inservice Inspection

. Table IWC-2500-1 Examir 'on Categories 006 Rev. 7 C-H, ALL PRESSURE RETAINING COMPONENTS Extent and Frequency of Examination 2

Test Examination Each Each Relief Item No. Parts Examined' R_equired Method' Period

• Interval

• Reauest Comments Pressure Vessels 1

C7.10 Pressure Retaining IWC-5221 VT-2 Pressure RR-45 Components test' retaining boundary' '

C7.20 Pressure Re- IWC-5222 VT-2 Pressure RR-60 l taining Com- test retaining ponents boundary' '

Piping i

C7.30 - Pressure Re- IWC-5221 ~

VT-2 Pressure RR-46

! taining Com- test' retaining ponents boundary' '

i l C7.40 Pressure Re- IWC-5222 VT-2 Pressure RR-44,

, taining Com- test retaining 60 l 57 ponents boundary f

i j i

i

000841 3-12

____m_._-_________m_._-_.__________._______..m_ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ __ ._. -.. ,-- .- -

Vogtle Electric Generating Plant Unit No.1 Inservice Inspection Table IWC-2500-1 Examination Categories 006 Rev. 7 '

p C-H, (continued)

Extent and Frequency of-Examination t 2 Test Examination Each Each Relief - ,

Item No. Parts Examined' Reauired Method' P_,riod* Interval

• Reauest Comments i

4 Pumps C7.50 Pressure Re- IWC-5221 VT-2 Pressure RR-46 taining Com- test' retaining .

ponents oundary' '

l C7.60 Pressure Re- IWC-5222 VT-2 Pressure RR l taining Com- test retaining - I ponents boundary' '

Valves C7.70 Pressure Re- IWC-5221 VT-2 Pressure RR-46 j taining Com- test' retaining ponents boundary' ' '

1 C7.80 Pressure Re- IWC-5222_ VT-2 Pressure RR-44, taining Com- test retaining 60 l_

ponents boundary" ,

i 000841 3-12a l

-i

~

. Vogtle Electric Generating Plant Unit No.1

Inservica Inspection - . .

Table IWD-2500-1 Examination Categories 006 Rev. 7 D-A, SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION Extent and Frequency of

Examination Test And Examination Examination Each- Each Relief

! L Item No. Parts Examined Reauirements ' Method Period Interval . Reauest Comments t ,

D1.10 - Pressure Retaining IWA-5000/ VT-2 Pressure re- RR-49,50 Components' IWD-5221' taining boundary

• IWA-5000/ Pressure RR-49,60 ' l IWD-5223' VT-2 retaining 24 boundary D1.20 Integral Attach- Figure ' VT-3 Integral RR-61 . l ment-Compo- IWD-2500-1 attachments nent Suppons and Restraints '

i ,

1

!. D1.30 Integral Attachment- Figure VT-3 Integral RR-61 l B Mechanical and IWD-2500-1 attachments

] Hydraulic Snubbers' l

DI.40 Integral Attach- Figure VT-3 Integral RR-61 l 4; ment-Spring IWD-2500-1 attachments .

F. Type Supports' DI.50 Integral Attach- Figure VT-3 Integral N/A to VEGP l ment-Constant IWD-2500-1 attachment Load Type Sup-ports' i

000841 4-2 L

_. . _ _ _ _ _ . -___ ____._ _ 1_ _ . ._ _- . . . _ _ _ . . _ _ . _ _ _ _ , .________2

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

=

~'

Vogtle Electric Generating Plant Unit No. I Inservice Inspection Table IWD-2500-1 Examination Categories - 006 Rev. 7 t

D-A, (continued)

Extent and Frequency of Examination -

Test And Examination Examination Each Each Relief Item No. Parts Examined Requirements Method Period Interval Request Comments DI.60 Integral Attach-~ Figure VT-3 Integral N/A to VEGP l ment-Shock IWD-2500-1. attachment .

Absorbers' NOTES:  ;

(1) The system boundary extends up to and including the first normally closed valve or valve capable of automatic closure as required to perform the safety-related system function. .

(2) The system hydrostatic test shall be conducted at or near the end of each inspection interval or during the same inspection period of each  !

i inspection interval for Inspection Program B. _ _

1 (3) In the case of multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be examined. The integral attachments selected for examination shall correspond to those component supports selected by  :

j IWF-2510(b). ,

t (4) There are no exemptions or exclusions from these requirements except as specified in IWA-5214(c).~  ;

(5) A system hydrostatic test (IWD-5223) and accompanying VT-2 examination are acceptable in lieu of the system pressure test (IWD-5221) and '

VT-2 examination.

?

l 000841 4-2a l  ;

i  :

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

' Vogtle Electric Generating Plant Unit No.1 ,

Inservice Inspection Table IWD-2500-1 Examinatiur. Categories 006 Rev.7 D-B, SYSTEMS IN SUPPORT OF EMERGENCY CORE COOLING, CONTAINMENT HEAT REMOVAL, ATMOSPHERE CLEANUP, AND REACTOR RESIDUAL HEAT REMOVAL i Extent and Frequency of Examinat ion Test And Examination Examination Each Each Relief Item No. Parts Examined Reauirements Method Period Lnterval Request Commente -

D2.10 Pressure Retaining _ IWA-5000/ VT-2 Pressure re- RR-50 Components' IWD-5222' taining boundary

• IWA-5000/ Pressure re- ' RR-60 l '

IWD-5223' VT-2 taining boushuf

• D2.20 Integral Attachment- Figure VT-3 Integral RR-61 l Component Supports IWD-2500-1 attachment and Restraints' D2.30 Integral Attachment- Figure VT-3 Integral RR-61 l .

