Text

Rev 1 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Units 1 & 2
	ML20209H409
Person / Time
Site:	Vogtle
Issue date:	02/15/1999
From:	; SOUTHERN NUCLEAR OPERATING CO.
To:	;
Shared Package
ML20209H392	List: ML20209H388; ML20209H395; ML20209H409;
References
	NUDOCS 9907200215
	Download: ML20209H409 (65)
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r-SOUTHERN NUCLEAR OPERATING COMPANY INSERVICEINSPECTION PROGRAM SECOND 10-YEAR INTERVAL VOGTLE ELECTRIC GENERATING PLANT UNITS 1 AND 2 d

SNC - GENERAL OFFICE SNC - VOGTLE PLANT PREP'D REV'D APPV.

APPV.

APFV.

BY BY BY VOGTLE MGR.

PLANT REV DATE DESCIUPTION (ITS)

(ITS)

PROJECT ENGRG GEN.

(NMS)

SUPP.

MGR.

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5/9/97 BASICISSUE MB JAE/HPW JBB 9"A*pIr#Nd 1

2/15/99 Withdrew RR-3, RR-3, RR-13, o

RR-15. Revised RR-4, P R-7 RR-LCV-1016-J 10, RR-11, RR-12, RR-g 16, RR 22. See Summr Changes.

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O Multiple preparers and reviewers. Preparation / review sheets on file.

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l VEGP-1 AND 2 INSERVICE INSPECTION PROGRAM Summary of Changes Revision 1

1. Updated the Class I and Class 2 Tables to reflect current Relief Requests.

l

2. Revised the following Relief Requests:

l RR-4 RR-11 RR-16 l

RR-7 RR RR-22 RR-10 RR-14 i

l

3. The following Relief Requests were withdrawn:

)

RR-3 RR-13 l

RR-8 RR-15

)

l 1

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l' 1

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vprgsoc. doc Page1 ofI' l

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VEGP-1 AND VEGP-2 INSERVICE INSPECTION PROGRAM DISTRIBUTION LIST MANUAL HOLD'P MANUAL NUMBER 2

. Authorized Nuclear Inservice Inspector, ANII 1

J. J. Churchwell 2

D. R. Cordes 3

W. H. Cole 4

l ITS ShelfCopy 5

ITS Shelf Copy 6

Manager, SNC Vogtle Project Nuclear Maintenance and Support 7

Manager, SCS Vogtle Project Support 8

Supervisor, SNC Document Control, VEGP 9

l Supervisor, SNC Engineering Support

("erformance Group), VEGP 10 Functional Maintenance Team Leader, SNC VEGP 11 i

i distlst. doc Page1of1 Rev.1

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r VEGP-1 AND VEGP-2 INSERVICE INSPECTION PROGRAM LIST OF EFFECTIVE PAGES Distibution List Revision 1 Class 3:

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SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 SECOND TEN-YEAR INTERVAL REQUEST FOR RELIEF NO. RR-3 Request for Relief Withdrawn l

4 7-11 Rev. I

SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 SECOND TEN-YEAR INTERVAL REQUEST FOR RELIEF NO. RR-3 (continued)

This page intentionally left blank l

l 7-12 Rev.I

i1-SOUTIIERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 SECOND TEN-YEAR INTERVAL REQUEST FOR RELIEF NO. RR-3 (continued) l This page intentionally left blank l

7-13 Rev. I

SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 SECOND TEN-YEAR INTERVAL l

REQUEST FOR RELIEF NO. RR-3 (continued) i This page intentione.Ily left blank l

l l

4 7 14 Rev.I

SOUTHERN NUCLEAR OPERATING COMPANY l

VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 I

SECOND TEN-YEAR INTERVAL REQUEST FOR RELIEF NO. R.R-4 1

I.

System / Component (s) for Which Reliefis Requested:

Volumetric and surface examination of pressure-retaining welds and integral attachments in the Reactor Pressure Vessel Closure Head as identiGed in Attachment I to this request for relief.

II.

Code Requirement:

(a) ASME Section XI, Category B-A, Item B 1.40, Table IWB-2500-1 requires volumetiic examinations of pressure-retaining welds in the reactor pressure vessel. The applicable examination volume is shown in ASME Section XI, Figure IWB-2500-5 and includes essentially one hundred percent (100%) of the weld length.

(b) Code Case N-509 (see Request for Relief RR-20), Category B-K, Item B10.10, Table IWB-2500-1 requires surface examinations ofintegrally welded attachments on the reactor pressure vessel. The applicable examination volume is shown in ASME Section XI, Figure IWB-2500-15 and includes essentially 100% of the weld length.

III. Code Requirement from Which Reliefis Requested:

Reliefis requested from performing the full Code-required volumetric and surface examinations of the Reactor Pressure Vessel Closure Head Welds identified in Attachment 1.

IV. Basis for Relief:

(a)

Physical obstructions, e.g., RPV closure head lifting lugs and the RPV closure head tonis flange configuration, limit or otherwise prohibit movement of the transducer used for the ultrasonic examination of the RPV closure head to flange weld along the required scan region thereby limiting the amount of examination coverage that can be attained. Full Code Coverage of greater than ninety percent (90%), as defmed by ASME Section XI Code Case N-460 and as accepted by the NRC, is not possible for the referenced welds that are in the vicinity of the obstructions.

(b) The geometric configuration and location of the Control Rod Drive (CRD) braces and RPV closure head lifting device prevents a complete surface examination of the RPV closure head lifting lugs.

