ML093631561

Relief Request No. 09-MN-006, Revision 1

ML093631561
Person / Time
Site:	McGuire
Issue date:	12/17/2009
From:	Brandi Hamilton Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML093631561 (13)

Text

Duke Duke BRUCE Vice H.HAMILTON President LEnergy. McGuire Nuclear Station Duke Energy MG01 VP /12700 Hagers Ferry Road Huntersville, NC 28078 980-875-5333 980-875-4809 fax bruce.hamilton@duke-energy.com December 17, 2009 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Duke Energy Carolinas, LLC (Duke)

McGuire Nuclear Station, Unit 1 Docket No. 50-369 Relief Request No. 09-MN-006, Revision 1 By letter dated August 31, 2009, Duke submitted Relief Request No. 09-MN-006 pursuant to 10 CFR 50.55a(g)(5)(iii), concerning limited volumetric examination coverage of Safety Injection System Weld No. 1NI-231-1. Duke subsequently discovered errors in this relief request. The NRC Project Manager was informed of this issue by a telephone call on November 18, 2009.

This relief request has been revised to correct these errors and is attached for your review and approval. Duke sincerely apologizes for any inconvenience this issue may have caused.

If there are any questions or further information is needed, please contact P. T. Vu at (980) 875-4302.

Very truly yours, B. H. Hamilton Attachments www. duke-energy.com

U. S. Nuclear Regulatory Commission December 17, 2009 Page 2 xc w/attachments:

L. A. Reyes, Regional Administrator U. S. Nuclear Regulatory Commission, Region II Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 J. H. Thompson, Project Manager U. S. Nuclear Regulatory. Commission 11555 Rockville Pike Mail Stop 0-8 G9A Rockville, MD 20852-2738 J. B. Brady, Senior Resident Inspector U. S. Nuclear Regulatory Commission McGuire Nuclear Station

Relief Request 09-MN-006, Revision 1 Proposed Relief in Accordance with 10 CFR 50.55a(g)(5)(iii)

Inservice Inspection Impracticality Duke Energy Corporation McGuire Nuclear Station - Unit I (EOC-1 9)

Third 10-Year Interval - Inservice Inspection Plan

McGuire Nuclear Station, Unit 1 Relief Request # 09-MN-006, Rev. I Page 2 of 5

1. ASME Code Component Affected Safety Injection System Pipe Butt Weld to Reducer ASME Code Class 2 Weld ID = 1N1231-1 Item Number = R1.11 Summary Number = M1.R1.11.0142 Note: In the attached examination data sheets, this weld is referred to as a Full Coupling to Pipe Weld. A review of the piping drawings has confirmed that this is a pipe butt weld to reducer.

II. Applicable Code Edition and Addenda ASME Boiler and Pressure Vessel Code,Section XI - 1998 Edition thru the 2000 Addenda, as amended by Relief Request 01-005.

II1. Applicable Code Requirement The examination requirements for Class 1 and 2 piping welds are governed by the Risk-Informed Inservice Inspection program which is based on WCAP-14572, Revision 1-NP-A. The WCAP Table 4.1-1, Examination Category R-A, Risk-Informed Piping Examinations, requires 100% of the exam location to be examined per Figure IWC-2500-7(a) for Item Number R1.11.

IV. Impracticality of Compliance The material is stainless steel. This weld has a wall thickness of 0.281 inches and a nominal pipe size of 1.5 inches.

This weld is required to be examined in accordance with ASME Section XI, Appendix VIII, Supplement 2, 1998 Edition through the 2000 Addenda.

Ultrasonic examination resulted in 77.5% coverage using 450 and 600 shear waves in the axial direction and 380 shear waves in the circumferential direction.

In addition, a supplemental examination from the reducer side was performed using 70* shear waves. This supplemental examination is not included in the percent of coverage because a qualification for examination of the far side of the weld does not exist.

The percentage of coverage reported represents the aggregate coverage from the 380, 450, and 600 scans performed on the weld and adjacent base material.