Mechtnical and IWD-2500-1 attachment l Hydraulic Snubbers' D2.40 Integral Attach-ment-Spring Figure IWD-2500-1 VT-3 Integral atts d s w.t RR-61 'l r Type Sepports' D2.50 Intq,ral Attach- Figure VT-3 Integral. N/A to VEGP l .

ment-Constant IWD-2500-1 attachment Load Type Supports

• r 000841 4-3 i

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

Vogtle Electric Genertting Plant Unit No.1 Inservice Inspection

_ Table IWD-2500-1 Examination Categories 006 Rev.7 D-B, (Continued) l Extent and Frequency of i Fv2.. :..d.cg Test And Examination Examination Each Each Relief Parts Examined Reauirements Method Period Interval Request _ Cc+.w. ;+

l Item No. .

D2.60 - Integral Attachment- Figure VT-3 Integral - N/A to VEGP l~

Shock Absorbers' IWD-2500-1 attachmaat NOTES:

(1) The system boundary extends up to and including the first normally closed valve or valve capable of automatic closure as required to perform the safety-related system function. _

(2) The system hydrostatic test shall be conducted at or near the end of each inspection interval or during the same

inspection period of each inspection interval for Inspection Program B.

i (3) In the case of multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be examined. The integral attachments selected for examination shall correspond to those component supports selected by IWF-2510(b).

l (4) There are no exemptions or exclusions from these requirements except as specified in IWA-5214(c).

(5) A system hydrostatic test (IWD-5223) and accompanying VT-2 examination are acceptable in lieu of the system pressure test (IWD-5222) and VT-2 examination. ,

i i

r 4

000841 4-3a l.

t

-m __ _ _ _ _ _ _ _ _ ._e a e * = e +- _ .- .-. - - ~ - .- _.__,m_ - _ _ _ _ _ _ __m _

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

Vogtle Electric Generating Plant Unit No.1 Inservice Inspection Table IWD-2500-1 Examination Categories 006 Rev. 7 A

D-C, SYSTEMS IN SUPPORT OF RESIDUAL HEAT REMOVAL FROM SPENT FUEL STORAGE POOL -

Extent and Frequency of 1 Exa...: ricn ,

Test And Examination Examination Each Each Relief Item No. Parts Examined Reauirements Method Period Interval Reauest - Comments 1

D3.10. Pressure Retaining IWA-5000/ VT-2 Pressure RR-50,53 Components' IWD-5221' retaining boundary *

• IWA-5000/ Pressure . RR-53,60 l IWD-5223' VT-2 retaining *

• boundary

D3.20 Integral Attachment- Figure VT-3 Integral RR-61 l Component Supports IWD-2500-1 attachment i and Restraints' i'

D3.30 Integral Attachment- Figure VT-3 Integral N/A to VEGP l Mechanical and IWD-2500-1 attachment Hydraulic Snubbers' t'

.i D3.40 Integral Attachment- Figure VT-3 Integral N/A to VEGP l ;

l Spring Type IWD-2500-1 attachment Supports'

D3.50 _ Integral Attachment- Figure VT-3 Integral N/A to VEGP l i Constant Load IWD-2500-1 attachment ,

l Type Supports' e

i 000841 4-4  ;

i

. t Vogtle Electric Generating Plant Unit No.1 Inservice Inspection 006 Rev. 7

Table IWD-2500-1 Examination Categories i

D-C, (Continued) l Extent and Frequency of Examination Test And Examination Examination Each Each Relief Method Period Interval Recuest Con.e. cats Item No Parts Examined Requirements l

VT-3 Integral N/A to VEGP l <

Integral Attachment- Figure D3.60

, Shock Absorbers' IWD-2500-1 attachment NOTES:

(1) The system boundary extends up to and including the first normally closed valve or valve capable of automatic closure

' as required to perform the safety-related system function.

, (2) The system hydrostatic test shall be conducted at or near the end of each inspection interval or during the same inspection period of each inspection interval for Inspection Program B.

(3) In the case of multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be examined. The integral attachments selected for examination shall correspond to those component supports selected by IWF-2510(b).

(4) There are no exemptions or exclusions from these requirements except as specified in IWA-5214(c). '

(5) A system hydrostatic test (IWD-5223) and accompanying VT-2 examination are acceptable in lieu of the system pressure n test (IWD-5221) and VT-2 examination.

t 1

000841 4-4a l-i a

l$

B p

l l

l-6.0 - RELEF REOUESTS i l 6.1 Scope

The following relief requests have been prepared from information determined in support of

< inspection activities (including preservice inspection) at VEGP Unit 1.

Relief Request No. Examination Area

' RR-1 Relief Request Withdrawn i

l RR-2 Mechanized exam of reactor vessel lower I shell-to-bottom head weld RR-3 Mechanized exam of reactor vessel lower shell longitudinal welds 4

RR-4 Mechanized exam of reactor vessel meridional welds

RR-5 Mechanized exam of reactor vessel bottom' head circumferentialwelds i RR-6 Volumetric exam of reactor vessel flange ligament um 4

RR-7 Volumetric exam of reactor vessel closure head welds RR-8 Mechanized exam of elbow-to-reactor vessel safe-end I welds s

RR-9 Class 1 bolting, greater than 2-in diameter 4

RR-10 Pressurizer integrally welded attachments RR-11 Visual exam of reactor vessel supports ,

RR-12 Volumetric exam of pressurizer welds t RR-13 Relief request withdrawn 00851 6-1 006 Rev. 7

Relief Reauest No. Examination Area RR-14 Volumetric exam of pressurizer surge-nozzle-to-vessel weld j 1

RR-15 ' Volumetric exam of pressurizer surge-nozzle inner radius RR-16 Pressurizer integrally welded attachments RR-17 Volumetric exam of steam generator nozzle-to-elbow welds ,

