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Forward Revs 1 & 2 to Inservice Insp Program ISI-P-014.Rev 1 Adds New Relief Requests Re Hydrostatic Testing of Piping, Components & Connections.Rev 2 Changes Existing Relief Requests Re RHR HXs to Address Nozzle Inner Radii
	ML20247B862
Person / Time
Site:	Vogtle
Issue date:	08/21/1989
From:	Hairston W; GEORGIA POWER CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	MSV-00080, MSV-80, NUDOCS 8909130168
	Download: ML20247B862 (27)
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U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.

20555 V0GTLE ELECTRIC GENERATING PLANT - UNIT 2 NRC DOCKET 50-425 OPERATING LICENSE NPF-81 REVISIOWS 1 & 2 TO INSERVICE INSPECTION PROGRAM Gentlemen:

In accordann with the requirements of. Technical Specification 4.0.5 concerning. surveillance requirements, Georgia Power Company (GPC) submits for NRC review and approval five copies of Revisions 1 and 2 of the Vogtle Electric Generating Plant Unit 2 Inservice Inspection (ISI)

Program, ISI-P-014.

The ISI program currently in effect was written to the requirements of the 1983 Edition of the ASME Section XI Code with Addenda through Summer 1983.

Enclosures 1 and 2 provided herein concern Revisions 1 and 2,

respectively.

The enclosed documents supercede portions of.the ISI program document previously submitted to the NRC.

A summary of the changes resulting from each of the revisions is provided in the enclosures and precedes the af fected documents.

The Revision 1 changes to the ISI program include the addition of three new relief requests, RR-54, RR-55, and RR-56 and other miscellaneous changes.

The first relief request, RR-54, concerns the hydrostatic testing of piping, components, and their connections less than or equal to 1 inch diameter.

The requested relief would allow the hydrostatic testing and visual examination of

piping, components, and their connections less than or equal to 1 inch diameter to be performed only on those components, etc., which are nonisolable from large diameter piping requiring hydrostatic testing.

Further, Relief Request RR-54 would allow piping, components, and their connections less than or equa'. tc 1 inch diameter which are isolable from other system hydrostatic test boundaries to be visually examined during a system leakage test, system functional test, or system inservice test in lieu of performing a hydrostatic test.

The second relief request, RR-55, concerns the ultrasonic examination of pressurizer safety relief valve piping welds which have been weld overlaid on the outside diameter of the weids and would allow scanning of I

the piping at the primary reference level versus at least twice the primary level as required by the ASME Section XI Code.

Scanning of the pressurizer safety relief valve piping at least twice the primary reference level is not possible due to the excessive noise associated 1

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wi th the Rtallurgical structure of the weld overlays.

The third relief request, RR-56, concerns the visual examination of several inaccessible ASME Code Class 3 integrally welded attachments and their component supports in the Auxiliary Feedwater System.

Relief from the examination

. requirements would be allowed by RR-56 since the affected attachments and their supports are inaccessible due to their location.

Neither direct or remote visual examination is practical.

Finally, Revision 1 also includes revisions to Relief Request RR-12, RR-15, and RR-26 which were made primarily due to editorial changes.

The Revision 2 changes to the ISI program include the revision of two existing relief requests, RR-32 and RR-52.

The fi rst relief request, RR-32, concerns the Residual Heat Removal System heat exchangers.

The relief request was revised to address nozzle inner radi.i of the subject component as it pertains to Vogtle Electric Generating Plant Unit 2.

Nozzle inner radii, as depicted in Figure IWC-2500-4 in the ASME Section XI Code, do not exist for the heat exchangers utilized on that particular unit; consequently, no examination can be performed.

The second relief request, RR-52, concerns the surface examination of the liftir.g lug welds on the reactor pressure vessel closure head.

Only a limited examination, of' those welds can be performed due to physical limitations created by the Control Rod Drive support braces.

The relief request was revised primarily to provide a clarification to the " Al ternate Examination" statement.

