Text

Relief Request (RR) 05-MN-003, Response to Request for Additional Information
	ML070940298
Person / Time
Site:	Mcguire
Issue date:	03/26/2007
From:	Gordon Peterson; Duke Energy Carolinas, Duke Power Co
To:	; Document Control Desk, NRC/NRR/ADRO
References
	RR 05-MN-003
	Download: ML070940298 (16)
	v • d • e

PDuke Power A Duke Energy Company GARY R. PETERSON Vice President McGuire Nuclear Station Duke Power MG01VP / 12700 Hagers Ferry Rd.

Huntersville, NC 28078-9340 704 875 5333 704 875 4809 fax grpeters@duke-energy. com March 26, 2007 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001

Subject:

Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC (Duke)

McGuire Nuclear Station Unit 2 Docket No. 50-370 Relief Request (RR) 05-MN-003 Response to Request for Additional Information This letter provides the additional information requested by the NRC staff via electronic mail from John F. Stang. The NRC staff's questions and Duke's responses are provided in Enclosure 1.

Duke requests that the proprietary drawings in Attachment 1 of Enclosure 1 be withheld from public disclosure pursuant to 10 CFR 2.390 Questions on this matter should be directed to Kenneth L. Ashe, McGuire Regulatory Compliance, at (704) 875-4535.

Sincerely, G.R. Peterson Enclosure Aoq ?

www. dukepower. corn

U.S. Nuclear Regulatory Commission March 26, 2007 Page 2 cc w/

Enclosure:

Mr. W.D. Travers Regional Administrator, Region II U. S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303 Mr. J.F. Stang Jr., Project Manager Office of Nuclear Reactor Regulation

U. S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08-H4A 11555 Rockville Pike Rockville, MD 20852-2738 Mr. J.B. Brady Senior Resident Inspector U.S. Nuclear Regulatory Commission McGuire Nuclear Station

Enclosure Response to RAI for Relief Request 05-MN-003

1. Please provide drawings or sketches of the American Society of Mechanical Engineers (ASME) Code,Section XI, Category B-A and B-F components listed on pages 1 and 2 of RR 05-MN-003.

Response: Attachment 1 to this enclosure includes the Duke Energy drawings for the following components listed on RR 05-MN-003.

Weld: 2RPV-W03 Weld: 2RPV-WO1 Weld: 2RPV-W15-SE Weld: 2RPV-W 17-SE Weld: 2RPV-W 18-SE Weld: 2NC2F-1 -1.

Weld: 2NC2F-3-1 Weld: 2NC2F-4-1 Drawings: MCM 2201.01-0001 001 and MCM 2201.01-0019 001 Drawings: MCM 2201.01-0001 001 and MCM 2201.01-0019 001 Drawings: MCM 2201.01-0018 001, MCM 2201.01-0019 001, MCM 2201.01-0010 sh.1, and MCM 2201.01-0010 002 Drawings: MCM 2201.01-0018 007, MCM 2201.01-0019 001, MCM 2201.01-0010 sh.1, and MCM 2201.01-0010 002 Drawings: MCM 2201.01-0018 010, MCM 2201.01-0019 001, MCM 2201.01 -0010 sh.1, and MCM 2201.01-0010 002 Drawings: MCM 2201.01-0018 001, MCM 2201.01-0019 001, MCM 2201.01-0010 sh. 1, and MCM 2201.01-0010 002 Drawings: MCM 2201.01-0018 007, MCM 2201.01-0019 001, MCM 2201.01-0010 sh.1, and MCM 2201.01-0010 002 Drawings: MCM 2201.01-0018 010, MCM 2201.01-0019 001, MCM 2201.01 -0010 sh.1, and MCM 2201.01-0010 002 The corresponding ASME figure numbers are listed in Column III (Code Requirement from Which Relief is Requested) of pages 1 and 2 on RR 05-MN-003. In addition, Attachment 6 of the RR 05-MN-003 submittal showed additional information addressing these welds.

2. It was noted in your submittal dated May 12, 2006, that the second 10 year inservice inspection (ISI) interval start date was December 1, 2001 and ends on December 1, 2011. Please confirm that RR 05-MN-003 is for the second 10-year ISI interval as compared to your operating licensee issue date March 3, 1983, which would be the beginning of the first 10-year ISI interval.

Response: RR 05-MN-003 is for the second 10-year ISI interval. The interval dates listed in RR 05-MN-003 are incorrect. The correct dates for the second interval start and end are March 1, 1994 and June 1, 2005, respectively. Note the NRC approved an extension of the second interval to "on or before June 1, 2005" in a letter dated July 20, 2004 in response to RR 03-004. An updated page 1 of 8 in the attachment to Duke's letter dated May 12, 2006 is included as Attachment 2 to this enclosure.

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3. It was noted in your submittal dated May 12, 2006 for welds Weld Nos.

2NC2F-1-1, 2NC2F-3-1, and 2NC2F-4-1 were classified as dissimilar metal welds under ASME Code,Section XI Category B-F. In Paragraph D of the May 12, 2006, submittal the material for the Reactor Pressure Vessel pipe-to-safe end weld is referenced as stainless steel. Please clarify material type for Weld Nos. 2NC2F-1 -1, 2NC2F-3-1, and 2NC2F-4-1 and the adjacent base metal.

