RC-13-0068, V. C. Summer, Unit 1, Request Relief from ASME Code Requirements in 3rd Ten Year Inservice Inspection Interval - (RR-III-10) Limited Pressurizer Surge Nozzle-to-Vessel Examination

V. C. Summer, Unit 1, Request Relief from ASME Code Requirements in 3rd Ten Year Inservice Inspection Interval - (RR-III-10) Limited Pressurizer Surge Nozzle-to-Vessel Examination

ML13129A178
Person / Time
Site:	Summer
Issue date:	05/06/2013
From:	Gatlin T South Carolina Electric & Gas Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RC-13-0068
Download: ML13129A178 (15)

Text

Thomas D. Gatlin Vice President,Nuclear Operations 803.345.4342 A SCANA COMPANY May 6, 2013 RC-13-0068 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001

Subject:

VIRGIL C. SUMMER NUCLEAR STATION UNIT 1 (VCSNS)

DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 REQUEST RELIEF FROM ASME CODE REQUIREMENTS IN VCSNS 3RD TEN YEAR INSERVICE INSPECTION INTERVAL (RR-III-10) Limited Pressurizer Surge Nozzle-to-Vessel Examination Pursuant to 10CFR50.4, South Carolina Electric & Gas Company (SCE&G), acting for itself and as an agent for South Carolina Public Service Authority, hereby submits the attached relief request. Pursuant to 10CFR50.55a(g)(5)(iii), relief is requested from the "essentially 100 percent" volumetric examination coverage requirement for the identified Pressurizer Nozzle-to-Vessel Welds, ASME Section Xl Category B-D, Item No. B3.1 10.

This requirement is considered impractical due to the pressurizer shell to surge nozzle weld configuration. The plant specific information supporting this proposed alternative is provided in Enclosure 1.

No new regulatory commitments are being made to the NRC by this letter. If you should have any questions, please contact Mr. Bruce L. Thompson at (803) 931-5042.

Very truly yours, Thomas D. Gatlin JMG/TDG/ts

Enclosure:

RR-III-10, Limited Pressurizer Nozzle-to-Vessel Examination c: K. B. Marsh E. A. Brown S. A. Byrne NRC Resident Inspector J. B. Archie K. M. Sutton N. S. Cams NSRC J. H. Hamilton RTS (CR-12-05348) t J. W. Williams File (810.19-2)

W. M. Cherry PRSF (RC-13-0068)

V. M. McCree VirgilC. Summer Station Post Office Box 88 *Jenkinsville, SC . 29065. F(803) 345-5209 ý ..

Document Control Desk CR-12-05348 RC-13-0068 Page 1 of 4 SOUTH CAROLINA ELECTRIC & GAS CO. (SCE&G)

VIRGIL C. SUMMER NUCLEAR STATION UNIT 1 (VCSNS)

Relief Request RR-III-10 Limited Pressurizer Nozzle-to-Vessel Examination

1. ASME Code Component(s) Affected The affected component is the V. C. Summer Unit 1 Pressurizer. The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code, Section Xl (Reference 1) examination category and item number is from IWB-2500 and Table IWB-2500-1 of the ASME BPV Code, Section Xl.

Category B-D welds is defined as "Full Penetration Welded Nozzles in Vessels" and for VCSNS Pressurizer Shell to Surge Nozzle weld is represented by Examination Requirements Figure Number IWB-2500-7(b) Nozzle in Shell or Head (see Figure 1 of this enclosure).

Examination Category Item No. Weld Number Description B-D B3.1 10 1-2100A-8 Pressurizer Surge Nozzle-to-Vessel

2. Applicable Code Edition and Addenda

ASME Code Section Xl, "Rules for Inservice Inspection of Nuclear Power Plant Components," 1998 Edition through 2000 Addenda.

3. Applicable Code Requirement

IWB-2412, Inspection Program B, requires volumetric examination of essentially 100%

of pressure-retaining welds identified in Table IWB-2500-1 once each ten-year interval.

The V. C. Summer Unit 1 third 10-year inservice inspection (ISI) interval ends December 31, 2013.

Table IWB-2500-1, Examination Category B-D requires volumetric examination of Item B3.110 (Pressurizer Nozzle-to-Vessel welds). Figure IWB-2500-7(b) (provided as Figure 1 of attachment 1) depicts the required examination volume (A-B-C-D-E-F-G-H) which includes the actual circumferential weld and adjacent base metal on either side of the weld extending to a distance of one-half the thickness of the wall from the extremities of the weld crown.

Document Control Desk CR-12-05348 RC-1 3-0068 Page 2 of 4 NRC Information Notice 98-42, "Implementation of 10CFR50.55a(g) Inservice Inspection Requirements," termed the reduction in coverage of less than 10% to be "essentially 100 percent." Information Notice 98-42 states in part, "The NRC has adopted and further refined the definition of 'essentially 100 percent' to mean 'greater than 90 percent' ... which has been applied to all examinations of welds or other areas required by ASME Section XM."