RR-lg Section XI, Appendix III for austenitic and dissimilar metal ,

piping welds l RR-19 Volumetric examination of steam generator channel head-to-tube sheet weld RR-20 Volumetric exam of Class 1 piping welds RR-21 Volumetric exam of Class 1 branch pipe connection welds RR-22 Volumetric exam of cast piping and elbows RR-23 Cast piping calibration block RR Volumetric exam of reactor coolant pump nozzle-to-elbow and nozzle-to-pipe welds RR-25 UT calibration block for reactor coolant pump nozzle-to-pipe welds RR-26 Volumetric exam of SA 376 piping welds t'

RR-27 Visual exam of Class 1 pump and valve intemals i

RR-28 Inner radius exam of steam generator outlet nozzle RR-29 Volumetric exam of steam generator secondary side welds RR-30 Volumetric and surface exam of Class 2 vessel welds RR-31 Use of piping calibration blocks to examine thin-wall vessels 6-2 006 Rev,7 000851 l l

1 l

_ - .- _ _J

R_ eliefReauest No. Examination Area RR-32 Volumetric exam of RHR heat exchanger nozzle inner radius RR-33 Relief request withdrawn .

2 RR-34 Volumetric exam of Class 2 piping welds RR-35 Technique for volumetric exam of thin-wall piping RR-36 Volumetric exam of Class 2 thin-wall piping RR-37 Volumetric exam of small-diameter Class 2 piping RR-38 Subsection IWE RR-39 Mechanized volumetric examination of pressure-retaining l

.I shell and head welds in the reactor vessel outside the beltline region

! RR-40 Notch length in basic ultrasonic calibration blocks for examination ofvesselwelds RR-41 Calibration blocks for reactor vessel nozzle-to-safe-end welds ,

a RR-42 Volumetric examination of nozzle inner radius section for l

steam generator inlet and outlet nozzles ,

RR-43 VT-4 visual examination of snubbers 1

E RR-44 Class 2 piping hydrostatically tested to Class 1 requirements RR-45 Relief request withdrawn 2

RR-46 System pressure test on Class 2 components 4

~000851 6-3 006 Rev. 7 l

l

' l

]

l o

4 i

l Relief Request No. Examination Area RR-47 Relief request withdrawn RR-48 Relief request withdrawn RR-49 System pressure test on Class 3 vertical pit type pumps RR-50 System pressure test on Class 3 components RR-51 ReliefRequest Withdrawn RR-52 Reactor Vessel integrally welded attachments RR-53 Class 3 hydrostatic test on Spent Fuel Cooling and Purification RR-54 Relief request withdrawn conditionally RR-55 Intentionally blank RR-56 Intentionally blank RR-57 ' Intentionally blank RR-58 Intentionally blank RR-59 Alternative pressure test requirement for welded repairs or installation of replacement items by ,

welding on Class 1,2, and 3 (Reference ASME Code Case N-416-1)

RR-60 Alternative rules for 10-Year System hydrostatic testing for Class 1,2, and 3 systems (Reference ASME Code Case N-498-1) i RR-61 Alternative rules for the selection and examination of Class 1,2, and 3 integrally welded attachments (Reference ASME Code Case N-509)

RR-62 . Selected Class 2 components be excluded from surface and volumetric examinations as allowed by 1989 Addenda through 1992 Edition of ASME Section XI 000851 6-4 006 Rev. 7

4

i. t i

VEGP-1 1: gg-y

Component or Relief Area 8

i

- Volumetric examination of pressure-retaining welds in centrifugally-cast' stainless steel piping and.

i static-cast stainless steel elbows made of SA 351-CF8A material in the Reactor Coolant System.

I .

Reauirement from which Reliefis Reauested 4

.ASME Code Section XI, Article III - 4420 requires that the examination shall be performed using

( sufficiently long examination beam path to provide coverage of the required examination volume in two beam-path directions. The examination shall be performed from two sides of the weld,

-where practicable or from one side of the weld as a minimum. Article III - 4430 requires that the angle beam examination for reflectors transverse to the weld shall be performed on the weld crown on a single scan path to examine the weld root by one-half V-path in two directions along the weld. Article III-2430 requires that manual scanning shall be done at twice (+6dB) the

- primary reference level as a minimum. - A meaningful ultrasonic examination cannot be '

accomplished on the cast stainless steel using conventional shear-wave techniques. Since a 1/2-node examination using a refracted 45' longitudinal wave was found to be the superior technique,

reliefis requested from the above requirements.

4 k

Basis for Relief l The cast SA-351, CF8A material contains a banded microstructure that consists of a duplex grain

i. size ranging from extremely coarse to very fine. This irregular grain structure causes significant

attenuation and some angular variations during a typical shear-wave ultrasonic examination. A better technique was developed wherein a 1.0 inch dual-element focused transducer, utilizing a 45' refracted longitudinal wave with a frequency of 1.0 Mhz was used. During calibration, the p primary reference level is set using side-drilled holes. Scanning is possible only at the primary l 1

reference level due to excessive noise associated with the higher gain levels and the metallurgical structure of the material. A demonstration using this technique was performed for Region II of the NRC and was determined to be a conservative method of detecting ID reflectors. (Reference NRC report numbers 50-425/85-24 and 50-425/85-25).

Alternate Examination A refracted-longitudinal wave ultrasonic examination, which is a 1/2 node examination, will be

_ performed. Scanning will be done at the primary reference level. The Code-required surface examination will be performed on all welds.

