View source for ONS-2014-053, Response to Request for Additional Information (RAI) Regarding the Fourth Ten Year Interval ISI Plan, Relief Request 13-ON-001 (ADAMS Accession No. ML14040A014)

{{Adams
| number = ML14107A035
| issue date = 04/10/2014
| title = Response to Request for Additional Information (RAI) Regarding the Fourth Ten Year Interval ISI Plan, Relief Request 13-ON-001 (ADAMS Accession No. ML14040A014)
| author name = Batson S
| author affiliation = Duke Energy Carolinas, LLC
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000287
| license number = DPR-055
| contact person = 
| case reference number = ONS-2014-053
| document type = Letter type:ONS
| page count = 5
| project = 
| stage = Response to RAI
}}

=Text=
{{#Wiki_filter:I Scott L. Batson DUKE                                                                                Vice President Oconee Nuclear Station ENERGY.                                                                             Duke Energy ONO1VP 17800 RochesterHwy Seneca, SC 29672 o: 864.873.3274 f 864.873. 4208 ONS-2014-053                                                                 Scott.Batson@duke-energy.com April 10, 2014 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

==Subject:==
Duke Energy Carolinas, LLC (Duke Energy)
Oconee Nuclear Station Units 3 Docket Numbers 50-287 Response to Request for Additional Information (RAI) regarding the Fourth Ten Year Interval ISI Plan, Relief Request 13-ON-001 (ADAMS Accession No. ML14040A014)
On September 26, 2013, Duke Energy submitted Relief Request 13-ON-001 (ADAMS Accession No. ML13273A037) pursuant to 10 CFR 50.55a(g)(5)(iii), requesting that NRC grant relief from the requirement to examine 100% of the volume specified by the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code). On February 7, 2014, the NRC submitted a Request for Additional Information electronically (via E-mail) regarding this Relief Request. The Duke Energy response to the RAI questions is attached as an enclosure.
There are no regulatory commitments associated with this letter.
If you have any questions concerning this letter, or require additional information, please contact Corey Gray at (864) 873-6325.
Sincerely, Scott L. Batson Vice President Oconee Nuclear Station

==Enclosure:==

Oconee Nuclear Station Unit 3, Duke Energy's Response to Request for Additional Information (RAI), Relief Request 13-ON-001, 3EOC-26 Limited Weld Examinations Ake04vr

'U. S. Nuclear Regulatory Commission April 10, 2014 Page 2 xc:
Mr. Victor McCree, Regional Administrator U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 Mr. James R. Hall, Project Manager (ONS)
(by electronic mail only)
U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop O-8B1 Rockville, MD 20852 Mr. Eddy Crowe NRC Senior Resident Inspector Oconee Nuclear Station Susan Jenkins Section Manager Division of Waste Management SC Dept. of Health & Environment Control 2600 Bull St.
Columbia, SC 29201

Enclosure Oconee Nuclear Station Unit 3 Duke Energy's Response to Request for Additional Information (RAI)
Relief Request 13-ON-001 3EOC-26 Limited Weld Examinations Page 1 HAl / 13-ON-001 RAI/  13-ON-OQi Response Response                                              Page 1

DUKE ENERGY'S REPONSE to REQUEST for ADDITIONAL INFORMATION

===RAI-1===
Request for Relief 13-ON-001, Sections 6 & 7, ASME Code, Section XI, Examination Category B-J, Unit 3 Piping Welds, Low Pressure Injection System, Pipe to Valve (3CF-11
& 3CF-14), Welds 3-53A-15-26 & 3CF-126-4, Summary Numbers 03.B9.11.0106 &
03.B9.11.0129, ASME Code Class 1.
: a. State the active degradation mechanisms for welds 3-53A-15-26 and 3CF-126-4, if any.
Duke reply: These welds were examined to satisfy the requirements of ASME Section XI, IWB-2500, Examination Category B-J, which does not require a degradation mechanism determination. See RAI-1 (c) below for additional information.
: b. Are the welds part of a risk informed inservice inspection program?
Duke reply: No
: c. Is there any operational experience showing inservice cracking of similar welds exposed to similar environmental conditions?
Duke reply: A search was performed for cracking on these welds and similar welds, in our ISI database and the Duke Corrective Action Program and none was found.

===RAI-2===
Request for Relief 13-ON-001, Section 8 ASME Code, Section XI, Examination Category C-A, Item CI.30 Pressure Retaining Welds in Vessels for ON, Unit 3 Steam Generator A, Feedwater System, Tubesheet-to-Shell Weld # 3-SGA-W69 Summary Number 03.Cl.30.0002, ASME Code Class 2.
The NRC staff notes that in RR 13-ON-001, Section 8, conflicting examination methodologies are stated in the following subsections:
        " In Paragraph 8.4, "Impracticability of Compliance," it is stated that, "scanning requirements are described in ASME Code, Section V, Article 4 T-441.1.2(a),
T-441.1.3, T-441.1.4, T-441.1.5, and T-441.1.6."
* In Paragraph 8.5, "Proposed Alternative and Basis for Use," it is stated that "this weld was examined using procedures, equipment and personnel qualified in accordance with ASME Code, Section XI, Appendix VIII."
        " It is also stated in Attachment "A", UT Calibration Examination Sheet (Page 81 of 96),
that Procedure NDE-640 was used.
Please clarify what examination methodologies were used in examining Tubesheet-to-Shell Weld # 3-SGA-W69.
Duke Reply: This weld was inspected in accordance with ASME Section V, Article 4 requirements, as modified by ASME Section XI, Article 1, Table 1-2000-1. Code required examinations were performed using Procedure NDE-820 and appropriately qualified personnel.
A supplemental "zero degree" exam was performed using Procedure NDE-640 and appropriately qualified personnel, in addition to the Code required examinations. No flaws were detected in either exam.
RAI/ 13-ON-001 Response                                                                 Page 2

I  , REGULATORY CORRESPONDENCE                                 I                           AD-L-S-ALL-0002 I                                                 Rev. 0 1 Outgoing Regulatory Correspondence                       ATTACHMENT 2 Review & Approval Documentation                        Page 2 of 4 Reviewer I Approver           Title I Organization          Signature, email, or telecom          Date Gary Scarboro                  Sr Tech Spc / ASME           See ASME Services Review Form            4-314 Sect XI Services             (attached)
Ned Finney Jr                  Lead Nuc NDE Spc I           See ASME Services Review Form ASME Sect XI Services        (attached)                              3-31-14 Sandy Clark                    Lead Engr / ASME Sect        See ASME Services Review Form XI Services                  (attached)                               4-3-14 Lester Stauffer                Lead Nuc NDE Spc /           See ASME Services Review Form Fleet Program Engr           (attached)                              3-31-14 Manager / Nuc Engr           See ASME Services Review Form Mark Pyne                      Support                      (attached)                               4-3-14 Reg. Affairs Lead:             Lead Engr / Reg Affairs David Haile Peer Reviewer (Optional):          Al/A                                   4L-                       v.)/
                                                                                                    " //4 Christopher J. Wasik           Manager I Reg. Affairs                       ,y/(                         /I'y Terry Patterson                Director I-Bob Guy                        Director I Site Support Signature Authority               Site Vice President                (Signs the letter)
Oath or Affirmation required on cover letter or enclosures?          YES 0           NO 0 Return To:    David Halle                                               864-873-4742 Regulatory Affairs Lead                                   Extension}}