ML20170A441

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Independent Spent Fuel Storage Installation Updated Decommissioning Safety Analysis Report, DSAR-14.24, Rev. 1, Safety Analysis Heavy Load Incident
ML20170A441
Person / Time
Site: Fort Calhoun, 07100256  Omaha Public Power District icon.png
Issue date: 04/30/2020
From:
Omaha Public Power District
To:
Office of Nuclear Reactor Regulation, Office of Nuclear Material Safety and Safeguards
Shared Package
ML20170A380 List: ... further results
References
LIC-20-0005
Download: ML20170A441 (7)


Text

Page 1 of 7 DSAR-14.24 Safety Analysis Heavy Load Incident Rev 1 Safety Classification: Usage Level:

Safety Information Change No.: EC 68812 Reason for Change: Updated to clarify compliance of the Auxiliary Building crane (HE-2) with ASME NOG-1-2004 and NUREG-0554 per EC 68812.

Preparer: D. Sojka Fort Calhoun Station

DSAR-14.24 Information Use Page 2 of 7 Heavy Load Incident Rev. 1 Table of Contents 14.24.1 General ...................................................................................................... 3 14.24.2 Applicable Industry and Regulatory Requirements .................................... 4 14.24.2.1 DELETED ............................................................................... 4 14.24.2.2 DELETED ............................................................................... 4 14.24.3 DELETED .................................................................................................. 5 14.24.3.1 DELETED ............................................................................... 5 14.24.3.2 DELETED ............................................................................... 5 14.24.4 DELETED .................................................................................................. 5 14.24.5 DELETED .................................................................................................. 5 14.24.6 DELETED .................................................................................................. 5 14.24.7 DELETED .................................................................................................. 5 14.24.8 DELETED .................................................................................................. 5 14.24.9 Specific References ................................................................................... 5 14.24.10 General References ................................................................................... 7

DSAR-14.24 Information Use Page 3 of 7 Heavy Load Incident Rev. 1 Heavy Load Incident 14.24.1 General Reference 14.24.9-1 required a review of the overhead load handling equipment, systems, and procedures to preclude the possibility of a load drop accident.

The consequences of a heavy load drop (HLD) were evaluated for the worst case identifiable loads carried by multiple cranes at FCS and requirements for these cranes were developed to ensure compliance with NUREG-0612.

Due the shutdown and permanent defueling of Fort Calhoun Station, the scope of cranes subject to the requirements of NUREG-0612 is reduced. The cranes listed below remain subject to the requirements of NUREG-0612:

Auxiliary Building Crane (HE-2) 106 Ton Main Hook 10 Ton Auxiliary Hook Deborating Demineralizer Crane Concrete Slab Removal Crane No. 2 Waste Evaporator Equipment Handling Crane Intake Structure Overhead Crane (HE-5)

Compliance with NUREG-0612 credits the administrative restrictions controlling the operation of the cranes. These restrictions are:

1. The Auxiliary Building crane is not used to move material over fuel assemblies in the spent fuel pool. The auxiliary building crane is provided with an electrical interlock system that will normally prevent the trolley from moving over the storage pool. This minimizes the possibility of dropping an object on the irradiated fuel stored in the pool resulting in the release of radioactive products.

The interlocks may be bypassed under strict administrative control to allow required movement of loads over the equipment hatches and areas located in the north and west ends of the auxiliary building and over the railroad siding. The interlocks may be bypassed in these locations since a load even if dropped could not fall into the spent fuel pool. If the crane interlocks are bypassed (or inoperable), a crane supervisor must be present to direct crane operation.

DSAR-14.24 Information Use Page 4 of 7 Heavy Load Incident Rev. 1

2. The auxiliary Building Crane with its main hook is used to move the spent fuel casks into the spent fuel pool. The capacity of the crane lifting system using the main hook is 106 tons to accommodate the current ISFSI spent fuel casks (Reference 14.24.9-5). The design of this lifting system is single failure proof. Therefore, the likelihood of dropping the spent fuel casks into the spent fuel pool or in the auxiliary building is extremely low. The crane, main hook and lifting system meet the requirements of NUREG-0612, NUREG-0554, ANSI-B30.2-1976, Regulatory Guide 1.104, CMAA-70-1975, and ASME NOG-1-2004 as a single failure proof system. See Appendix F Section 2.2.4 for the seismic analysis of the crane.

14.24.2 Applicable Industry and Regulatory Requirements The framework of the District's response to heavy loads was developed by two concurrent efforts identified as Phase I and Phase II. The Phase I/II distinction was made by the NRC. The District's response to both phases was intended to demonstrate an acceptable level of compliance to the "four" evaluation criteria of NUREG-0612.