1-6-39 006 Rev. 7 4

1 This page intentionally left blank a

6-40 006 Rev. 7

1 VEGP-1 i

BB-M

' Comoonent or Relief Area

A single calibration block made from centrifugally-cast 29-inch inside diameter (ID) and

2.45-inch nominal wall piping was used to examine centrifugally cast piping and statically cast elbows as follows

1 I

Component Diameter Nominal Thickness Ma==nred Thickness 1 27-1/2"(Cold Leg) 2.32" to 2.69" 2.44" to 3.19" 29" & 31"(Hot Leg) 2.45" to 3.63" 2.48" to 3.54" j 2.60" to 3.49" 31"(Intermediate Leg) , 2.60" to 3.63" Requirement from which Reliefis Requested j Subparagraph III-3410, Appendix III of ASME Section XI requires that basic calibration

- blocks shall be made from material of the same nominal diameter and nominal wall i thickness or, pipe schedule as the pipe to be examined. Reliefis requested from this requirement for main loop piping in the primary reactor coolant system.

f B==le for Relief The single calibration block described above was fabricated from a dropout of actual I piping installed at VEGP. Due to its compatibility with the materials being examined and i the issues associated with examining cast stainless steel, it was determined during

preservice and the first inservice inspection interval to use this one calibration block for multiple examinations. Relief Request RR-23 was therefore submitted as part of Revision

! I to the VEGP Inservice Inspection Program.

The original version of RR-23 specified 27-1/2" diameter components with nominal thicknesses ranging from 2.32" to 2.35",29" diameter components with a nominal thickness ranging from 2.45" to 2.48", and 31" diameter components with nominal i- thicknesses ranging from 2.60" to 2.62" Relief was subsequently granted for the three diameters and thickness ranges in an NRC letter dated November 26,1991 from

- David J. Lange (NRC) to W. G. Hairston, III (GPC).

6-41 006 Rev. 7 1

- .- .-4-,...- . ** _ pop, .

4 VEGP-1 4

I RR-23 (continued) 4 Following completion of the Interval 1 ISI examinations for these components, it was

determined that the thicknesses of approximately 12 components (particularly elbows) exceeded those previously delineated in RR-23. After this determination, a review was

performed by GPC to ensure that previous examinations were satisfactory. A sensitivity demonstration was performed in the presence of an NRC Region II representative using the 2.45" thick calibration block and a 3.00" thick calibration block. Results of the demonstration were acceptable and it was acknowledged that the examinations performed on these components were being conducted in a conservative manner. GPC has

• . concluded that re-examination of these components during Interval 1 (usi ng a thicker block) would not provide any appreciable increase in safety. Correspondingly, it is estimated that to build scaffolding, remove and subsequently replace insulation, and to examine these welds would result in an additional 3 to 4 Rem of exposure were the affected components re-examined.

j Alternate ExaminatiGD

Examinations were conducted as described above.

Imolementation Schedule 4

All inspections for Interval I have been completed, therefore, no further action is anticipated. During Interval 2, examinations are anticipated to be conducted using the 2.45" thick block and the 3.00" thick block in conjunction with the provisions of Code Case N-461. Additional relief, if needed, will be sought at that time.

t 4

6-41a 006 Rev. 7 l Y

3

- - . ~ ~ ,

, s .

VEGF4 BIL-M (contimmed)

Attachement 1 Minimum .l Identification No. Code Category Descnpuon Percentame Examined Restnction 11201 0054 B-J 31" Elbow to Reactor raains Pump Nozzle 90 % 100% exam from elbow side,80% exam from nozzle side l 11201-006 4 B-J 31" Elbow to Reactor Coolant Panp Nozzle 90 % 100% exam from cibow side,80% exam from nozzle side 11201-007 4 B-J 31" Elbow to Reactorraalad Pany Nozzle 90 % 100% exam from elbow side,80% exam from nozzle t

' side -

11201 4084 B-J 31" Elbow to Reactor Coolast Pump Nozzle 90 % 100% exam from elbow side,80% exam from nozzle side  ;

B-J 27.5" Reactor raalaw Pump Nozzle to Pipe 75 % 100% exam from pipe side, 11201-009-1 50% exam from nozzle side 11201 010-1 B-J 27.5" Reactor raalad Pump Nozzle to Pipe 75% 100% exam from pipe side, l 50% exam from nozzle side I

I 11201-011-1 B-J 27.5" Peartar raalaw Peep Nozzle to Pipe 75 % 100% exam from pipe side, l 50% exam from nozzle side I

B-J 27.5" Reactor raalam Pump Nozzle to Pipe 75 % 100% exam frosa pipe side, I1201-012-1

' 50% exam from mante side i

6-43 006 Rev. 7 h

VEGP-1 4

RR-30

_ Comoonent or Relief Area I Volumetric and/or surface examination of pressure-retaining welds in Class 2 vessels (or components).

Specific examination identifications are shown in Attachment I to this reliefrequest. l ,

i Reauirement from which Reliefis Reauested

b. .

l Item Nos. C1.10, C1.20, and C1.30, Category C-A, Table IWC-2500-1 of ASME Section XI require t - volumetric examination of pressure-retaining welds in Class 2 pressure vessels. Applicable examination j volumes are shown in Fig. IWC-2500-1 and -2 and includes 100% of the weld length. Item No. C2.21, 4- - Category C-B, requires volumetric and surface examination of pressure-ra*=ining nozzle welds in Class 2 vessels. Applicable examination volume and area are shown in Fig. IWC-2500-4 and includes 100%

of the weld length. Item No. C3.30, Category C-C, requires surface examination ofpressure-retaining integrally welded attachments in Class 2 pumps. Item No. C6.10, Category C-G, requires surface examination of pressure-retaining welds in Class 2 pumps. The examination area is shown in Fig. IWC-2500-5 and IWC-2500-8 and includes 100% of the weld length. Actual examinations and their extent l 2 of coverage are listed in Attachment 1. (See RR-31).