4. Reason for Request

In accordance with 10CFR50.55a(g)(5)(iii), relief is requested for the Pressurizer Surge Nozzle-to-Vessel Weld, ASME Section Xl Category B-D, Item Number B3.1 10 from the "essentially 100 percent" volumetric examination coverage requirement. During refuel 20, VCSNS was limited in the amount of code coverage obtainable. VCSNS was successful in coverage of 75.5 percent with no recordable indications. The essentially 100 percent code coverage (90 percent minimum) requirement is considered impractical due to the pressurizer shell to surge nozzle weld configuration. Ultrasonic examination of the pressurizer surge nozzle to vessel weld is limited in coverage due to the configuration and interference with the pressurizer heater penetration ring and insulation. VCSNS is declaring that the examination was performed to the extent practical using qualified equipment and personnel.

5. Proposed Alternative and Basis for Use SCE&G proposes that the examinations completed during the last refuleing, at the reduced coverage, be accepted as meeting the Code requirements to the extent practical.

Alternative components could not be substituted for examination due to the mandatory selection requirements of the Code. The limited volumetric examination should detect any general patterns of degradation that may occur in the areas covered, therefore providing reasonable assurance of the continued structural integrity of the subject weld.

The pressurizer is a vertical, cylindrical vessel that provides a point in the Reactor Coolant System where liquid and vapor can be maintained in equilibrium under saturated conditions for pressure control purposes. The vessel is constructed in accordance with ASME Boiler and Pressure Vessel Code Section III, Class 1 Nuclear Vessels. The pressurizer has a hemispherical top and bottom head (provided as Figure 2 of attachment 1) constructed of SA-533 Grade A Class 2 carbon steel that has a minimal wall thickness of 2.55 inches that includes a 0.19 inch cladding. All vessel surfaces exposed to reactor coolant are lined with austentic stainless steel cladding.

The surge line and electrical heaters are installed through the bottom head of the vessel (provided as Figures 2, 3, and 4 of attachment 1). The nozzle forging for the surge line was constructed with SA-508 Class 2 and has a 24.5 inch diameter at the nozzle to

Document Control Desk CR-12-05348 RC-1 3-0068 Page 3 of 4 vessel interface which is automatic subarc welded with P1 material to conform to Westinghouse PDS-10365BS. There are 78 electrical immersion heaters installed in bottom head orientated in three concentric rings with approximately 10 inch spacing (provided as Figure 2 of attachment 1). The rings exclude an 18 inch section for clearance of the 14 inch diameter surge pipe. The inner ring is located on a 34 inch diameter with 20 immersion heaters that are approximately 1.75 inches in diameter and pitched every 4.5 inches.

The weld is the Pressurizer Surge Nozzle-To-Vessel Weld (VCSNS weld number 1-2100A-8), ASME Section Xl Category B-D, Item Number B3.1 10 which is the P1 material utilized to conform to Westinghouse PDS-1 0365BS (provided as Detail-E of Figure 4 of this enclosure). The details of the weld and weld material are located on Westinghouse (Proprietary) drawings: 3453C54, "Wire and Flux Qualification Drawing" and 1097J92, "Lower Head Assembly Drawing."

Wesdyne International, a Westinghouse Electric Company, performed the inspection with Procedure SDI-STD-1 010 Revision 3, "Manual Ultrasonic Procedure for the Examination of Pressure Vessel Welds > [Greater Than] 2" [Inches] in Thickness, Including Non-PDI Reactor Vessels and Heads" dated August 9, 2012. The complete Ultrasonic Examination Data Records for the Category B-D, Item B3.1 10 examination included as attachment 2. The report includes details of the UT scanning parameters, including the transducer size, frequency and angle. The examinations were performed on the outside surface with a 45 degree shear wave, 60 degree shear wave, and 0 degree longitudinal wave search units. Also included are coverage plots for each of the examinations showing the nozzle configuration and percent coverage for the scans. As reported, the two level three inspectors were able to obtain 100 percent of the linear weld in the clockwise and counter clockwise direction but were only able to obtain 51 percent for both the axial directions from the head side and from the nozzle side. Based on the coverage, the level three inspector declared a total of 75.5 percent weld required volume coverage was obtained. This is less than the code allowable of 90 percent therefore this requirement is impractical due to the pressurizer to surge nozzle weld configuration.

During the refuel 20 inspection, station personnel received approximately 1 Rem with 44 mili-Rem received during the inspection by qualified personnel.

6. Duration of Proposed Alternative This request is applicable to the V. C. Summer Unit 1 inservice inspection program for the third 10-year ISI interval that ends December 31, 2013.

