View source for ULNRC-06134, Response to Request for Additional Information Relief Request 13R-17, Proposed Alternative to ASME Code, Section XI Requirements, Which Extends Reactor Vessel Inservice Inspection Frequency from 10 Years to 20 Years

{{Adams
| number = ML14232A776
| issue date = 08/20/2014
| title = Response to Request for Additional Information Relief Request 13R-17, Proposed Alternative to ASME Code, Section XI Requirements, Which Extends Reactor Vessel Inservice Inspection Frequency from 10 Years to 20 Years
| author name = Maglio S
| author affiliation = Ameren Missouri
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000483
| license number = NPF-030
| contact person = 
| case reference number = TAC MF3876, ULNRC-06134
| document type = Letter type:ULNRC
| page count = 5
| project = TAC:MF3876
| stage = Response to RAI
}}

=Text=
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WAmeren                                                                                                                                                                                   Callaway Plant MISSOURI August 20, 2014 ULNRC-06134 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 10 CFR 50.55a Ladies and Gentlemen:
DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 UNION ELECTRIC CO.
FACILITY OPERATING LICENSE NPF-30 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RE: RELIEF REQUEST 13R-17, PROPOSED ALTERNATIVE TO ASME CODE, SECTION XI REQUIREMENTS, WHICH EXTENDS REACTOR VESSEL INSERVICE INSPECTION FREQUENCY FROM 10 YEARS TO 20 YEARS (TAC NO. MF3876)
Reference 1.                ULNRC-06093, "Proposed Alternative to ASME Code, Section XI Requirements, Which Extends Reactor Vessel Inservice Inspection Frequency From 10 To 20 Years (ReliefRequest BR-17)," (ADAMS Accession No. ML14098A428) dated April 8, 2013 Reference 2.                NRC Letter "Request for Additional Information Re: Relief Request 13R-17, Proposed Alternative to ASME Code, Section XI Requirements, Which Extends Reactor Vessel Inservice Inspection Frequency From 10 Years To 20 Years (TAC No. MF3876)," (ADAMS Accession No. ML14203A063) dated July 25, 2014 By the Reference 1 letter, Union Electric Company (Ameren Missouri) submitted relief request BR-17 to provide an alternative to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Section XI, "Rules for Inservice Inspection ofNuclear Power Plant Components,"
which would extends the reactor vessel inspection interval from 10 to 20 years. The ASME Code Edition and Addenda applicable to Callaway's third 10-year inservice inspection interval is the 1998 Edition with 2000 Addenda.
By the Reference 2letter, the NRC staff requested additional information needed to complete its review of the relief request. The requested information is provided in the enclosure to this letter.
***************************************************************************************************************************      PO Box 620                  Fulton, MD 65251                    AmerenMissouri.com STARS $            Alliance

ULNRC-06134 August 20, 2014 Page2 This letter does not contain new commitments. If there are any questions, please contact me at 573-676-8719 or Mr. Jerry Doughty at 573-220-5145.
I declare under penalty of perjury that the foregoing is true and correct.
Sincerely, I+
1c~M~~li9 Executed on:     ~ / ~0 /1..o Manager, Regulatory Affairs

==Enclosure:==
Response to Request for Additional Information (TAC No. MF3876)

ULNRC-06134 August 20, 2014 Page 3 cc:    Mr. Marc L. Dapas Regional Administrator U. S. Nuclear Regulatory Commission Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Fred Lyon Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 0-8B 1 Washington, DC 20555-2738

ULNRC-06134 August 20, 2014 Page4 Index and send hardcopy to QA File A160.0761 Hardcopy:
Certrec Corporation 4150 International Plaza Suite 820 Fort Worth, TX 76109 (Certrec receives ALL attachments as long as they are non-safeguards and may be publicly disclosed.)
Electronic distribution for the following can be made via Responses and Reports ULNRC Distribution:
F. M. Diya D. W. Neterer L. H. Graessle B. L. Cox S. A. Maglio T. B. Elwood Corporate Communications NSRB Secretary STARS Regulatory Affairs Mr. John O'Neill (Pillsbury Winthrop Shaw Pittman LLP)

Enclosure to                         Response to Request for Additional ULNRC-06134                            Information (TAC No. MF3876)
Page 1
: 1. Please confirm that the next ASME Code-required volumetric examination of category 8-A and B-0 welds must be performed by the end of the extended third lnservice inspection interval (December 18, 2024).
Callaway Response:
Callaway will perform the next ASME Code-required volumetric examination of category B-A and B-D welds prior to December 18, 2024.
: 2. Please provide the linear inches for the last weld Inspection. Also, please provide the actual area of plate inspected during the last weld inspection.
Callaway Response:
Total length of all the welds requiring volumetric examination: 4950 inches Area of plate actually inspected: 46,600 square inches
: 3. In the license renewal application dated December 15, 2011 (ADAMS Accession No. ML113530374),
page 4.2-9, the value of RTNDTIUI of "Nozzle Shell to Intermediate Shell Weld Seam" is different from the value in this relief request. Please explain this discrepancy.
Callaway Response:
The "Nozzle Shell to Intermediate Shell Weld Seam" from license renewal application dated December 15, 2011 (ADAMS Accession No. ML113530374), page 4.2-9, corresponds to "Nozzle To Inter. Shell Circ. Weld 103-121" in Table 3 of relief request 13R-17. This weld was fabricated with three different weld metal heats. Relief request 13R-171ists details for each heat, while the license renewal application shows a composite of the details, keeping only the most limiting value for each parameter from among the heats as explained in Table 3.5 of WCAP-17168-NP, Revision 0.}}