J

- Basis for Relief i

Access limitations are due to geometric configuratica of the welded areas. Flanges and supports restrict

! coverage of required examination volume and areas. The actual restriction for each weld is shown in Attachment 1.

i 1 1

M1prnate Examination The maximum percentage possible of the required ultrasonic examination will be performed. The Code-required surface examination will be performed on the Boron Injection Tank. Also, the Code-required surface examination will be performed to the extent possible on the Safety Injection Pump. ,

I I

i 6-54 006 Rev. 7

l RR-30 ,

- (continued) -l 1

Attachsment 1 f

. Minimum l l

Code Item NwW '

j Description Examined Rgiricten Identification No. CatcaorY bio.

l i

. (REGENERATIVE HEAT EXCHANGER)

C1.30 Head toTube Sheet Weld 94 % 94% Code exam done from e . I1208-E6@l-W01 C-A head side ofweld -weldolet C1.30 Tube Sheet to ShellWeld 93 % 93*/. Code exam done from 11208-E6-001-WO2 C-A shell side ofweld -weldolet i

C-A C1.30 Tube Sheet to ShellWeld 93 % 93% Code exam done from 11208-E6-001-WO9 shell side ofweld - weldolet ,

C-A C1.30 Tube Sheet to Head Weld 94 % 94% Code exam done from 11208-E6-001-W10 head side ofweld -weldolet l

(EXCESS LETDOWN HEAT EXCHANGER) .

C-A C1.20 Unit Flange to Channel Head Weld .- 45 % 45% Code exam done from 11208-E6-002-W01 channel head side ofweld-4 mstnanentationlines interfere.

l (LETDOWN HEAT EXCHANGER)

C-A C1.20 VesselHead to Head Flange 29 % 29% Code exam done from 11208-E6-003-WO3 head side-Flange bolting interferes.

l (LETDOWN REHEATHEAT EXCHANGER)

C-A C1.10 VesselFlange to VesselShell 84 % 84% Code exam done from 11208-E6-007-WO3 head side-welded identification plate.

6-55 006 Rev. 7

- - _ - - _ _ - _ > - - - - -- -._--_- - - - _ . _- -- -,-w - < ..___r .- .

RR-30 ,

(continued) l Attachment 1 Minimum l Code Item Percentage Catemory F_g. Desenpuon Exanuned Restncuon Identification No.'

l (DISCHARGE PULSATION DAMPENER)

C1.10 Hemi-Head to Hemi-Head Weld 89 % SupportInterference 11208-V4-002-W01 C-A l

(BORON INJECTION TANK)

C-B C2.21 Nozzle to Head Weld 50 % 100% Exam from head side 11204-V6-001-W01

-0% from nozzle side C1.20 Head to Shell Weld 38% 76% exam from head side 11204-V6-001-WO2 C-A due to supports -0% from shellside due to taper Cl.20 Head to Shell Weld 50% ' 100% exam from head side -

! 11204-V6-001-WO3 C-A

' 0% from shell side due to j taper C2.21 Nozzle to Head Weld 50 % 100% cxam from head side-11204-V6-001-WO4 C-B 0% from nozzle side l

(SAFETYINJECTION PUMP)

C-G C6.10 Pump Casing to Sucuon Nozzle Weld 66 % Pump supports prevent 11204-P6-003-WO2 access to required area (CENTRIFUGAL CHARGING PUMP)

C3.30 Integrally Welded Pump Support Bracket 70 % Pump supports prevent 11208-P6-002-WO3 C-C access to required area C3.30 Integrally Welded Pump Support Bracket 70 % Pump supports prevent 11208-P6-002-WO5 C-C access to required area 6-56 006 Rev. 7 L-____-_-__________________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____ _ _ _ _ _ _ _ _ _ _ _ _ __

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VEGP-1 l

1 M  ;

Component or Relief Area Article IWF-5000 of ASME Section XI outlines the inservice test requirements for hydraulic and mechanical type snubbers.

Reauirement from which Reliefis Reauested The schedule for the testing of snubbers is described in Article IWF-5000. In addition,  ;

personnel performing these tests are to be qualified to both VT-3 and VT-4 visual l j

examination requirements. Reliefis requested from using Article IWF-5000 and qualified VT-4 visual examination personnel.

Basis for Relief ,

Instead of using Article IWF-5000, the on-going testing program per the pre-ITS (Improved Iechnical Specifications) Plant Technical Specifications will be performed.

The snubber testing requirements currently found in the VEGP Plant Technical l

Specifications are being relocated to a licensee-controlled document as allowed by the NRC Final Policy Statement on Technical Specification Improvements for Nuclear Power Reactors as noticed in the Federa! Register 58 FR 39132 dated July 22,1993. The i

snubber testing program for VEGP and its requirements remain unchanged even though l

the existing VEGP Plant Technical Specifications are being converted to the i Westinghouse Improved Standard Technical Specifications-style as issued by the NRC in l NUREG-1431 dated September 28,1992. Other than the location where the snubber testing program and its requirements are documented, e.g., the Updated Final Safety Analysis Report (UFSAR), Technical Requirements Manual, etc., the snubber testing l

program remains unchanged for VEGP, i.e., it is designed to demonstrate the functional l integrity of the snubbers and is, at least, equivalent to the requirements of Article IWF-5000.

l The functional testing of the snubbers will be performed by trained personnel using a detailed procedure. In addition, the required VT-3 examination will be performed using qualified personnel.

I l

t 6-82 006 Rev. 7

VEGP-1 RR-43 (continued)

Alternate Examination As noted above, the existing snubber testing program will continue to be performed regardless of where the program and its requirements are documented due to the conversion of the existing Plant Technical Specifications to the Improved Standard Technical Specifications-style. The Improved Technical Speci6 cations for VEGP are expected to go into effect in 1996 contingent upon NRC approval. Once the Improved Standard Technical Specifications-style ofPlant Technical Specifications are approved for VEGP, the snubber testing program and its requirements will be relocated to a licensee-controlled document such as the UFSAR, Technical Requirements Manual, etc.

Otherwise, the snubber testing program as currently performed remains unchanged.

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6-100 006 Rev. 7

,* VEGP-1

! RR-59 Component or Relief Area f All ASME Class 1,2, and 3 piping and components.  !

l  !

