ML110540441: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 3: Line 3:
| issue date = 02/23/2011
| issue date = 02/23/2011
| title = Request for Additional Information, Round 2, Relief Request RR-12 from ASME Code Case N-722 Visual Examination Requirements for 4th 10-Year Inservice Inspection Interval
| title = Request for Additional Information, Round 2, Relief Request RR-12 from ASME Code Case N-722 Visual Examination Requirements for 4th 10-Year Inservice Inspection Interval
| author name = Wilkins L E
| author name = Wilkins L
| author affiliation = NRC/NRR/DORL/LPLIV
| author affiliation = NRC/NRR/DORL/LPLIV
| addressee name = Hansher B
| addressee name = Hansher B

Revision as of 23:26, 10 July 2019

Request for Additional Information, Round 2, Relief Request RR-12 from ASME Code Case N-722 Visual Examination Requirements for 4th 10-Year Inservice Inspection Interval
ML110540441
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 02/23/2011
From: Lynnea Wilkins
Plant Licensing Branch IV
To: Hansher B
Omaha Public Power District
Wilkins, L E, NRR/DORL/LPL4, 415-1377
Shared Package
ML110540438 List:
References
TAC ME4541
Download: ML110540441 (1)


Text

From: Wilkins, Lynnea Sent: Wednesday, February 23, 2011 9:47 AM To: HANSHER, BILL R Cc: Lent, Susan; Burkhardt, Janet

Subject:

DRAFT 2nd RAI for Fort Calhoun Station, Unit 1 Relief Request (TAC No. ME4541) Attachments: ME4541 2nd RAI.docx Bill, By letter dated August 16, 2010 as supplemented by letter dated January 14, 2011, (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML102300641 and ML110200193), Omaha Public Power District proposed an alternative to 10 CFR 50.55a(g)(6)(ii)(E) for the Fort Calhoun Station, Unit 1. This requirement defines the inservice inspection frequency of visual examination of the reactor vessel hot leg nozzle to safe end welds in accordance with American Society of Mechanical Engineer's Boiler and Pressure Vessel Code Case N-722, "Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated With Alloy 600/82/182 Materials," and with Nuclear Regulatory Commission (NRC) conditions. The duration of request is for the fourth 10-year ISI interval which ends on September 25, 2013.

The NRC staff has reviewed your submittal and has determined that the information specified in the attached draft Request for Additional Information (RAI) is needed for the staff to complete its evaluation.

Please contact me if a clarifying teleconference is needed for the attached RAIs.

Thank You

Lynnea Wilkins, Project Manager Fort Calhoun Station, Unit 1 Cooper Nuclear Station Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Phone: 301-415-1377