Georgia Power Company has determined that conformance with certain requirements of the ASME Code,Section XI, is impractical and, in accordance with 10 CFR 50.55a(g)(5)(iii), hereby notifies the. NRC of that determination.

The NRC is requested to review and approve the enclosed j

ISI program changes.

Approval of the enclosed relief requests and other program changes will not endanger life or property or the common defense and security and is otherwise in the public interest given due consideration to the burden upon GPC that could result should the Code requirements be imposed.

Approval of the enclosed ISI program is requested by November 3, 1989.

Should there be any questions, please contact this office.

Sincerely, td.

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W. G. Hairston, III j

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MSV-00080 Page 3 L

' August 21, 1989

Enclosures:

1.

Summary of Changes and Revision 1 to Vogtle Electric Generating. Plant Unit 2 ISI Program, ISI-P-014.

"J.

2.

Summary of Changes and Revision 2 -to Vogtle Electric Generating Plant Unit 2 ISI Program, ISI-P-014.

xc: Georgia Power Capany Mr. C. - K. McCoy Mr. G. Bockhold, Jr.

Mr. P. D. Rushton Mr. - L. A. Ward NORMS =

U. S. Nuclear Regulatory Commission Mr. 5. D..Ebneter,. Regional Administrator Mr. J. B. Hopkins, Licensing Project Manager, NRR (2 copies)

Mr. J. F. Rogge, Senior Resident Inspector, Vogtle

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prp ENCLOSURE 1 i

V0GTLE' ELECTRIC GENERATING PLANT UNIT 2 INSERVICE INSPECTION PROGRAM ISI-P-014 Revision 1 Summary of Changes Revision 1 consists of the addition of three relief requests, RR-54, RR-55, and RR-56, and other miscellaneous ' changes.

A summary of the changes resulting from Revision 1 and the affected page numbers in-document ISI-P-014 are provided below:

Relief Request RR-54 Relief from system hydrostatic test' requirements on (a) piping less than or equal to

-1" nominal pipe size (NPS) and (bs components and their connections less than or equal to 1" NPS is sought by Relief. Request RR-54.

Pages 2-33, 2-34, 3-16, 3-17, 4-2, 4-4, 4-6, 6-4, and 6-99 were revised to reflect these changes.

Relief Request RR-55 Relief Request RR-55 discusses the ultrasonic examination of

selected 6-inch pressurizer safety relief valve piping welds.

Scanning was possible only at tne primary refercnce level due to excessive noise associated with the. metallurgical structure of the weld overlays.

This limitation was previously discussed in the Vogtle Electric Generating Plant Unit 2 Preservice Inspection (PSI) Program (ISI-P-010) as Relief Request RR-19.

Pages 2-23, 6-4, and 6-100 were revised to reflect this change.

Relief Request RR-56 Relief Request RR-56 discusses the physical limitations involved in performing the visual examination of selected Class 3 Auxiliary Feedwater System integrally welded attachments and component supports.

These limitations were previously discussed in the PSI Program as Relief Request RR-47.

Pages 4-2, 5-4, 6-4, and 6-101 were revised to reflect these changes.

Miscellaneous Changes Weld number 21201-V6-002-WOO 3, an upper middle shell-to-lower middle shell weld in the pressurizer, has been deleted from to Relief Request RR-12. The subject weld was El-1 0

J

,,g' ENCLOSURE l-(Continued)

Revision 1 Summary of Changes i

examined during the PSI,

but, no ASME Section XI Code requirement.-exists for inservice inspection since it is not a shell-to-head weld..Page 6-19 was revised to reflect this c ha nge. -.

Re'ief Request RR-15 was revised to correct the examination identification number.

Page 6-23 was revised to reflect this

' change.

' to Relief Request RR-26 was revised to correct an examination identification number.

Page 6-46 was revised to reflect this change.

