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Category:Letter
MONTHYEARML24023A0392024-01-22022 January 2024
NEI Comments on the Information Collection Renewal for Domestic Licensing of Special Nuclear Material, Docket Id NRC-2023-0118
ML23355A1972023-12-14014 December 2023
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ML23135A7332023-05-0909 May 2023
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ML23110A6752023-04-18018 April 2023
04-18-23_NRC_Fee Waiver for NEI 23-03
ML23110A6782023-04-18018 April 2023
Request for Review and Endorsement of NEI 23-03, Supplemental Guidance for Application of 10 CFR 50.59 to Digital Modifications at Non-Power Production or Utilization Facilities
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ML23107A2302023-03-31031 March 2023
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ML23138A1662023-03-24024 March 2023
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ML23083B4622023-03-24024 March 2023
Transmittal of NEI 22-05 Revision a, Technology Inclusive Risk Informed Change Evaluation (Tirice) Guidance for the Evaluation of Changes to Facilities Utilizing NEI 18-04 and NEI 21-07
ML23060A3272023-03-0101 March 2023
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ML23023A2752023-01-23023 January 2023
Request for Extension of Comment Period from the Nuclear Energy Institute on PRM-50-124 - Licensing Safety Analysis for Loss-of-Coolant Accidents
ML22348A1122023-01-17017 January 2023
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ML22353A6082023-01-11011 January 2023
U.S. Nuclear Regulatory Commission Report of the Regulatory Audit of the NEI-Proposed Aging Management Program Revision to Selective Leaching Program (XI.M33)
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ML22336A0372022-11-16016 November 2022
Fee Exemption Request for NEI 08-09 Revision 7 - Changes to NEI 08-09 Cyber Security Plan for Nuclear Power Reactors
ML22321A3152022-11-16016 November 2022
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ML22298A2262022-10-25025 October 2022
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ML22298A2302022-10-17017 October 2022
Submittal of NEI 22-03, Draft Revision 0, Nuclear Generation Quality Assurance Program Description
ML22207B6512022-07-26026 July 2022
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ML22195A0202022-07-13013 July 2022
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ML22195A0672022-07-13013 July 2022
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ML22159A2772022-06-28028 June 2022
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ML22110A1782022-04-0101 April 2022
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ML21342A2032021-10-29029 October 2021
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ML22081A2002021-10-29029 October 2021
NEI Backfitting Concerns with NRCs Developing Position on Protection of Dry Storage Systems from Natural Phenomena During Short Term Operations
2024-01-22
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May 27, 2008 Mr. Thomas C. Houghton, Director Strategic Regulatory Programs, Nuclear Generation Division Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708
SUBJECT:
INDUSTRY INITIATIVE ON CONTROL OF HEAVY LOADS
Dear Mr. Houghton:
I am writing to clarify the approaches the Nuclear Regulatory Commission (NRC) staff considers acceptable for interim analyses, which I described in my letter to you dated May 16, 2008. In a telephone conversation on May 20, 2008, you indicated to me that the need to evaluate the reactor vessel supports and attached piping in completing interim analyses for reactor vessel head lifts over flooded refueling cavities was unclear.
The staff recognizes that facility owners that ultimately intend to develop more detailed load drop analyses using energy balance methods or enhance the reliability of the handling system to single failure proof crane equivalence may need additional time to complete such efforts.
Therefore, development of an interim analysis may be necessary and is an acceptable approach. As I stated in my letter dated May 16, 2008, licensees may perform these interim analyses for reactor vessel head lifts over flooded refueling cavities that conform to the proposed analysis guidelines contained in Industry Criteria for Reactor Vessel Head Load Drop and Consequence Analysis, which is in the NRC Agencywide Documents Access and Management System (ADAMS) as Accession No. ML081300340.
Many existing analyses completed since the late 1970s generally conform to these guidelines, with the exception that component supports and attached piping were not explicitly considered.