Recuirement From Which Reliefis Reauested Paragraph IWA-4400(a) of the 1983 Edition of ASME Section XI with Addenda through Summer 1983 requires that a system hydrostatic test be performed in accordance with IWA-5000 after a welded repair on a pressure-retaining boundary. Reliefis requested from performing this Code-required post-repair / replacement hydrostatic pressure test on Class 1,2, and 3 welds. Alternative exammations are proposed.

RMis for Relief Georgia Power Company (GPC) has determined that hydrostatically testing post-repair / installation welds represents a hardship with little benefit. Hardships are generally l

encountered with the performance of hydrostatic testing performed in accordance with the l

Code. For example, since hydrostatic test pressure would be higher than nominal j l i operating pressure, hydrostatic pressure testing frequently requires significant effort to set i

up and perform. The need to use special equipment and the need for individual valve lineups can cause the testing to impact maintenance / refueling outage schedules.

Piping components are designed for a number ofloadings that would be postulated to f

occur under the various modes of plant operation.Section XI hydrostatic testing only l

subjects the piping components to a small increase in pressure over the design pressure and, therefore, does not present a significant change to pressure boundary conditions.

Accordingly, hydrostatic pressure testing is primarily regarded as a means to enhance leakage detection during the examination of components under pressure, rather than solely as a measure to determine the structuralintegrity of the components.

i The ASME Subcommittee Working Group on Pressure Testing concluded that no additional benefit is gained by conducting the existing system hydrostatic tests in place of the alternate rules which require a leak test at nominal operating pressure. The conclusion of the group was that hydrostatic testing does not necessarily verify structuralintegrity and, in fact, the slightly higher test pressures currently called for in the Code could result in operational difficulties as well as extended outages and increased costs.

Industry experience has demonstrated that leaks are not discovered as a result of hydrostatic test pressures propagating a pre-existing flaw through-wall. This experience 6-101 006 Rev. 7

. VEGP-1 RR-59 (continued)

Baain for Relief (continued) indicates that leaks in most cases are being found when the system is at normal operating pressure. This is mainly due to the fact that hydrostatic pressure testing is infrequently performed, while system leakage tests at normal operating pressures are conducted a minimum of once each maintenance / refueling outage for Class 1 systems, and each 40-month inspection period for Class 2 and 3 systems. In addition, leaks may be identified during system walkdowns by plant operators.

I Georgia Power Company has determined that the nondestructive examinations and their j associated acceptance criteria provide assurance of the structural integrity of the weld.

The proposed alternative examinations will provide reasonable assurance that unallowable flaws are not present in the subject welds. Consequently, an acceptable level of quality and safety will be achieved and public health and safety will not be endangered by allowing the proposed alternative examination in lieu of the Code requirement.

Alternative Examinations Georgia Power Company proposes to perform alternative examinations delineated in ASME Code Case N-416-1, with augmented exams for Class 3 piping and components, in lieu of Code-required hydrostatic tests. These alternative examinations are as follows:

1. Perform nondestructive examinations in accordance with the methods and acceptance criteria of the applicable subsection of the 1992 Edition of ASME,Section III.

2. Perform a VT-2 visual examination of the welds in conjunction with the system i

leakage test using the 1992 Edition of ASME Section XI.

3. Perform surface examinations on the root pass layer of butt and socket welds on the pressure-retaining boundary of Class 3 piping and components.

4. The nondestructive examinations and pressure tests shall be documented on an Owner's Report for Repairs or Replacements, Form NIS-2.

6-102 006 Rev. 7 1

VEGP-1 .

BB-f2 (continued)

Imnlementation Schedule 4

Because of the benefits which can be derived from the use of ASME Code Case N-416-1, with augmented examinations as delineated above, GPC wishes to implement this relief request immediately. The actions, i.e., alternative examinations, proposed by GPC are consistent with those required ofBeaver Valley as approved by the NRC. Because immediate use of Relief Request RR-59 is desired, GPC requests that the NRC grant interim approval of RR-59 pending its full review and approval of this relief request.

i 6-103 006 Rev. 7

, 1 l

t. - - - - .-. . . - . . .--._ __

s VEGP-1 l Ba.a Comoonent or Relief Area 2

Class 1,2, and 3 systems subject to hydrostatic testing.

Reauiramant From Which Reliefis Reauested Tables IWB-2500-1, IWC-2500-1, and IWD-2500-1 of the 1983 Edition of ASME Section XI with Addenda through Summer 1983 require system hydrostatic and leakage testing as shown below. The Code requires system hydrostatic testing once per 10-year interval at or near the end of the interval.

ASME Examination Category B-E, Item B4.11, B4.12, B4.13 and B4.20, ASME Examination Category B-P, Item B15.11, B15.21, B15.31, B15.51, B15.61 and B15.71, ASME Examination Category C-H, Item C7.20, C7.40, C7.60 and C7.80, j

! ASME Examination Category D-A, Item DI.10, l

! ASME Examinktion Categcry D-B, Item D2.10, and i

i ASME Examination Category D-C, Item D3.10.

! Reliefis requested from perfonning the Code-required hydrostatic tests. Alternative

examinations are proposed.

[ Basis for Relief i

Georgia Power Company (GPC) has determined that hydrostatic tests represent a hardship i

with little benefit. Hardships are generally encountered with the performance of j: hydrostatic testing performed in accordance with the Code. For example, since

! hydrostatic test pressure would be higher than nominal operating pressure, hydrostatic pressure testing frequently requires significant effort to set up and perform. The need to l

use special equipment and the need for individual valve lineups can cause the testing to

. impact maintenance / refueling outage schedules.