The coverage from each angle beam scan is shown on the following table.

McGuire Nuclear Station, Unit I Relief Request # 09-MN-006, Rev. 1 Page 3 of 5 Weld Percent of Percent of Primary'Angles Beam Direction Length Volume Coverage Scanned Covered Claimed (inches) 600 shear Axial Reducer 5.97 60 60 Side 450 shear Axial Pipe Side 5.97 50 50 Counter 380 shear Clockwise 5.97 100 100 Reducer Side 380 shear Clockwise Pipe 5.97 100 100 Side Aggregate =77.5%

The aggregate percent coverage obtained is calculated by taking the average of the percentage coverage obtained from each of the 600, 450, and 380 examinations as follows:

(60 + 50 + 100 + 100)/4 = 77.5%

The limitation was caused by the geometry of the taper on the reducer. In order to scan all of the required volume for this weld, the component would have to be redesigned to allow scanning from both sides of the weld, which is impractical.

The McGuire Inservice Inspection Plan allows the use of Code Case N-460, which requires greater than 90% volumetric coverage of Figure IWC-2500-7(a) examination volume C-D-E-F. Therefore, the available coverage will not meet the acceptance criteria of this Code Case.

V. Burden Caused bv ComDliance See section IV, fifth paragraph.

VI. Proposed Alternative and Basis for Use Radiography (RT) is not a desired option because RT is limited in the ability to detect degradation mechanisms such as thermal fatigue cracking and stress corrosion cracking initiating at the pipe inside surface. Additionally, radiography has not been qualified through performance demonstration.

McGuire Nuclear Station, Unit I Relief Request # 09-MN-006, Rev. I Page 4 of 5 An alternate butt weld from within Risk Segment NI-063B cannot be selected for examination in lieu of weld 1NI-231-1 because there is only one other butt weld (1N1270B-1 3) in Risk Segment NI-063B and this weld was examined during refueling outage 1EOC19.

VII. Duration of Proposed Alternative This request is for the duration of the third inservice inspection interval, currently scheduled to end on December 1, 2011.

VIII. Justification for Granting Relief Ultrasonic examination of the weld for the item number M1 .R1.11.0142 was conducted using personnel, equipment, and procedures qualified in accordance with ASME Section XI, Appendix VIII Supplement 2 of the 1998 Edition with the 2000 Addenda as administered by the Performance Demonstration Initiative (PDI). In the case of this piping weld, NRC has imposed requirements for coverage of stainless steel piping welds in 10CFR50.55a (b) (2) (xv) (A) (1). This requires scanning of the weld and adjacent base material from four orthogonal directions. If this requirement cannot be met, then the NRC will not allow credit for coverage on the far side of the weld unless a demonstration test is passed with all flaws being on the far side of the weld. The demonstration requires detection, length sizing, and through wall sizing of flaws with the sound beam passing through the austenitic weld metal. The PDI qualification test could not meet the NRC requirements; therefore credit for full ultrasonic coverage is not claimed.

There were no recordable indications found during the examination of this weld.

The IWC-5220 System Leakage Test performed each inspection period provides adequate assurance of pressure boundary integrity. The VT-2 visual examination performed in conjunction with this System Leakage Test was last completed on October 23, 2008 for the piping segment containing weld #1 N1231-1.

In the event of weldment leakage, early detection capability is afforded by diverse reactor coolant system (RCS) leakage detection instrumentation and routine RCS leakage calculations. Technical Specification 3.4.15 requires the RCS leakage detection instrumentation to be operable during Modes 1-4. The RCS leakage detection instrumentation is comprised primarily of the containment atmosphere particulate radioactivity monitors, containment sump level instrumentation, and the containment ventilation unit condensate drain tank level monitor. Similarly, Technical Specification surveillance requirement 3.4.13.1 requires that a RCS mass balance be performed every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The periodic RCS leakage calculations and diverse RCS leakage detection instrumentation would afford early detection capability in the event of weldment leakage,

McGuire Nuclear Station, Unit I Relief Request # 09-MN-006, Rev. 1

'Page 5 of 5 whereby mitigative actions could be taken prior to catastrophic component failure.