Document Control Desk CR-12-05348 RC-13-0068 Page 4 of 4

7. Precedents On October 8, 2012 Braidwood Station submitted a similar request that was issued under Accession Number ML12283A084. Braidwood also sought relief due to impracticality of a similar weld type (Pressurizer Nozzle-To-Vessel) due to limited coverage of the safety valve nozzle and spray nozzle.

On April 5, 2007 Watts Bar submitted and on August 29, 2007 was granted relief for a similar request that was issued under Accession Number ML072280088. Watts Bar was seeking relief due to impracticality of a similar weld type (Pressurizer Nozzle-To-Vessel ) due to limited coverage of the safety valve nozzle and spray nozzle.

The average of these scan volumes resulted in approximately 55 percent of the code required volume being scanned.

8. References

1. ASME Boiler and Pressure Vessel Code, Section Xl, 1998 Edition through 2000 Addenda, American Society of Mechanical Engineers, New York.

2. NRC Information Notice 98-42, "Implementation of 10CFR50.55a(g) Inservice Inspection Requirements," termed the reduction in coverage of less than 10% to be "essentially 100 percent."

3. Westinghouse (Proprietary) drawings 3453C54, "Wire and Flux Qualification Drawing."

4. Westinghouse (Proprietary) drawings 1097J92, "Lower Head Assembly Drawing."

Document Control Desk CR-12-05348 RC-1 3-0068 Page 1 of 4 Fig. IWB-&2.500-?(b) 1998 SECTTON .I - DIVISION I t

o rnl, n2 - nozzle wall thickness -

Is = shell ior head] thicknes*

,j = no2zle inside corner radius D

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A-B-C-D-E-F-G-H Corner flaw EXANMNATION REGION INDIOOil_ EXAMINATION VOLUME Mtoeo (211 Shell lot headl adjoining region C-0-E-F Attachment weld region B-C-F-G Nozzle cylinder region A-B-G -H Notzle inside corner region M-N-O-P NOTES:

(1) Exa mination regions are identified for the purpose of differentiating the accoltance stondards in IWB-3512.

(2) Examination volumes may be determined either by direct measurements on Ihe component or by measurements based on design drawings, Figure 1, FIG. IWB-2500-7(b) NOZZLE IN SHELL OR HEAD (Examination Zones in Flange Type Nozzles Joined by Full Penetration Butt Welds)

Document Control Desk CR-12-05348 RC-1 3-0068 Page 2 of 4 I~. I' w

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Figure 2, Partial VCSNS Drawing 1MS-07-0117 Pressurizer Outline

Document Control Desk CR-12-05348 RC-13-0068 Page 3 of 4 4 4 4

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Figure 3, Partial VCSNS Drawing 1MS-07-0117 Pressurizer Outline - Detail "E" Immersion Heater Details

Document Control Desk CR-12-05348 RC-1 3-0068 Page 4 of 4 FORG4NGS I)ETAIL"E" Figure 4, Partial VCSNS Drawing 1MS-07-0118 Pressurizer General Arrangement

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Examiner _ _ _ _ _ _ Lv. !I[ Date: 10129/19)2 Limited scan area, see attached sketch Print Paul Blecha Code Coverage Achieved 75.5  %/I Examiner Lv. III Date: 10/29/2012 RiskInformed El YES 2) NO C'Bore 0 Y j] N Print Kenneth Smith Exam is Acceptable El YES F NO Reviewer: Z /-y.L-o Date: I 3z/17_. Reviewer:( -'-( L -o *Date:

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Examiner Lv. Il Date: 10/29/2012 Limited scan area. See attached sketch Print Paul Blecha Code Coverage Achieved 175.5 %1 Examiner Lv. m Date: 10/29/2012 Risk Informed El YES [] NO C'Bore E Y E) N Print Kenneth Smith Exam is Acceptable [] YES [] NO Reviewer: 7L Date: Reviewer: c[ o . 77 ( Date: , /' 0JZ..

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V.C. Summer/ 1 0 Plant/Unit:

Crown Height: Flush 1 Comp/System: PZR / RC Crown Width: 2.00" Diameter: N/A Weld / Component ID Number: 1-21 OOA-8 Weld Length: 74.5" Heater Penetraton 1.25" Typ Weld coverage based on % of weld material scanned from both directions with both transducers t 18.5" perpendicular and parallel to the weld (4 directions)

COMMENTS: Weld material coverage calculated as: CW =100%, CCW =100%, Ax Hd= 51%, Ax Nz = 51% TOTAL = 302%

302% /4 = 75.5% Weld Volume Coverage EXAMINER /ti~u.Q*S * .. ,--Lv. III Date 10/29/2012 EXAMINER: * ,- - Lv. III Date 10/29/2012 Print Paul Blecha Print Kenneth Smith REWVIEF &ý ýLl DATE IV/2-P/J2-- REVIEWER: Lv. -772E DATE: 9L/

Authorized Inspection Agency r1-L9oyt-A E--t DATE k /k "A powerful part of your team"