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attachments RR-53 Class 3 hydrostatic test on Spent Fuel Cooling & Purification RR-54

' System hydrostatic testing'on 1" NPS and smaller piping and. components RR-55 Pressurizer Safety Relief Valve' Piping.

RR-56 Auxiliary Feedwater Integrally. Welded Attachments and Associated Component Supports 1

6-4 014 Rev. 1 L____--___.-

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Component or Relief' Area-

Volumetric examination of inner radius section of the pressurizer-surge nozzle-l

. Examination I.D. no.

21201-V6-002-IR-06 4

' Requirement from which' Relief is Requested-

' Item No. B3.120, Category B-D, Table IWB-2500-1 of ASME Section XI J

requires a: volumetric examination offpressurizer nozzle inside radius section.- The: applicable' examination volumes are shown in Fig. IWB-2500-7(b).

Relief'from this examination is requested.

Basis for Relief

.The' geometry of the nozzle barrel prohibits an ultrasonic scan-from the nozzle side..The heater well couplings prohibit the scan

-from'the vessel head side.: -An inner radius section examination of

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this cozzle will, therefore, not be possible.

Alte.tnate Examination-None i

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r VEGP-2 RR-54 Component or Relief Area Relief is requested from performing system hydrostatic testing on (a) piping 5 1" nominal pipe size (NPS) and (b) components and their connections in piping i 1" NPS.

Requirement from which Relief is Requested The'following portions of the Code require system hydrostatic testing on all sizes of pressure retaining components.

- Table IWB-2500-1, Examination Category B-P

- Table IWC-2500-1, Examination Category C-H

- Table IWD-2500-1, Examination Category D-A, Item No. D1.10

- Table IWD-2500-1, Examination Category D-B, Item No. D2.10

- Table IWD-2500-1, Examination Category D-C, Item No. D3.10 Basis for Relief Specific system hydrostatic testing on (a) piping '< 1" NPS and (b) components and their connections in piping < l NPS is impractical. Typically, piping and components of this small diameter are used for sampling systems, reactor pressure v4.ssel head vent systems, excess letdown-systems, and for instruhanta-tion applications.'The systems mentioned are seldom operated, and as such, degradation is expected to be negligible. Piping and components used for instrumentation applications (i.e., pressure.

j indicators, flow indicators) are subjected essentially to no flow conditions, and as such, failure mechanisms which cause degrada-tion are minimal.

Component pressure boundary integrity can be verified by performing VT-2 examinations during system leakage test, system functional test or system inservice test conditions.

Alternate Examinations System hydrostatic testing and the accompanying VT-2 examination will be performed on (a) piping ~< 1" NPS and (b) components and their connections.in piping $ 1" NPS which are unisolatable from larger diameter piping which raquire hydrostatic testing. A VT-2 examination will be performed during system leakage test, system function test, or system inservice test on (a) piping < 1" NPS and (b) components and their connections in piping i l' NPS which are isolatable from other system hydrostatic test boundaries.

6-99 014 Rev. 1 i

VEGP-2 RR-55 Component or Relief Area Volumetric examination of pressure retaining welds in the 6-inch Pressurizer Safety Relief Valve (PSRV) piping with OD weld overlays.

Requirement from which Relief is Recuested ASME Code Section XI, Appendix III, Article 111-2430 requires that manual scarting shall be done at twice (46dB) the primary reference level as a minimum.

Basis for Eyemotiqn Due to the overlaid condition of selected 6-inch PSRV piping, a meaningful ultrasonic examination could not be performed from the weld build-up using conventional ultrasonic shear wave techniques. A better technique was developed using a dual-element focused transducer, utilizing a refracted longitudinal wave with a frequency of 1.5 MHz. The calibration block was constructed with a welded overlay representative of the existing field conditions. The Distance Amplitude Correction (DAC) Curve was established using side-drilled holes and the ID notch was used to establish sensitivity. Scanning was possible only at the primary reference level due to excessive noise associated with the metallurgical structure of the material.