V.

Alternate Examination:

No attemate examination is proposed for the closure head to flange weld. The RPV closure head j to flange weld will be volumetrically examined to the extent practical. Likewise, the RPV closure head lifting lugs will be examined by surface means to the fullest extent practical.

I l

7-15 Rev.I

SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 SECOND TEN-YEAR INTERVAL REQUEST FOR RELIEF NO. RR-4 (continued)

VI..fustification for Granting Relief:

Relief was granted by the NRC for the RPV closure head torus to flange welds end closure head

. lifting lugs during the First Ten-Year Interval. These included First Ten-Year Interval Requests for Relief RR-7 and RR-52 for VEGP-1 and 2. NRC approval was documented in correspondence dated November 26,1991 and December 17,1991 for VEGP-1 and 2, respectively.

Although there are physical obstructions which limit the amount of examination coverage for those welds identified in Attachment 1, reasonable assurance still exists that an acceptable level of quality and safety will be maintained since there have been no catastrophic failures of reactor pressure vessels. As a result, SNC requests that relief be authorized pursuant to 10 CFR 50.55a(g)(6)(i) since it is impractical to perform these examinations to the extent required by the Code.

VII. Implementation Schedule:

The subject examinations will be performed to the fullest extent practical during the Second Ten-Year Interval which commenced May 31,1997.

l i

7-16 Rev.I 1

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SOUTHERN NUCLEAR OPERATING COMPANY I

VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 SECOND TEN-YEAR INTERVAL i

REQUEST FOR RELIEF NO. RR-7 1.

System / Component (s) for Which Reliefis Requested:

Volumetric examination of pressurizer pressure retaining welds (Class 1) as identified in Attachment I to this request for relief.

II.

Code Requirement:

l ASME Section XI, Category B-B (Item No. B2.11) and B-D (Item No. B3.110), Table IWB-2500-1, requires volumetric examination of pressure-retaining welds in the pressurizer. The l

applicabl examination volume is shown in ASME Section XI Figures IWB-2500-1 and 7(b).

III. Code Requirement from Which Reliefis Requested:

Reliefis requested from perferming the Code-required volumetric examinations of the components identified in Attachment 1 to this request for relief.

IV. Basis for Relief:

(a) Geometric limitation of the pressurizer skirt obstructs and/or prevents transducer movement along the required scan region of the Category B-B lower shell to lower head weld. Full Code Coverage is not possible in the vicinity of the obstructions.

(b) Geometric configuration of the 16" Category B-D pressurizer surge nozzle prevents scanning from the nozzle side. In addition, the pressurizer lower head heater penetrations obstructs and/or prevents transducer movement along the required scan region from the shell side. Limited coverage can be obtained for the 16" Category B-D nozzle to shell weld. However, no coverage can be obtained for the 16" nozzle inner radius due to the transducer " set back" dimension required.

(c)

Geometric configuration of the 4" and 6" relief and spray nozzles prevent scanning from the nozzle side for the Category B-D upper head to nozzle welds.

l (d) Geometric limitations of the pressurizer supports, ID plates and instmmentation nozzles obstmets and/or prevents transducer movement along the required scan region of the Category B-B upper head to upper shell weld. Full Code Coverage is not possible in the vicinity of the obstructions.

7-25 Rev.1

F SOUTIIERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 SECOND TEN-YEAR INTERVAL REQUEST FOR RELIEF NO. RR-7 (continued)

V.

Alternate Examination:

No alternate examinations will be pedormed for Category B-B welds. A 100% surface l

examination will be performed on the 4" and 6" nozzle to shell (B-D) welds, and approximately 85% surface exam on the 16" nozzle to shell (B-D) weld (heater penetration obstruction).

VI. Justification for Granting Relief:

The examinations are being conducted to the extent practical.

Relief was initially granted by the NRC during the First Ten-Year Interval for those welds / components in Attachment I having reauests for relief submitted for them. These included First Ten-Year Interval Requests for Relief RR-12, RR-14, and RR-15. KRC approval was documented in correspondence dated November 26,1991 and December 17,1991 for VEGP-1 and 2, respectively.

Although there are physical obstructions which limit or prohibit the amount of examination coverage for those welds / components identified in Attachment 1, reasonable assurance still exists that an acceptable level of quality and safety will be achieved. As a result, SNC requests l

that this request for relief be authorized pursuant to 10 CFR 50.55a(g)(6)(i) since it is impractical to perfonn the examinations to the extent required by the Code.

VII. Implementation Schedule-The subject examinations will be performed to the extent practical during the Second Ten-Year Interval which commenced May 31,1997.

l l

[

7-26 Rev.I

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!~

VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 SECOND TEN-YEAR INTERVAL REQUEST FOR RELIEF NO. RR-8 Request for Relief Withdrawn l

7-30 Rev.I 1

f '.

SOUTIIERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PL. ANT, UNITS 1 AND 2 SECOND TEN-YEAR INTERVAL REQUEST FOR RELIEF NO. RR-8 l

(continued) 1 This page intentionally left blank l

i i

1 l

I 741 Rev.1

{

r-.

SOUTIIERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 SECOND TEN-YEAR INTERVAL REQUEST FOR RELIEF NO. RR-8 (continued)

This page intentionally left blank l

l 7-32 Rev.1

SOUTIIERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 SECOND TEN-YEAR I.NTERVAL REQUEST FOR RELIEF NO. RR-10 1.