The component weld was examined by volumetric NDE methods during construction and verified to be free from unacceptable fabrication defects.

Based on the above information, it is Duke's position that a reasonable assurance of component integrity exists.

IX. Previous Submittals None.

X. Attachments Ultrasonic examination data for this weld (6 pages) is attached.

VEnergy. UT Pipe Weid Examination Site/Unit: McGuire II Procedure: PDI-UT-2 Outage No.: M1-19 Summary No.: M1.RI.11.0142 Procedure Rev,: C Report No.: UT-08-033 Workscope: ISI Work Order No.: 01783505 Page: 1 of 4 Code: 199812000 Addenda Cat./Item: R-A/R1.11 Location:

Drawing No.: MCFI-1N174

Description:

Full Coupling to Pipe System ID: NI Component ID: 1N1231-1 Size/Length: N/A Thickness/Diameter: 0.281 /1.500 Limitations: Yes - See Attached Limitation Report Start Time: 0940 Finish Time: 0954 Examination Surface: Inside I- Outside O Surface Condition: AS GROUND Lo Location: 9.1,1.4 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 07125 Temp. Tool Mfg.: D.A.S Serial No.: MCNDE32823 Surface TerTnp.: 82" .- F Cal. Report No.: CAL-08-123, CAL-08-124, CAL-08-125, CAL-08-126, CAL-08-127 Angle Used 0 45145T 1 60- 70 38 Scanning dB 40.8 54.0 61.6/63 52.0 Indication(s): Yes f No o Scan Coverage: Upstream . Downstrearr 10, CwL-,]1 ccw g, Comments:

FC 08-01, 08-04 Results: Accept - Reject [] Info J initial Section Xl Exam Percent Of Coverage Obtained > 90%: No Reviewed Previous Data: No I

Date Reviewer g f~ure uare 1011712008 Gayle E Houser Level II 11/8/2008

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Date Site Review ~~J§4~ature S ature LJ~I~

10/17/2008 N/A 10/17/2008 Date ANII Review \ ,nalture , , /h 10/17/2008 1Nancy Ritchie SlauLghter 11/8/2008 11 UI J c> F G

DUKE ENERGY COMPANY ISI LIMITATION REPORT Summary #: M1.RL,11,0142 Component ID IN1231-1 remarks:

[ NO SCAN SURFACE BEAM DIRECTION Due to configuration CLIMITED SCAN -1 2 1M 2 [] cw L]ccw FROM L N/A to L N/A INCHES FROM WO 1.7 to Beyond ANGLE: El 0 El 45 Eg 60 other FROM 0 DEG to 360 DEG F- NO SCAN SURFACE BEAM DIRECTION El LIMITED SCAN El 1 3]2 71 [] 2 [1 cw [] ccw FROM L to L INCHES FROM WO to ANGLE: 13-0 [] 45 El 60 other FROM _ DEG to DEG E" NO SCAN SURFACE BEAM DIRECTION El IMITED SCAN []i 1 02 [1 1El20iCW El CCW FRC)M L to L INCHES FROM WO to DEGto DEG ANGLE: El 0 [] 45 El 60 other FROM BEAM DIRECTION LI NO SCAN SURFACE

[3 LIMITED SCAN El 1 R3 2 Ell [12 [EcwFccw Sketch(s) attached FROM L to L INCHES FROM WO to m1 = fi- No ANGLE: El 0[El 45 El 60 other _ FROM _ DEG to __ DEG_I . y Prepared By: Greg Ra som Level: Date: 10/17/2008 Sheet 2 of 4\ ,/--

Date: Author Reviewed By: H"~( ?11 d Inspector: !