A demonstration of this technique was performed during the PSI in accordance with IWA-2240 and found to be equivalent to the specified i

method.

Alternate Examination Scanning will be performed only at the primary reference level using an examination technique equivalent or similar to that utilized during the Preservice Inspection.

~.

6-100 014 Rev. I

B,,.T

VEGP-2 y

RR-56 Component or Relief Area Visual VT-3 examination of inaccessible Class 3 integrally welded attachments and their component sugy)rts on the Auxiliary Feedwater System; Examination ID Numbers:

2-1302-Oll-H015 2-1302-013-H009 2-1302-018-E009 2-1302-020-B015 Requirement From Which Relief is Requested i

Item No. D1.20, Examination Category D-A, Table IWD-2500-1, of ASME Section XI requires a visual VT-3 examination of integral attachments.. Item No..F2.10 Examination Category F-B, Table.

IWF-2500-1 requires a visual VT-3 examination of.the component supports.. Relief is requested from these requirements for the examination. numbers listad above.

Basis for Relief The above listed component supports are located in piping tunnels that have minimum access clearances.

Inspection personnel cannot perform a direct visual examination. Remote inspection capabilities cannot be used due to insulation'en the components 1and lack of surface preparation.

The remaining integrally welded attachments on these lines, along with the required component supports, have been inspected without evidence of any unacceptable condition.

~100% of the integrally welded attachments on line numbers 1302-019-and 1302-021 have been inspected with acceptable results. 'These lines are similar in design, function and service as lines 1302-011, 1302-013, 1302-018 and 1302-020.

Construction Code requirements ensure the structural edcquacy of these supports.

The Section III examination results were documented in the VEGP-2 PSI Final Report.

Alternate Examination None 6-101 014 Rev. 1

f,.

'* w ENCLOSURE 2 V0GTLE ELECTRIC GENERATING PLANT UNIT 2.

INSERVICE INSPECTION PROGRAM ISI-P-014 Revision 2 Summary of Changes Revision 2 consists of the revision of two relief requests, RR-32 and RR-52.

A summary of the changes resul ting from Revision 2 and the affected page numbers in document ISI-P-014 are provided below:

Relief Request RR-32 Relief Request RR-32 was revised to address nozzle inner radii as they pertain to the Residual Heat Removal heat exchangers at Vogtle Electric Generating Plant Unit 2.

Nozzle inner radii, as depicted in Figure IWC-2500-4 in the ASME Section XI Code, do not exist for those particular heat exchangers.

Pages 3-4, 6-59, and 6-60 were revised to reflect the changes.

A continuation page, 6-59a, has been added to the subject relief request.

Relief Request RR-52 i

Relief Request RR-52 was revised primarily to provide clarification to the " Al ternate Examination" statement.

A i

limited surface examination of the reactor pressure vessel cicsure head lifting lugs can only be performed due to physical limitations created by the geometric configuration and location of the Control Rod Drive support braces.

Page 6-96 was revised j

to reflect the necessary changes.-

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T' VEGP-2 RR-32 Component or Relief Area Examination of (1) the nozzle inner radii and (2) the reinforcing plate-to-vessel welds of the Residual Heat Removal heat exchangers (Class 2).

l Examination I.D. nos. - 21205-E6-002-IR01 21205-E6-002-IR02 21205-E6-002-WO9 21205-E6-002-W10 Requirement From Which Relief Is Requested (1) Item No. C2.22, Category C-B, Table IWC-2500-1 of ASME Section XI requires a volumetric examination of the inner radius section of pressure retaining nozzles (greater than 12-inch nominal' pipe size) in vessels with nominal wall thickness greater than 1/2-inch.

(2) Item No. C2.31, Category C-B, Table IWC-2500-1 requires a surface examination of the reinforcing plate-to-vessel welds in vessels greater than 1/2 inch nominal wall thickness.

Kslief is requested from the above examination requirements.