Instead, the analyses assumed the reactor vessel supports were rigid, which is bounding with respect to stresses developed in the reactor vessel near the supports. These analyses considered form drag as the head moved through water, but neglected surface and hydraulic effects that are certain to further reduce the impact forces. The staff considers the margin provided by the neglected surface and hydraulic effects adequate to ensure reactor vessel support and loop piping stresses would remain within allowable limits. Therefore, these analyses are acceptable for use as the basis for comparative analyses when the refueling cavity will be flooded (i.e., the lower of fully flooded or flooded to within 15 feet of the bottom of the reactor vessel head whenever the head is above the guide studs) during the reactor vessel head lift. These comparative (parametric) analyses for lifts over flooded refueling cavities need only consider differences in reactor head lift height, head assembly weight, reactor vessel material properties, and reactor vessel and head geometry. However, the NRC staff understands these analyses will only be used on an interim basis during the period necessary to either complete more detailed load drop analyses using energy balance methods or enhance the reliability of the handling system to single failure proof crane equivalence.
From your letter dated April 22, 2008, we understand that you will combine into a single industry guideline the guidance documents related to load drop analyses and single failure proof crane equivalence with guidance on updating the plant Final Safety Analysis Report (FSAR) to reflect
T. C. Houghton the current licensing basis with respect to control of heavy loads. We consider this latter guidance essential to support clear updates to the FSAR and a more consistent licensing basis.
For planning purposes in support of potential NRC endorsement through a Regulatory Issue Summary, please inform us of your schedule for completion of the combined industry guideline.
The NRC staff appreciates your continued interest in implementation of your initiative on heavy load handling. Please contact Mr. Steven Jones of the NRC staff at (301) 415-2712 to discuss any other concerns.
Sincerely,
/RA/
William H. Ruland, Director Division of Safety Systems Office of Nuclear Reactor Regulation PROJ: 689 cc: See Next Page
T. C. Houghton the current licensing basis with respect to control of heavy loads. We consider this latter guidance essential to support clear updates to the FSAR and a more consistent licensing basis.
For planning purposes in support of potential NRC endorsement through a Regulatory Issue Summary, please inform us of your schedule for completion of the combined industry guideline.
The NRC staff appreciates your continued interest in implementation of your initiative on heavy load handling. Please contact Mr. Steven Jones of the NRC staff at (301) 415-2712 to discuss any other concerns.
Sincerely,
/RA/
William H. Ruland, Director Division of Safety Systems Office of Nuclear Reactor Regulation PROJ: 689 cc: See Next Page DISTRIBUTION:
PUBLIC PROJ0689 Rids NrrAdes RidsNrrDss RidsNrrDe RidsNrrDpr DHarrison SJones Accession No.: ML081410597 OFFICE DSS/SBPB DSS/SBPB:BC DSS:DD NAME SJones DHarrison WRuland DATE 5/23/08 5/27/08 5/27/08 OFFICIAL RECORD COPY
T. Nuclear Energy Institute Project No. 689 cc:
Mr. Anthony Pietrangelo, Vice President Mr. Alexander Marion, Executive Director Regulatory Affairs Nuclear Operations & Engineering Nuclear Energy Institute Nuclear Energy Institute 1776 I Street, NW, Suite 400 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 Washington, DC 20006-3708 arp@nei.org am@nei.org Mr. Jack Roe, Director Mr. John Butler, Director Operations Support Safety-Focused Regulation Nuclear Energy Institute Nuclear Energy Institute 1776 I Street, NW, Suite 400 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 Washington, DC 20006-3708 jwr@nei.org jcb@nei.org Mr. Charles B. Brinkman Mike Melton, Senior Project Manager Washington Operations 1776 I Street, NW, Suite 400 ABB-Combustion Engineering, Inc. Washington, DC 20006-3708 12300 Twinbrook Parkway, Suite 330 man@nei.org Rockville, MD 20852 brinkmcb@westinghouse.com Dennis Buschbaum PWROG Chairman Mr. James Gresham, Manager Comanche Peak Steam Electric Station Regulatory Compliance and Plant Licensing 6322 North Farm to Marked Rd 56 Westinghouse Electric Company Mail Code E15 P.O. Box 355 Glen Rose, TX 76043 Pittsburgh, PA 15230-0355 Dennis.Buschbaum@luminant.com greshaja@westinghouse.com Mr. James H. Riley, Director Ms. Barbara Lewis Engineering Assistant Editor Nuclear Energy Institute Platts, Principal Editorial Office 1776 I Street, NW 1200 G St., N.W., Suite 1100 Washington, DC 20006-3708 Washington, DC 20005 jhr@nei.org Barbara_lewis@platts.com 3/25/08