System / Component (s) for Which Reliefis Requested:

Volumetric examination of pressure-retaining primary nozzle to elbow welds in Class 1 portions of Steam Generators as identified in Attachment 1 to this request for relief.

II.

Code Requirement:

ASME Section XI, Table IWB-2500-1, Examinatien Category B-F, Item No. E5.130, requires l

volumetric and surface examination of pressure-retaining welds in piping. The applicable examination volume is shown in ASME Section XI Figure IWB-2500-8.

III. Code Requirement from Which Reliefis Requested:

Reliefis requested from perfonning a full Code-coverage volumetric examination of the piping welds identified in Attachment I to this request for relief.

IV. Basis for Relief:

The elbows are manufactured from centrifugally cast stainless steel with a coarse grain stmeture which prevents the use of normal ultrasonic shear wave techniques (Reference RR-9). The configuration of these elbow to nozzle weld joints is such that complete examinations are impractical to perform. The nozzle side of these welds has a sharp taper immediately adjacent to the weld, plus the surface of the nozzle is in a rough, as-cast condition. These conditions prevent any meaningful ultrasonic examinations from being performed on the nozzle; therefore, scanning of these welds can only be performed on the elbow side of the weld and on a portion of the weld itself. With this configuration, examinations will be performed as follows:

Reflectors Parallel to the Weld - For reflectors parallel to the weld, scanning will be performed only from the elbow side using a one half-node refracted longitudinal wave; therefore, only one beam direction will be attainable.

Reflectors Transverse to the Weld - For reflectors transverse to the weld, scanning will be performed on the elbow side and on a portion of the weld using a one half-node refracted longitudinal wave. Transducer interference by the nozzle taper will prevent total weld coverage.

Coverage for this configuration is calculated as 50%.

V.

Alternate Examination:

No alternative examinations are proposed.

7 36 Rev.1

SOUTIIERN NUCLEAR OPERATING COMP '

VOGTLE ELECTRIC GENERATING PLANT, UNI'._

<%D SECOND TEN-YEAR INTERVAL REQUEST FOR RELIEF NO. RR-10 (continued)

VI. Justification for Granting Relief:

Relief was initially granted by the NRC during the First Ten-Year Interval for those welds in Attachment I having requests for relief submitted for them. This included First Ten-Year Interval Request for Relief RR-17. NRC approval was documented in correspondence dated l

November 26,1991 and December 17,1991 for VEGP-1 and 2, respectively.

These welds are located in a low oxygen, PWR primary system water environment outside of areas considered subject to thermal stratification; therefore, there should be a low potential for cracking in these welds. Complete examinations of other welds in the system experiencing similar environmental conditions have and will be performed, using similar examination techniques. The overall examinations performed on welds in the primary system water environment, in conjunction with the low potential for cracking, should provide reasonable assurance of the operational readiness of the welds for which reliefis requested. Compliance with Code coverage requirements would necessitate refabrication of the elbows and/or the Steam Generator primary nozzles, which is completely impractical; therefore, approval should be granted pursuant 1o10 CFR 50.55a(g)(6)(i).

VII. Implementation Schedule:

The subject examinations will be performed to the extent practical during the Second Ten-Year Interval which commenced May 31,1997.

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r SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 SECOND TEN-YEAR INTERVAL-REQUEST FOR RELIEF NO. RR-11 1.

System / Component (s) for Which Reliefis Requested:

Volumetric examination of pressure-retaining pipe branch connection welds for nominal pipe size 4 inches and greater (Class 1) as identified in Attachment I to this request for relief.

II.

Code Requirement:

1 ASME Section XI Table IWB-2500-1, Examination Category B-J, Item No. B9.31, requires volumetric and surface examinations on branch pipe connection welds. The examination areas are shown in ASME Section XI Figures IWB-2500-9, -10, and -11.

III. Code Requirement from Which Reliefis Requested:

Reliefis requested from performing a full Code Coverage volumetric examination of the branch connection welds identified in Attachment 1 to this request for relief.

IV. Basis for Relief:

Examination of branch connection welds is typically difficult due to the configuration of the branch connection fitting and the weld design. For branch connection welds in the VEGP Reactor Coolant System (RCS) primary loop piping, these problems exist in addition to the problems of examining cast stainless steel pipe material. (See Attachment 2)

Two basic weld configurations are used for the branch conn ction designs on the RCS primary loop piping. The 4 inch branch connections were installed using a " set-on" weld design, while the 6,10,12, and 16-inch branch connections were installed using a " set-in" design.

Typically, examination coverage of branch connection welds can be obtained by scanning from the main run af pipe using a 45 degree shear wave technique. In this case, due to the cast stainless steel material used in the RCS primary loop piping, the examination is limited to a 1/2

. node examination using a 45 degree refracted longitudinal (RL) wave technique developed for this piping material.

Examination of the 4-inch branch connection welds from the main run of piping using the 1/2 node RL wave is not possible due to the geometry of the " set-on" configuration. However, partial coverage of the 6,10,12, and 16-inch branch connection welds from the main run using the 1/2 node RL technique is possible because of the " set-in" configuration. The VEGP branch connection configuration is depicted in Attachment 2.