Basis'for Relief (1) Figure no. IWC-2500-4 of ASME Section XI which constitutes the examination requirement for Examination I. D. Nos. 21205-E6-002-IR01 & 21205-E6-002-IR02 does not illustrate the nozzle design of the VEGP-2 RHR Heat Exchangers. The configuration of the nozzles at VEGP-2 differs from the configuration depicted in the

[

Code figure. The VEGP-2 configuration has a sharp inner corner instead of the usual smooth, rounded configuration. The attached figure-depicts the configuration at VEGP-2. Also, there is a reinforcing metal plate welded behind the inner corners. There-fore, it is impractical to perform an inner radius ultrasonic examination on Examination I. D. Nos. 21205-E6-002-IR01 and 21205-E6-002-IR02 due to the lack of nozzle inner radii.

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1 VEGP-2 RR-32 Basis for Relief (cont'd)

(2) Figure No. IWC-2500-4(c) of ASME Section XI which constitutes the examination requirement for Examination I.D. Nos. 21205-E6-002-WO9 & 21205-E6-002-W10 does not illustrate the reinforcing plate-to-vessel design of the VEGP-2 RHR Heat Exchangers. Refer to the attached figure for the VEGP-2 configuration. The rein-forcing plate at VEGP-2 is welded to the inside diameter of the heat exchanger wall with no nozzle-to-reinforcing plate contact (welds). The reinforcing plate-to-vessel welds are inaccessible.

Therefore, it is impractical to perform a surface examination on the reinforcing plate-to-vessel welds 21205-E6-002-WO9 and 21205-E6-002-W10 due to their inaccessibility.

For the reasons discussed above, GPC has determined that implemen-tation of the Code requirements is impractical. Accordingly, relief from the Code requirements is sought from the NRC as allowed by 10CFR50.55a (g)(5)(iii).

Alternate Examination in Lieu of ASME Section XI Requirements (1) As discussed above, due to the lack of nozzle inner radii, no examination can be performed for Examination I.D. Nos. 21205-E6-002-IR01.and 21205-E6-002-IR02 for the VEGP-2 RER Heat Exchangers. Those examination areas are to be deleted from the inservice inspection plan document since the nozzle inner radii do not exist.

(2) Due to their inaccessibility, no surface examination of the reinforcing plate-to-vessel welds 21205-E6-002-WO9 and 21205-E6-002-W10 can be performed. No alternate examination, e.g.,

volumetric examination, can be performed or is proposed due to the configuration involved. The interface between the rein-forcing plate and the RHR heat exchanger vessel wall precludes an adequate volumetric examination from being performed for the aforementioned welds. No compensating increase in the level of quality and safety would be realized should an alternate exami-

nation, e.g.,

volumetric examination, be performed.

1 6-59a 014 Rev. 2

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VEGP-2 RR '

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. Component or' Relief Area-

.SurfaceLexamination:of Integrally. Welded Attachments on-the Reactor

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- Vesse1~ Closure Head, o.. ;

. cI

Examination: ID'No.

.21201-V6-001-W204 21201-V6-001-W205 21201-V6-001-W206 j

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. Requirement from which Relief-is Requested

. Item No..BB.10) Category B-H, Table IWB-2500-1 of'ASME Section XI

requires a' surface examination of integrally welded-attachments on the. reactor; vessel. Applicable examination area is shown in Figure

IWB-2500-15.

l Basis for Relief'

Geometric configuration and location of the CRD support braces.

. presents physical limitations that prevent complete coverage of.

.the RPV Closure Head lifting lugs required for the surface examination..

For the reasons described above, GPC has determined that implemen-

~

tation of the. code requirements is impractical. Accordingly, relief from>the Code requirements is sought from the NRC as allowed by

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10CFR50.55a-(g)(5)(iii).

Alternate Examination DueLto physical limitations discussed above, approximately 50%

of.the weld length of the RPV Closure Head lifting lugs will be. examined as during the Preservice Inspection.

6-96 014 Rev. 2

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Enclosures:

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