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SUPPleMeri~al J Report Report No.: UT-08-033 Page: 3 of ____"_

Summary No.: M1.Rl11.0142 Examiner: Dean, Steven Level: It-N Reviewer: Date:ý /1.

Examiner: Ransom, Greg J. Level: It-N Site Review: N/A ,. , Date:

Other: N/A Level: N/A ANlt Review: Date:

Comments:

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'Determination of Percent Coverage for P00011.

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DUk(? UT Examinations - Pipe Site/Unit: McGuire / 1 Procedure: PDI-UT-2 Outage No.: M1-19 Summary No.: M1.R1.11.0142 Procedure Rev.: C Report No.: UT-08-033 Workscope: ISI Work Order No.: 01783505 Page: 4 ot 4 45 dae Scan 1 100.000  % Length X 50.000  % volume of length / 100 = 50.000  % total tor Scan 1 Scan 2 100.000  % Length X 0.000  % volume of length / 100 = 0.000  % total for Scan 2 Scan 3 100.000  % Length X 100.000  % volume o1 length / 100 = 100.000  % total for Scan 3 Scan 4 100.000  % Length X 100.000  % volume of length I 100 = 100.000  % total tor Scan 4 Add totals and divide by # scans = 62.500  % total for 45 deg Other deg - 60 (to be used for supplemental scans)

The data to be listed below is for coverage that was not obtained with the 45 deg scans-Scan 1  % Length X  % volume ot length / 100=  % total tor Scan 1 Scan 2 100.000  % Length X 60.000  % volume of length / 100 = 60.000  % total for Scan 2 Scan 3  % Length X  % volume of tength 100 =  % total for Scan 3 Scan 4  % Length X  % volume of length / 100 =  % total lor Scan 4 Percent complete coverage Add totals for each scan required and divide by h of scans to determine;

% Total for complete exam Site Field Supervisor:j4 / /c{c 0 I& , Date: //- 7-0 S"o K' VI

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owe UT Base Metal _. mination Site/Unit: McGuire / 1 Procedure: NDE-640 Outage No.:

• Summary No.: M1 .R1 .11.0142 Procedure Rev.: 4 Report No.: BOP-UT-08-064 Workscope: ISI / 1EOC1 9 Work Order No.: 01783505 Page:. 1 of i-.2C,-":

1'., 7 .

Code: 1998/2000 Addenda Cat./Item: N/A Location: N/A 01-1 .j, Drawing No.: MCFI-1N174

Description:

Full Coupling to Pipe System ID: NI Component ID: 1N1231-1 Size/Length: N/A Thickness/Diameter: .281 / 1.50 Limitations: None Start Time: 0947 Finish Time: 1100 Examination Surface: Inside Outside v.' Surface Condition: AS GROUND Lo Location: 9.1.1.4 Wo Location: Centerline of Weld Couplant: ULTRAGEL II Batch No.: 07125 Temp. Tool Mfg.: D.A.S Serial No.: MCNDE32823 Surface Temp.: 82 -F Scanning dB: 44.1 Cal. Report No.: CAL-08-122 Ind.  % Amplitude Position One Position Max Position Two Loss  % - - - - '-' - . Rerarks No.

Back Wall Full Screen Li W1 W2 MP LM W1 W2 MP L2 Wi W2 MP NRI Comments:

Results: Accept , Reject Into Initial Section X) Exam Percent Of Coverage Obtained > 90%: Yes Reviewed Previous Data: No

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Date Site F 10/16/2008 NfA 10/1 6/2008VA 4-066) AW4X e-

Supplemental Report Report No.: BOP-UT-08-064 k?

Page: 2 oi)

Summary No.: Ml.R1.11.0142 'A Examiner: Ellis II, Kenneth R. Level: I1-N Reviewer: ýf , ,.A Dale: -[z /I/6ý Examiner: N/A Level: N/A Site Review: N/A . , , , Date:-. _____

Other: N/A Level: N/A ANII Review: /0 4#2At J~e Date: __

Comments: ,V.-.

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