~ 7-41 Rev.I s

L

I l

SOUTilERN NUCLEAR OPERATING COMPANY l

VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 l

SECOND TEN-YEAR INTERVAL REQUEST FOR REL.lEF NO. RR-11 I

(continued)

!V. Basis for Relief (continued):

I

\\

1 I

For the 4, 6,12 and 16 inch, the " Calculated Percentages" are less than reported during the First Ten Year Interval. Although the same technique is used, circumferential scan limitations were not initially included in calculations which reduce the accumulative Code Coverage obtairad by one-half. Performing circumferential scans for the applicable branch connections is not possible due to weld configurations. While the examination coverages that are listed in Attachment 1 vary from those shown for the First Ten-Year Interval, the actual extent and quality of the examinations remain the same.

1 V.

Alternate Examination:

It was determined that the only feasible examination from the branch connection side would be a refracted shear wave technique from the taper of the fitting. This technique relies on the ability of the shear wave to reflect off of the inner wall of the fitting bore. Calibration blocks were built with a 10% notch ir sensitivity and 3/16 inch side-drilled holes for establishing a DAC curve.

The forged stain., steel material, used in all but the 10-inch branch connections, allows the use of shear wave u' sonic techniques; however, the geometry of the fittings still presents problems in obtaining Code, required examination coverage. The fitting side of the 10-inch branch connection is cast stainless steel which precludes the use of a shear wave technique. Also, due to the geometry of the part, examination from the branch connection side using the 1/2 node RL l

technique is not feasible.

VI. Justification for Granting Relief:

The examinations are being conducted to the fullest extent practical.

Relief was initially granted by the NRC during the First Ten-Year Interval for those welds in Attachment I having requests for relief submitted for them. These included First Ten-Year Interval Requests for Relief RR-21 for VEGP-1 and 2. NRC approval was documented in correspondence dated November 26,1991 and December 17,1991 for VEGP-1 and 2, respectively.

l These welds are located in a low oxygen, PWR primary systein water environment outside of areas co idered subject to thermal stratification; therefore, there should be a low potential for cracking in these welds. Complete examinations of other welds in the system experiencing similar environmental conditions have and will be performed, using similar examination techniques. The overall examinations performed on welds in the primary system water 7-42 Rev.1 l

SOUTI1ERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 SECOND TEN-YFAR INTERVAL REQUEST FOR RELIEF NO. RR-11 (continued)

VI. Justification for Granting Relief (continued):

1 environment, in conjunction with the low potential for cracking, should provide reasonable assurance of the operational readiness of the welds for which reliefis requested. Compliance with Code coverage requirements would necessitate refabrication of the branch connections and main loop piping, which is completely impractical; therefore, approval should be granted pursuant to 10 CFR 50.55a(g)(6)(i).

VII. Implementation Schedule:

The subject examinations will be performed to the fullest extent practical during the Second Ten-Year Interval which commenced May 31,1997.

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SOUTIIERN NIICLEAR OPERATING COMPANY VOGTI,E El.ECTRIC GENERATING PI, ANT, UNITS 1 AND 2 SECOND TEN-YEAR INTERVAL REOUEST FOR RELIEF NO. RR-11 (continued)

ATTACllMENT 2 6-INCH 12-INCH PIPE >

16 INCH BRANCH CONNECTION PIPE +

J L

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h

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BRANCH

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4-INCH l

BRANCH CONNECTION l

7 45 Rev.1 i

SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 SECOND TEN-YEAR INTERVAL REQUEST FOR RELIEF NO. RR-12 l

1.

System / Component (s) for Which Reliefis Requested:

Volumetric examination of pressure-retaining circumferential welds in 10-inch di uneter Safety Injection piping made from SA-376 and SA-312 grade maWrial, as identified in Attachment I to j

this request for relief.

II.

Code Requirement:

Item No. B9.11, Category B-J, Table IWB-2500-1 and Item No. C5.11, Category C F-1, Table i

IWC-2500-1 of the ASME Section XI require a surface and volumetric examination of circumferential piping welds. The required examination volume is shown in ASME Section xI Figures IWB-2500-8(c) and IWC-2500-7(a). ASME Section XI, Article III-4420 requires that the examinations shall be perfonned using sufficiently long examination beam path to proside 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. ASME Section XI, 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 Supplement 4 also requires an additional examination volume for reflectors transverse to the weld to include 1/2-inch on each side of the weld. ASME Section XI, Article 111-2430 requires that manual scanning shall be done at twice (+6dB) the primary reference level, as a minimum.

III. Code Requirement from Which Reliefis Requested:

Reliefis requested from performing the Code-required volumetric examinations of the welds identified in Attachment 1.

IV. Basis for Relief:

The SA-376 and SA-312 materials exhibit severe angular variations and significant attenuation

. problems during a typical shear-wave ultrasonic examination. This was determined to be caused by severely banded microstructure. A meaningful ultrasonic examination could not be accomplished on the SA-376 and SA-312 materials using conventional shear-wave techniques.

In addition, physical limitations exist due to the geometric configuration of some weld joints, j

V.

Alternate Examination:

A refracted-longitudinal (RL) wave, which is a 1/2-node examination technique, was found to be the best technique during preservice inspection activities. During calibration for the RL-wave examination, the primary reference level will be set using side-drilled holes and appropriate notches. Scanning was possible only at the primary reference level due to the excessive 7-46 Rev. I

SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 SECOND TEN-YEAR INTERVAL REQUEST FOR RELIEF NO. RR-12 (continued)

V.

Alternate Examination (continued):

noise associated with the metallurgical structure of the material. On pipe to valve configurations, the weld was examined on the pipe side using the half-node technique. Scanning from the valve side was not possible due to valve geometry. On pipe to tee configurations, the weld was examined on the pipe side using the half-node technique. Only partial scanning from the tee was possible due to geometry.