The purpose of the Phase I response was to identify the load handling equipment within the scope of NUREG-0612 and to describe the pertinent associated load paths, procedures, operator training, special and general purpose lifting devices, the maintenance, testing and repair of equipment and the handling equipment specifications which ensure that the potential for a load drop is extremely small (References 14.24.9-3, 14.24.9-15, 14.24.9-16, 14.24.9-17). An NRC safety evaluation review (SER) was received indicating satisfactory compliance with Phase I requirements (NRC-84-157, Reference 14.24.9-18). Compliance with Phase I requirements is the Fort Calhoun licensing basis for the control of heavy loads.

The Phase II response was intended to demonstrate compliance with the "four" criteria by the use of single-failure-proof handling equipment; stop/interlocks, or other site specific considerations (administrative controls);

or load drop analyses. Compliance with Phase II was rescinded by the NRC (Reference 14.24.9-4). Phase II efforts are considered as enhancements to the Phase I program and do not represent the Fort Calhoun licensing basis.

14.24.2.1 DELETED 14.24.2.2 DELETED

DSAR-14.24 Information Use Page 5 of 7 Heavy Load Incident Rev. 1 14.24.3 DELETED 14.24.3.1 DELETED 14.24.3.2 DELETED 14.24.4 DELETED 14.24.5 DELETED 14.24.6 DELETED 14.24.7 DELETED 14.24.8 DELETED 14.24.9 Specific References 14.24.9-1 USNRC letter signed by Darrell G. Eisenhut dated December 22, 1980 w/enclosures: 1. NUREG-0612, Control of Heavy Loads at Nuclear Power Plants, 2. Staff Position - Interim Actions for Control of Heavy Loads, 3.

Request for Information on Control of Heavy Loads 14.24.9-2 USNRC letter signed by Darrell G. Eisenhut dated February 3, 1981 14.24.9-3 LIC-81-0076 Responses to Section 2.1, dated June 22, 1981 and November 30, 1981, Request for Additional Information on Control of Heavy Loads

DSAR-14.24 Information Use Page 6 of 7 Heavy Load Incident Rev. 1 14.24.9-4 NRC letter NRC-85-0192, June 28, 1985, Thompson Jr. to All Licensees, Completion of Phase II of Control of Heavy Loads at Nuclear Power Plants NUREG-0612. (Generic Letter 85-11) 14.24.9-5 EC 41654, Upgrade of Auxiliary Building Crane HE-2 14.24.9-6 DELETED 14.24.9-7 DELETED 14.24.9-8 DELETED 14.24.9-9 OPPD letter, dated November 14, 1985, Resubmittal of OPPD's Control of Heavy Loads Response 14.24.9-10 DELETED 14.24.9-11 DELETED 14.24.9-12 Not Used 14.24.9-13 Not Used 14.24.9-14 Not Used 14.24.9-15 OPPD Letter No. LIC-82-224, June 2, 1982, Jones to Clark, Phase I response 14.24.9-16 OPPD Letter No. LIC-83-222, September 1, 1983, Jones to Clark, Phase I response 14.24.9-17 OPPD Letter No. LIC-84-091, April 5, 1984, Jones to Miller, Phase I response 14.24.9-18 NRC Letter No. NRC-84-0157, May 22, 1984, Miller to Jones, NRC SER for Phase I Response to Control of Heavy Loads 14.24.9-19 DELETED 14.24.9-20 DELETED 14.24.9-21 DELETED

DSAR-14.24 Information Use Page 7 of 7 Heavy Load Incident Rev. 1 14.24.9-22 DELETED 14.24.9-23 Not Used 14.24.9-24 DELETED 14.24.9-25 DELETED 14.24.9-26 DELETED 14.24.9-27 NRC Regulatory Issue Summary (RIS) 2005-25, Clarification of NRC Guidelines for Control of Heavy Loads, October 31, 2005, with Supplement 1, May 29, 2007 14.24.9-28 NRC Enforcement Guidance Memorandum (EGM) 07-006, Enforcement Discretion for Heavy Load Handling Activities, September 28, 2007 14.24.9-29 DELETED 14.24.9-30 DELETED 14.24.9-31 DELETED 14.24.10 General References 14.24.10-1 Stone and Webster Topical Report, SWECO 7703, Dated Sept. 1977, Missile Barrier Interaction 14.24.10-2 USNRC letter signed by Ashock C. Thadani, dated December 30, 1985 14.24.10-3 EA-FC-95-001, Heavy Load Drop Analysis - Intake Structure 14.24.10-4 OPPD Letter LIC-95-0001, Fort Calhoun Station (FCS),

Cycle 16 Reload Evaluation Report, dated January 20, 1995 14.24.10-5 OPPD Memorandum PED-DEN-96-0385, Transmittal of Reload Evaluation Report, Revision 0, dated August 16, 1996 14.24.10-6 OPPD Calculation FC06968, Revision 0, (AREVA Document 77-5040573-02, FCS RSG - Licensing Report),

FCS RSG - Evaluations for the Impact of the RSG on FCS