Piping components are designed for a number ofloadings postulated to occur under the l.

various modes of plant operation.Section XI hydrostatic testing only subjects the piping

! components to a small increase in pressure over the design pressure and, therefore, does l

6-104 006 Rev. 7 L

m , , _ _ _ _ _ , _,_ ,

gmg. g,., , ,,

e VEGP-1 anda i

I (continued) l Basis for ReEef(continued) 9 not present a significant change to pressure boundary conditions. Accordingly, j hydrostatic pressure testing is primadly regarded as a means to enhance leakage detection i during the examination of components under pressure, rather than as a measure to j . determine the structural integrity of the components.

1 i

The ASME Subcommittee Working Group on Pressure Testing concluded that no

additional benefit is gained by conducting the existing system hydrostatic tests in place of the alternate rules which require a leak test at nominal operating pressure. The conclusion

. of the group was that Section XI hydrostatic testing does not verify structural integrity

i. and, in fact, the slightly higher test pressures currently called for in the Code could result in operational difficulties as well as extended maintenance / refueling outages and increased costs, i

Industry experience has demonstrated that leaks are not discovered as a result of l

. hydrostatic test pressures propagating a preexisting flaw through wall. This experience indicates that leaks in most cases are being found when the system is at normal operating pressure. This is largely due to the fact that hydrostatic pressure testing ism' frequently performed while system leakage tests at nominal operating pressures are conducted a j minimum of once each refueling outage for Class I systems, and each 40-month inspetior, 4

period for Class 2 and 3 systems. In addition, leaks may be identified during system walkdowns by plant operators.

i

! The use of Code Case N-498, " Alternative Rules for 10-Year System Hydrostatic Testing

- for Class 1 and 2 Systems", was previously approved by the NRC in Regulatory Guide 1.147, Revision 11. The alternative rules for Code Class 1 and 2 in Code Case N-498-1 are unchanged from N-498. Code Case N-498-1 added an alternative to the 10-year system hydrostatic tests required for Class 3 Systems by Table IWD 2500-1, Categories D-A, D-B, or D-C to the Class 1 and 2 alternatives included in Code Case N-498. Code Case N-498 was found to be acceptable because the alternative provided adequate assurance and because compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety.

Georgia Power Company has determined that the alternative rules of ASME Code Case N-498-1 provide reasonable assurance of the structurN integrity of the Code system.

Consequently, an acceptable level of que.lity and safety will be achieved and public health and safety will be maintained by allowing the proposed alternative examination as an option to the Code requirement.

6-105 006 Rev. 7

, VEGP-1 RR-60 (continued)

D Alternative Examinations i

Georgia Power Company proposes to perform an alternative examination delineated in Code Case N-498-1 as an option to performing Code-required hydrostatic tests. Code Case N-498-1 requires that a VT-2 visual examination be performed in conjunction with system pressure test at nominal operating pressure.

Imolementation Schedule Because of the benefits which can be derived from the use of ASME Code Case N-498-1, GPC wishes to implement this relief request immediately. The actions, i.e., alternative exeminations, proposed by GPC are consistent with those required of the Beaver Valley and Farley plants as approved by the NRC. Because immediate use of Relief Request RR-60 is desired, GPC requests that the NRC grant interim approval of RR-60 pending full review and approval of this relief request.

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g. . .__ ._ . ._ . . . . . . . . _ _ _ _ _ _ _ _ _ _ _ _ ._.. _ _

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. C' i/ 0 VEGP-1  !

l Comoonents or Relief Area ,

1 I

All ASME Class 1,2, and 3 Integrally Welded Attachments included within the scope

[

j of the ISI Program. Speci6cally, these include the following:

. ASME Examination Category B-H, Items B8.10 and B8.20 for Vessels, I ASME Eramination Category C-C, Items C3.10, C3.20 and C3.30 for ,

i Vessels, Piping, and Pumps, . >

l, ASME Evamination Category D-A, Items D1.20, D1.30 and DI.40 for l

Systems In Support Of Reactor Shutdown, I

j ASME Examination Category D-B, Itc.ns D2.20, D2.30 and D2.40 for

Systems In Support Of ECC, CHR, Atmosphere Cleanup, and Reactor RHR, and l

W ASME Examination Category D-C, Item D3.20 for Systems In Support OfRHR and SF Storage Pool.

Requirement From Which Reliefis Requested Table IWB-2500-1, Examination Category B-H, Items B8.10 and B8.20 in the 1983 Edition ,

of ASME Section XI with Addenda through Summer 1983 require a voinmetric or surface examination of the integrally welded attachments that meet certain conditions as noted in the subject table. Table IWC-2500-1, Examination Category C-C, Items C3.10, C3.20 and C3.30 of that same Code edition / addenda require a surface examination of the integrally welded attachments that meet certain conditions as noted in the subject table. Table IWD-2500-1, Examination Category D-A, Items D1.20, DI.30, D1.40; Examination Category D-B, Items D2.20, D2.30, D2.40; and Examination Category D-C, Item D3.20 of that same Code edition / addenda require a visual examination of the integrally welded attachments that meet certain conditions as noted in the subject table.

Reliefis requested from performing the Code-requi ed volumetric, surface, or visual examination on those Integral Attachments required by the above referenced tables.

r B==ic for Relief On November 25,1992, ASME issued Code Case N-509 which approved a set of alternative

~

rules for the selection and examination of Class 1,2 and 3 Integrally Welded Attachments, '

Section XI, Division 1. The Code Case provides an alternative sampling which will retain i

6-107 006 Rev. 7 l

m 1

,[ VEGP-1  !

M l (cantinuedl Basis for Relief (continued) an acceptable level of quality and safety for Class 1,2, and 3 integrally welded attachments.