VI. Justification for Granting Relief:

Relief was granted by the NRC for the First Ten-Year Interval. These included First Ten-Year Interval Requests for Relief RR-26 for VEGP-1 and 2. NRC approval was documented in correspondence dated November 26,1991 and December 17,1991 for VEGP-1 and 2, respectively. Subsequent revisions to the requests for relief were approved by the NRC as documented in correspondence dated January 6,1993 and August 13,1996 for VEGP-1 and 2, respectively. The examinations of the Class 1 and 2 Safety Injection System piping are being conducted to the fullest extent practical in the same manner as for the First Ten-Year Interval.

The examinations performed using the half-node technique, while not meeting full Code coverage requirements, are considered to be a viable means of detecting any significant circumferential cracking and should provide reasonable assurance of the operational readiness of the subject welds. Compliance with Code coverage requirements would necessitate replacement of the piping, which is completely impractical; therefore, approval should be granted pursuant to 10 CFR 50.55a(g)(6)(i).

VII. Implementation Schedule:

The subject examinations will be performed to the fullest extent practical during the Second Ten-Year Interval which commenced May 31,1997.

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SOUTHERN NUCLEAR OPERATING COMPANY VOGTL4E ELECTRIC GENERATING PLANT, UNITS 1 AND 2 SECOND TEN-YEAR INTERVAL l

REQUEST FOR RELIEF NO. RR-13 Request for Relief Withdrawn l

7-53 Rev. I

l SOU1 IIERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 SECOND TEN-YEAR INTERVAL REQUEST FOR RELIEF NO. Rk-13 (continued)

This page intentionally left blank l

l 7-54 Rev. I

SOUTIIERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT, UNITS i AND 2 SECOND TEN-YEAR INTERVAL REQUEST FOR RELIEF NO. RR-13 (continued)

This page intentionally left blank l

i 7-55 Rev. I

SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 SECOND JEN-YEARINTERVAL REQUEST FOR RELIEF NO. RR-14 1.-

System / Component (s) for Which Reliefis Requested:

Volumetric examination of pressure-retaining welds and nozzle inner radius sections of vessels and surface examinations of nozzle reinforcement plates (Class 2) as identified in Attachment 1

to this request for relief.

II. - Code Requirement:

ASME Section XI, Category C-A, Item No. C1.20, Table IWC-2500-1, requires volumetric examination of pressure-retaining welds of Class 2 pressure vessels. Applicable exarnination volumes are shown in Figures IWC-2500-1 and 2. ASME Section XI, Category C-B, Item Nos.

C2.21 and C2.22, Table IWC-2500-1, requires volumetric examinations ofpressure-retaining

' welds of Class 2 pressure vessels and nonle inner radii r.nd surface examinations ofnozzle reinforcement plate welds. The applicable examination volume is shown in Figure IWC-2500-4.

IIL Ccde Requirement from Which Reliefis Requested:

Reliefis requected from performing the Code-required volumetric examinations of the components identified in Attachment 1 to this request for relief.

IV.- Basis for Relief:

(a) The configuration of the steam generator (SG) steam outlet nozzle is such that no inner radius exists. The nozzle is manufactured from a forging that is a solid block of steel.

Seven (7) holes, each 81/2-inch diameter, have been drilled through this forging to provide an outlet for the steam.' Thus, this nozzle does not have a conventional " ner radius.

m (b) Geometric configuration of the SG main steam, auxilirry feedwater and main feedwater nozzles presents physical limitations that prevent complete coverage during ultrasonic examination. Scanning from the nozzle side is not feasible.

(c) ' The configuration of the VEGP Residual Heat Removal (RHR) heat exchanger (Hx) nozzles differs from that shown in ASME Section XI Figure IWC-2500-4(c). Although the

~

reinforcing plate welded to the vessel has a rounded configuration in the flow it is not a true nozzle inner radius when compared with the configuration in Figure IWC-2500-4(c).

Please refer to Attachment 2 for a figure depicting the VEGP configuration. It is not.

_ possible to perform an inner radius ultrasonic examination since the interface between the j

reinforcing plate and the RHR heat exchanger vessel wall prohibits volumetric i

examination. Although the reinforcement plate is welded to the inside diameter of the heat i

7-56 Rev.1

t SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 SECOND TEN-YEAR INTERVAL REQUEST FOR RELIEF NO. RR-14 (continued)

IV. Basis for Relief (continued):

l exchanger wall, the reinforcing plate-to-vessel welds are inaccessible. Therefore, it is l

- impractical to perform a surface examination on the reinforcing plate-to-vessel welds.

l (d) For the VEGP-1 Boron Injection Tank (BIT), the outside diameter (OD) configuration, combined with the interfering support legs and cast stainless steel material presents physical limitations that prevent complete coverage during ultrasonic examinations.

l I

V.

Alternate Examination:

l-No alternate examination is proposed. The affected Class 2 vessel welds are being examined to I

fullest extent practical.

L 1

VI. Justification for Granting Relief:

The examinations are being conducted to the fullest extent practical.

Relief was initially granted by the NRC during the First Ten-Year Interval for those l

welds / components in Attachment I having requests for relief submitted for them. These included First Ten-Year Interval Requests for Relief RR-28, RR-29, RR-30, and RR-32. NRC approval was documented in correspondence dated November 26,1991 and December 17,1991 for VEGP-1 and 2, respectively. It was determined during the first ten-year interval review process that geometric configurations and interferences make the volumetric examinations of these welds impractical to perform to the extent required by the Code. The subject components would require extensive modifications in order to obtain complete compliance with the specific requirements of ASME Section XI. The increase in plant safety would not compensate for the burden placed on the licensee that would result from imposition of the requirement.

