ML16237A347

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License Renewal Interim Staff Guidance, LR-ISG-2016-01, Changes to Aging Management Guidance for Various Steam Generator Components.
ML16237A347
Person / Time
Issue date: 12/07/2016
From: Benjamin Beasley
Division of License Renewal
To: Hanson J
Nuclear Energy Institute
Seung Min, NRR/DLR, 415-2045
References
LR-ISG-2016-01
Download: ML16237A347 (4)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 7, 2016 Mr. Jerud Hanson Nuclear Energy Institute 1201 F St., NW, Suite 1100 Washington, DC 20004-1218

SUBJECT:

LICENSE RENEWAL INTERIM STAFF GUIDANCE, LR-ISG-2016-01, CHANGES TO AGING MANAGEMENT GUIDANCE FOR VARIOUS STEAM GENERATOR COMPONENTS

Dear Mr. Hanson:

On June 7, 2016, the U.S. Nuclear Regulatory Commission (NRC) published in the Federal Register (81 FR 36612) a request for public comment on draft License Renewal Interim Staff Guidance (LR-ISG), LR-ISG-2016-01, Changes to Aging Management Guidance for Various Steam Generator Components. In response, the Nuclear Energy Institute (NEI) submitted comments by letter dated July 7, 2016, available in the NRCs Agencywide Documents Access and Management System (ADAMS) at Accession No. ML16194A026. The NRC has reviewed and dispositioned the public comments as discussed in Appendix C of the final LR-ISG-2016-01.

The major changes to aging management guidance in this LR-ISG are: (a) addition of visual inspections of steam generator head internal areas to the Generic Aging Lessons Learned (GALL) Report,Section XI.M19, Steam Generators, to detect signs of cracking or loss of material (e.g., detection of rust stains and gross cracking or distortion); (b) changes to the Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants (SRP-LR), Sections 3.1.2.2.11 and 3.1.3.2.11, Cracking due to Primary Water Stress Corrosion Cracking, that describe further evaluation regarding primary water stress corrosion cracking (PWSCC) in divider plate assemblies and tube-to-tubesheet welds; and (c) changes to the aging management review items in the GALL Report and SRP-LR for managing cracking due to PWSCC in divider plate assemblies and tube-to-tubesheet welds and loss of material due to boric acid corrosion in steam generator heads (interior surfaces) and tubesheets (primary side).

If a licensee demonstrates that industry generic analyses (EPRI Report 3002002850) are applicable and bounding for its unit, a plant-specific program (e.g., one-time inspection program) to ensure that cracking is not occurring in the divider plater assembly and tube-to-tubesheet welds is not necessary in accordance with the revised guidance in SRP-LR, Sections 3.1.2.2.11 and 3.1.3.2.11.

A Federal Register notice announcing the issuance of LR-ISG-2016-01 has been published (81 FR 88276). Also, courtesy copies of this letter are being sent to subscribers of an NRC electronic mailing list on general license renewal topics.

We will make corresponding changes to the aging management guidance for the subsequent license renewal period (i.e., up to 80 years of operation), which is documented in draft NUREG-2191, Generic Aging Lessons Learned for Subsequent License Renewal Report (GALL-SLR),

and draft NUREG-2192, Standard Review Plan for Review of Subsequent License Renewal for Nuclear Power Plants.

J. Hanson If you have any questions, please contact Dr. Seung Min of my staff by telephone at 301-415-2045 or by e-mail at Seung.Min@nrc.gov.

Sincerely,

/RA/

Benjamin G. Beasley, Acting Deputy Director Division of License Renewal Office of Nuclear Reactor Regulation

Enclosure:

Final LR-ISG-2016-01 cc: Reactor License Renewal Stakeholder GovDelivery

ML16237A390 (Package), ML16237A347 (Letter), ML16237A383 (LR-ISG)

ML16239A069 (FRN) *concurrence via email OFFICE ME:DLR:RARB STA:NRR/DE STA:NRR/DLR BC:DLR:RSRG NAME SMin *KKarwoski *AHiser SBloom DATE 8/16/2016 8/16/2016 8/22/2016 9/23/2016 OFFICE BC:DLR:RARB LA:DLR:RPB1 OGC DD:DLR (Acting)

NAME DMorey *IBetts STurk BBeasley DATE 9/28/2016 8/31/2016 10/30/2016 11/30/2016 OFFICE DD:DLR (Acting)

NAME BBeasley DATE 12/7/16

Letter to J. Hanson from B. Beasley dated December 7, 2016.

SUBJECT:

LICENSE RENEWAL INTERIM STAFF GUIDANCE, LR-ISG-2016-01, CHANGES TO AGING MANAGEMENT GUIDANCE FOR VARIOUS STEAM GENERATOR COMPONENTS DISTRIBUTION:

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