Response: Weld Nos. 2NC2F-1-1, 2NC2F-3-1, and 2NC2F-4-1 are stainless steel welds that attach the stainless loop piping to the stainless safe ends. The loop piping was fabricated from cast stainless steel. The safe-ends were fabricated by depositing stainless steel type 309S butter and stainless steel type 308L weld metal onto the carbon steel nozzle material with subsequent post weld heat treatment.

Note that there are two (2) welds within close proximity to each other at these locations. The stainless welds listed above were conservatively categorized as B-F welds because of their close proximity to the dissimilar metal weld and the carbon steel base material of the nozzle. By categorizing these welds as B-F they receive 100% inspection rather than a 25% sample under category B-J. (Reference original relief request submittal Attachment 6, page 3 of 4 for figures showing the two welds.)

4. For each request number 1 through 8 listed on pages 1 and 2 of RR 05-MN-003 the ASME Code requirement was not stated in the licensee's request for relief as to which ASME Code requirement the licensee was seeking relief. Please state the ASME Code requirement for each number that relief is being requested pursuant to Code of Federal Regulations 50.55a(g)(5)(iii).

Response: ASME Code paragraph IWB-2500(a) requires components to be examined and tested as specified in Table IWB-2500-1. The table identifies a figure number, associated with each examination item number, which provides the required examination volume dimensions. Specifically, Duke seeks relief from obtaining the full volume required by these figures.

Please reference the table shown on pages 1 and 2 of RR 05-MN-003 in which the figure numbers for which Duke seeks relief from code requirements is shown in Column III for each weld.

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5. For ASME Code,Section XI, Categories and Items numbers where both a volumetric and surface examination is required please provide the coverage obtained for the surface examination.

Response: Listed below are the surface examinations for welds listed under the Relief Request. Surface exams on nozzle welds were performed earlier in the interval with acceptable results.

Weld: 2RPV-W03 Weld: 2RPV-W01 Weld: 2RPV-W15-SE Weld: 2RPV-W 17-SE Weld: 2RPV-W18-SE Weld: 2NC2F-1-1 Weld: 2NC2F-3-1 Weld: 2NC2F-4-1 No Surface exam required per code No Surface exam required per code Examined 11/27/1994 100% Surface Examined 11/30/1994 100% Surface Examined 12/01/1994 100% Surface Examined 11/27/1994 100% Surface Examined 11/30/1994 100% Surface Examined 12/01/1994 100% Surface 0

3 Component Drawings in Response to RAI Question 1 Updated Page 1 of 8 in Response to RAI Questions 2 and 4

Request Relief 05-MN-003 Page 1 of 8 Proposed Relief in Accordance with 10 CFR 50.55a(g)(5)(iii), Inservice Inspection Impracticality Duke Energy Corporation McGuire Nuclear Station - Unit 2 (EOC-16)

Second 10-Year Interval - Inservice Inspection Plan Interval Start Date= March 1, 1994 Interval End Date= June 1, 2005 ASME Section XI Code - 1989 Edition with No Addenda Code Case N-460 is applicable Examination Dates October 6, 2003-April 14, 2005 I.-

IH.

IV. & V.

VI.

ViI.

VIII.

Request Limited System Code Requirement from Which Relief is Impracticality/

Proposed Implementation Justification for Number Area/Weld I.D.

Component for Which Relief is Requested:

Burden Caused Alternate Schedule and Granting Relief Number Requested:

100% Exam Volume Coverage by Compliance Examinations or Duration Area or Weld to be Examined Exam Category Testing Item No.

Fig. No.

Limitation Percentage

1.

2RPV-W03 NC System Exam Category B-A See Paragraph See Paragraph "E" See Paragraph See Paragraph Reactor Vessel Lower Shell to Lower Item No. BO 1.011.003 "A"

"F' "G"

Head Circumferential Weld Fig. IWB-2500-1 See Attachment I See Attachment 1 72.76% Volume Coverage Pages 1-40 Pages 1-40 Page 1 Page I

2.

2RPV-W0I NC System Exam Category B-A See Paragraph See Paragraph "E" See Paragraph See Paragraph Reactor Vessel Lower Head to Bottom Item No. B01.021.002 "B"

"F' "H"

Head Circumferential Weld Fig. IWB-2500-3 See Attachment 2 See Attachment 2 87.19% Volume Coverage Pages 1-81 Pages 1-81 Page 2 Page 2

3.

2RPV-WI5-SE NC System Exam Category B-F See Paragraph See Paragraph "E" See Paragraph See Paragraph "I" Reactor Vessel Outlet Nozzle to Safe Item No. B05.010.005 and B05.010.005A "C"

"F" See Attachment 3 End Weld (22 degrees)

Fig. IWB-2500-8 See Attachment 3 Pages 1-7 84.38% Volume Coverage Pages 1-7 Page 3 Page 3

4.

2RPV-WI7-SE NC System Exam Category B-F See Paragraph See Paragraph "E" See Paragraph See Paragraph "I" Reactor Vessel Outlet Nozzle to Sate Item No. B05.010.007 and B05.010.007A "C".

"F' See Attachment 4 End Weld (202 degrees)

Fig. IWB-2500-8 See Attachment 4 Pages 1-7 80.24% Volume Coverage Pages 1-7 Page 3 Page 3

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