Although there are phywcal obstructions which limit the amount of examination coverage for l

those components identified in Attachment 1, reasonable assurance still exists that an acceptable

!~

level of quality and safety will be maintained since there have been no catastrophic failures of Class 2 pressure vessels. SNC requests that relief be authorized pursuant to 10 CFR l

50.55a(g)(6)(i) since imposing the Code requirements is impractical.

l l

1 i

i l

I 7-57 Rev.1

SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 SECOND TEN-YEAR INTERVAL REQUEST FOR RELIEF NO. RR-14 (continued)

VII. Implementation Schedule:

The subject examinations will be performed to the fullest extent practicd during the Second Ten-Year Interval which commenced Ma:. 31,1997.

l 1

l 7-58 Rev.I

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SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 SECOND TEN-YEAR INTERVAL REQUEST FOR R2 LIEF NO. RR-14 (continued)

ATTACHMENT 2

)

\\

i 7/8" VESSEL WALL WELDS WO!I (NOZZLE B)

WOI2 (NOZZLE A)

_ _. _ _ S l

+

REINFORCING PLATE I.5/8" ElCK NOZZLE TO VESSEL WELD AREA OF INTEREST INNER RADIl 0.438 IR01 & IR02 i

2 h

L

)

[

NO WELDS WO9 (NOZZLE B)

NOZZLE W10 (NOZZLE A)

L RESIDUAL HEAT REhf0 VAL HEAT EXOLANGER NOZZLE TO VFSSEL WELDS l

(NOT TO SCALE) i 1

7-61 Rev.I

i-l

.s.

SOUTIIERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 SECOND TEN-YEAR INTERVAL REQUEST FOR RELIEF NO. RR-15 Request for Relief Withdrawn l

7-62 Rev.I

SOUTHERN NUCLEAR OPERAT1.NG COMPANY VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 SECOND TEN-YEAR INTERVAL REQUEST FOR RELIEF NO. RR-15 (continued)

This page intentionally left blank l

7-63 Rev.I

SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 l

SECOND TEN-YEAR INTERVAL REQUEST FOR RELIEF NO. RR-15 (continued)

This page intentionally left blank l

l l

7-64 Rev.1

SOUTHERN NUCLsAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT. UNITS 1 AND 2 SECOND TEN-YEAR INTERVAL REOUEST FOR RELIEF NO. RR-16 I.

. System / Components (s) for Which Reliefis Reauested:

Volumetric examination of pressure-retaining piping welds in Class 2 systems as identified in Attachment I to this request for relief.

Reanirement from Which Reliefis Reauested:

'ASME Section XI, Category C-F-2, Item C5.51, Table IWC-2500-1 requires surface and volumetric examination of pressure-retaining welds in Class 2 piping. The applicable examination volumes are shown in Figure IWC-2500-7 and include essentially 100% of the weld length.

IIL Code Reauirement from Which Reliefis Reauested:

4 Reliefis requested from performing a Full Code Coverage volumetric examination of the Class 2 piping welds identified in Attachment I to this request for relief.

1 IV. Basis for Relief:

1 Physical limitations due to geometric configuration of the welded areas restrict coverage of the examination volume required by Figure IWC-2500-7.

l V.

Alternate Examination:

l No alternate examination is proposed.

VL Justification for Grantine Relief:

The volumetric examinations of the Class 2 piping welds are being conducted to the fullest extent practical. As noted herein, physical access is restricted due to the geometric configuration of the welded areas identified in Attachment 1, thereby preventing full code examination coverage.

Relief was granted by the NRC for the Class 2 piping welds during the Fir:,t Ten-Year Interval.

These included First Ten-Year Interval Requests for ReliefRR-34, RR-35, RR-36, and RR-37 for VEGP-1 and 2. NRC approval was documented in correspondence dated November 26,1991 and December 17,1991 for VEGP-1 and 2, respectively.

i As a result, SNC requests that relief be authorized pursuant to 10 CFR 50.55a(g)(6)(i) since imposition of Code required examinatiens is impractical.

745 Rev.1

SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 SECOND TEN-YEAR INTERVAL REOUEST FOR RELIEF NO. RR-16 (continued)

VIL Imniementation Schedule:

The subject examinations will be performed to the fullest extent practical during the Second Ten-Year Interval which commenced May 31,1997.

l 7-66 Rev.1

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1 SOUTilERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 SECOND TEN-YEAR INTERVAL REQUEST FOR RELIEF NO. RR-22 1.

Sj stem / Component (s) for Which Reliefis Requested:

Each of the ASME Class 1,2, and 3 small items consisting ofpiping, tubing (except heat exchanger tubing, sleeves, and welded plugs used for heat exchanger tubing), valves, and fittings 1-inch and smaller nominal pipe size (NPS) subject to repair or replacement within the scope of

' the ISI Program. Steam generato: tubing, sleeves, and welded plugs used for steam generator tubing ne considered by SNC to be heat exchanger tubing-related components at VEGP and are therefore excluded from the scope of this request for relief.

II.

Code Requirement:

IWA 7400 (a) (4) of the 1989 Edition of ASME Section XI exempts 1-inch NPS and smaller l

replacement items and their installation from the requirements ofIWA-7000; whereas, the repairs ofitems 1-inch NPS and smaller are not similarly exempted from the requirements ofIWA-4000.