Since approval was granted by ASME, the alternative requirements should be technically rocceptable for determining flaws. By implementing the alternative examinations, cost savings, personnel radiation dose, and outage time can be realized by Georgia Power Company (GPC)  !

at Vogtle Electric Generating Plant, Unit 1. A VEGP-1 study was performed by Southern Nuclear Operating Company (SNC) on behalf of GPC that compared the number ofintegrally  ;

~

welded attachment examinations required under the present ASME Section XI scope versus the number ofintegrally welded attachment examinations required under ASME Code Case N-509. That study is shovm in Attachrnent I to this relief request and shows that at least 10%

of the present ASME Section XI integrally welded attachment scope for piping will be ,

examined when the subjet code case is implemented.

l Alternative Examinations ,

Georgia Power Company proposes that the following examinations be performed in lieu of the Code-required volumetric, surface, or visual examination on those integrally welded  !

i attachments required by Table IWB-2500-1, IWC-2500-1, or IWD-2500-1 in the 1983 Edition, Summer 1983 Addenda of ASME Section XI:

. Surface Examinations:

Those integrally welded attachments as specifically noted in ASME Code Case N-509, ASME Examination Category B-K, Integral Attachments for Class 1 Vessels, Piping, Pumps, l l

and Valves, and ASME Examination Category C-C, Integral Attachments for Class 2 Vessels, Piping, Pumps, and Valves.  ;

l Visual Examinations:  ;

ASME Examination Category D-A, Integral Attachments for Class 3 Vessels, Piping, Pumps, and Valves.

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6-108 006 Rev. 7 l

. VEGP-1 i

)

4 BB-fl l (continued)

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Attachment 1 VOGTLE ELECTRIC GENERATING PLANT ASME CODE CASE N-509 STUDY l UNIT 1 Integrally Welded Attachment Examinations Recuired For Pioinn Class 1 Qagl Class 3 191al Present Scope 0 103 329 432 N-509 Scope 0 9 37 di Exams Saved 0 94 292 386 NOTES

1. ASME Code Case N-509 was approved on November 25,1992 but has not yet been included in NRC Regulatory Guide 1.147.

l

2. Class 1,2, and 3 component supports shall be selected for examination in accordance with IWF of the 1989 Edition w/1990 Addenda of Section XI to the ASME Boiler and Pressure Vessel Code.

3. The 1989 Edition w/1990 Addenda of Section XI to the ASME Boiler and Pressure l Vessel Code is essentially ASME Code Case N-491 contained in NRC Regulatory Guide 1.147, Revision 10.

4. Except for selection of component supr.cas for examination, all references to ASME Section XI within the code case shall be from the edition and addenda specified in the owners ISI program.

5. Table 2500-1 in ASME Code Case N-509 uses Examination Category B-K for Class 1 integrally welded attachments in place of Examination Categories B-H and B-K-1 ofIWB and Examination Category C-C for Class 2 integrally welded attachments in the place of Examination Category C-C ofIWC. It also uses Examination Category D-A for Class 3 integrally welded attachments in the piace of Examination Categories D-A, D-B, and D-C ofIWD.

, 6. The base metal design thickness exemption is lost for Class 1 and 2 integrally welded attachments. l 6-109 006 Rev. 7 f

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4 VEGP-1 BB:S Comoonent or Relief Area t Reliefis requested from the surface and volumetric examination requirements ofvessels and their connections in piping 4" nominal pipe size (NPS) and smaller in systems other than Residual Heat Removal (RHR), Emergency Core Cooling (ECC), and Containment Heat Removal (CHR) systems or portions thereof. Specifically, the following components are involved:

Regenerative Heat Exchanger (Tag No.1-1208-E6-001)

Excess Letdown Heat Exchanger (Tag No.1-1208-E6-002)

Letdown Het Exchanger (Tag No.1-1208-E6-003) I Letdown Reheat Heat Exchanger (Tag. No.1-1208-E6-007) r Discharge Dampener (Tag No.1-1208-V4-002)

Reauirement from whig _h Reliefis Requested Reliefis requested to exclude the components cited above from the surface and volumetric  ;

examinations as required by Table IWC-2500-1, Examination Category C-A (Items C1.10, C1.20, and C1.30) and Examination Category C-C (Item C3.10) as allowed in IWC-1220,

" Components Exempt From Examination", in the 1989 Edition,1989 Addenda through the  ;

1992 Edition of ASME Section XI. l l

l Basis for Relief j

Subarticle IWC-1220 of the 1989 Addenda of ASME Section XI allowed the exemption of i selected components from the surface and volumetric examination requirements ofIWC-1220.

! The 1992 Edition of ASME Section XI also includes these exemptions in IWC-1220. These

! exemptions will be allowed when the newer Addenda and Editions of the Code are authorized j in 10CFR50.55a. Georgia Power Company (GPC) sees no benefit in performing examinations l_

on components which the Code has determined can be exempted. The other requirements in the Code are therefore acceptable to assure an acceptable level of safety or quality. It is l

j hnpractical to perform examinations which do not provide a compensating increase in the level i

of safety or quality, i

These added exemptions would apply to several coraponents which are in high dose rate

- areas. The most significant of these components is the regenerative heat exchanger. A conservative whole body dose in the range of one to two Rem is a reasonable estimate for l

examining the regenerative heat exchanger. The dose rate surveys for the regenerative heat l l

exchanger indicate a contact dose rate of two to three Rem / hour and a dose rate at l l

6-110 006 Rev. 7 l

4 k

r I r

l VEGP-1 BB:S (continued)

B==le for Relief (continued) eighteen inches away from the heat exchanger of one to one-and-one-half (1 to 1-1/2)

Rem / hour. The estimated stay time to perform the Code-required examinations on the regenerative heat exchanger is one hour. Such exposure is contrary to the principles of ALARA to perform examinations on components without a compaa==+ing increase in the level .

of safety or quality. For the reasons diw=W above, GPC has determined that implementation of the Code requirements is impractical.

Alternate Examination These exemptions exclude the applicable vessels from the surface and volumetric examinatiora required by IWC-2500. The remainder of the Code-required examinations (i.e., pressure tests) would be performed to assure that an acceptable level of safety and quality is maintained for the applicable components.

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1 6-111 006 Rev. 7 e

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