III. Code Requirrinent for Which ReliefIs Requested:

Reliefis requested from the requirements ofIWA-4000 and IWA-7000 on piping, tubing, valves, and fittings 1-inch NPS and smaller.

IV. BasishRelief:

ASME Section XI Code Case N-544 was issued on August 24,1995 and provides an alternative l

to the requirements ofIWA-4000 and IWA-7000 when a repair or replacement is performed on piping, valves and fittings 1-inch NPS and smaller. A copy of the code case is provided as j

l Attachment I to this request for relief. The provisions of this code case were added to IWA-l

~4131 and IWA-4132 in the 1995 Addenda to ASME Section XI.

V.

Alternate to the Code Requirements:

Southern Nuclear Operating Company will comply with the requirements of Code Case N-544 in lieu ofIWA-4000 and IWA-7000 except that the subject code case will not be applicable to heat I

exchanger tubing, sleeves, and welded plugs used for heat exchanger tubes in Class 1,2, and 3 heat exchangers, including similar steam generator-related components.

- VI. Jus _tification for the Granting of Relief:

1 t

The 1989 Edition of ASME Section XI Code provides an exemption for replacement items 1-inch NPS and smaller from the requirements ofIWA-7000, but repairs to such items are not similarly exempted. Therefore, a repair to an item is subject to more restrictive requirements than replacing the item. Code Case N-544 allows application cf the alternative requirements for replacement to all repair and replacement activities. The ASME Code Committee evaluated the 7-90 Rev.1 l

L

r 1

SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 SECOND TEN-YEAR INTERVAL REQUEST FOR RELIEF NO. RR-22 (continued)

VI. : Justification for the Granting of Relief (continued):

proposed alternatives contained in the code case and determined that they are acceptable for repair and replacement activities on piping (including tubing with certain exceptions), valves, and fittings 1-inch NPS and smaller. Components to which exceptions were applied are identified in Paragraphs - 1300 and - 1400 of Code Case N-544. Specifically, the exceptions include heat exchanger tubing, sleeves, and welded plugs for heat exchanger tubing for Class 1, 2, and 3 systems. In addition, SNC considers steam generator tubing, sleeves, and welded plugs i

used for plugging steam generator tubes to be heat exchanger-related components. Therefore, Code Case N-544 will not be applicable to the steam generators nor to other Class 1,2, and 3 heat exchanger tubing, including sleeves and welded plugs for heat exchanger tubing. The steam generator tubes will continue to be inspected in accordance with the requirements of ~ 'EGP Technical Specification 5.5.9, " Steam Generator (SG) Tube Surveillance Program", including any tube plugging required as a result ofinspections performed. Any necessary repairs of steam generator tubes or those of other Class 1,2, and 3 heat exchangers will be repaired in accordance with the requirements of the 1989 Edition of ASME Section XI. SNC has determined that implementation of the code case (with the exceptions noted herein concerning heat exchangers and steam generators) will not affect the level of quality and s afety, nor decrease the margin of public health and safety. To ensure that the level of quality and safety is maintained, SNC will i

perform repair / replacement activities for 1-inch NPS and smaller using various existing approved procedures and/or programs which establish control on the planning, work control, quality assurance / quality control, and implementation of work packages.

i While the cost savings associated with Code Case N-544 have not been quantified as a Cost Beneficial Licensing Action item, its implementation is consistent with the intent to eliminate nonbeneficial work activities and their associated costs. Therefore, it is requested that the proposed alternative be authorized pursuant to 10 CFR 50.55a(a)(3)(i).

VII, Implementation Schedule:

+

This relief for request is applicable to the Second Ten-Year Interval which commenced May 31, l

1997.

7-91 Rev.I

SOUTHERN NUCLEAR OPERATING COMPANY VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 SECOND TEN-YEAR INTERVAL REQUEST FOR RELIEF NO. RR-22 (continued)

ATTACHMENT 1 cda N-544 Casts or assit so:LER A.wp Patsstat vtssts, coot Approval Oate: August 24.190s s.eu n enna. ewe m

(

and one reaMirmareen estes.

Case N.544 reactor coolant manceup systems operable from onsite Repair / Replacement of Small teems emergency power.

Section XI. Division 1 1400 Class 2 and 3 piping. tubing lexcept heat exchanger tubing. and sleeves and welded plugs used q,,,,y. When performing repair or replacement of f r heat eschanger subingt valves. and nitings. NPS piping, valves. and nitings. NPS I and smaller. what I 3"d '**U* ""'I *****'***d '"PP

attemative requirements may be used in lieu of IWA.

4000 for repair and IWA.7000. for rep!acement con.

2000 ACTIVITIES PERFORMED TO ducted in accordance with Section XI Editions and StatMER 1978 ADDENDA THROUGH Addenda through the 1990 Addenda, er [WA.4000 for 1990 ADDENDA OF SECTION XI repair and replacement conducted in accordance with l

00 Fw h h 'MW W m W M the 1990 Addenda and laser?

the following requirements are an alternative to the end replacement requirements of IWA.4000 and Aeply: 1 is the opinion of the Commines mas repair and replacement of piping. valves, and Actings. NPS I and smaller, may be performed in accordance with 2200 items to be used for replacement shall be the following requirements:

constructed in accordance with IWA.7210. except that possessioi of a Certincate of Authoritation and an agreement wah an Authonged Inspection Agency are

.t000 CENERAL REPA!R AND neither required nor prohibited.

REPLACEMENT REQUIRDIENTS 2300 liams to be used for repair and replacement

.I100 Repair and replacement activities performed in shall be obtained. installed and documented in accord.

accordance with Section XI Edition and Addenda from ance with the provisions of IWA 1400(n) and the the 1977 Edition with the Summer 1978 Addenda technical requirements of IWA.7210. For Section !!!

through the 1939 Edition with the 1990 Addenda on items. the requirements of NA.3700/NCA.38CO need nems identined in.1300 and.1400 shall satisfy the not be met. provided the Owner's Quality Assurance requirements of.2000.

Program provides measures to assure that material used for replacement is furnished in accordance wi,th the 1200 Repair.and replacement activities performed in W**

accordance with Section XI Editions and Addenda from 1

^

the 1989 Edition with the 1991 Addenda through the 1992 Edition with the 1994 Addenda on items identined

- - '***"I'**

8'"*7'

""'**"*'*9" in.1300 and.1400 shall satisfy the requiremenu for instaHation of these items.

2400 Repair shall be performed and documented in 1300 Class I piping. subing (except heat eschanger accordance with IWA.1400(n). IWA.4l20. IWA.4200.

tubing, and sleeves and welded plugs used for heat and IWA.4300 Weld n!)er material shall be obtained eschanger subingl. valves. Actings, and associated sup-in accordance with.2300. A Repair / Replacement Plan, pons, no larger than the smaller of (a) or (bl below:

pressure tesung. services of an Authon=ed Inspection

'"# I' '" *

(b A ize and design such that. in the event of 9" *

postulated failure dunng normal plant operating condi.

sions, the xactor can be shut down and cooled in an 1500 If an item to be repaired or replaced does not orderly manner. assuming makeup is provided by normal saasfy the requirements of Secuan XI. the Owner shall 7-92 Rcv.1

F VOGTLE ELECTRIC GENERATI SOUTIIERN NUCLEAR OPERATING COMPANY SECOND TEN-YEAR INTERVAL REQUEST FOR RELIEF NO. RR-22

)

(continued)

ATTACIIMENT 1 (continued)

CASE (continued)

N-544 CASES OF ASME aOILER AND PRESSURE vt33EL CODE determine :he cause of an.icceptabilit.v and evaluate the NCA.3300 need not bc, met, prosided the Owner's sunaDihtv of the repair or replacement pnor to returning Quality Assurance Program provides measures to assure the stem to sertsce. If the speel6 canon for the original that matenal used for replacement is fumashed in accord.

item is determined to be dancient. appropnate corrective ance with the applicable matenal specincation and provisions shall be included in the specificanon for the matenal requirements of Secuan III. A RepaireReplace.

repair or the replacement nem.

ment Plan. pressure testing. services of an Authonaed 2600 Fo? vahes uhose performance parameters could

'"'P**"*" I*"*I' ** *** *

be affected by trw repair or replacement activity. a

" " "9" presersics test shall be made in accordance with Subsec. 3400 Repair shall be performed and documented in non IWV pnor to retuming the vahe to service.

accordance wuh IWA.1400tnl. IWA.4120. lWA.4200.

2700 For pumps whose performance parameters could

- * ' * ^

1 be affected by the repair or replacement activity, a new set of reference values shall be determined in acc reance with.3300. A Repair / Replacement Plan, accordance with Subscenon IWP during the Erst inser.

Pressure tesung. services of an Authonzed Inspacean vice test performed after the pump is put into sabice.

gency, and completion of NIS.2 forms are not re.

2300 Use of these alternative requirements including 3500 If an item to be mpaired or replaced does not specifying the size of Class I items to which these requirements will be applied, shall be documented by sadsfy the requirements of Section XI. ihe Owner shall the Owner and is subject to review by the Inspector.

the mse of mep@lin W evaluane h suitability of the repair or replacement prior to retuming the item to service. If the sper icanon for the original 3000 ACTTVITTES PERFORMED TO 1991 item is determined to be deheie% appropriate correcdvs ADDENDA THROt*CH 1994 ADDENDA provisions shall be included in the speciAcation for the OF SECTION XI repair or the replacement item.

3100 For the items identined in.1300 and.1400.

3600 For valves whose performance parameters could the following requirements are r.n attemauve to the be affected by the repast or replacement activity, a repair and replacement requirements of IWA.4000.

preservice test shall be made in accordance with Subsec.

" " IWV E" ' ' "'* "I 'h*

- ' **'*i**'

3200 items to be used for replacement shall be censtructed in accordance with [WA.4170, except that 3700 For pumps whose petformance parameters could possession of a Ceruncate of Authoritsuon and an be affected by the repair or replacement activity, a agreement with an Authonted Inspection Agency are new set of reference values shah be determined 14

/

neither required nor prohibited.

accordance with Subsection IWP during the Arst inser.

3300 hems to be used for repair and replacement

' ice te8t Performed after the pump is put into service.

shall be obtained, installed, and documented in accord.

3800 Use of these attemative requirements. including ance with the provisions of IWA-1400(n). and IWA.

specifying the sise of Class I items to which these 4132 for the 1993 Addenda and later, and (WA-4870.

requiremenu will be applied. shall be documented by For Section lit items. the requirements of NA 3700/

the Owner and is subject to review by the insp2ctor.

l 7-93 Rev.1

ML20209H409

Text

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