ML20037D200

Advises That Review Program Is Underway to Determine If Facility Heavy Load Handling Sys Comply w/NUREG-0612. Facility Operating Staff Will Write & Implement Procedures for Operator Training/Qualification & Crane Insp & Maint

ML20037D200
Person / Time
Site:	Clinton
Issue date:	05/18/1981
From:	Wuller G ILLINOIS POWER CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
RTR-NUREG-0612, RTR-NUREG-612 L30-81(05-81)-L, L30-81(5-81)-L, U-0234, U-234, NUDOCS 8105220212
Download: ML20037D200 (2)

Text

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'\\, s% r .w \\ 4.i*!~e, f [Q f j-y h f/ ? v-Mr. Darrell G. Eisenhut, Director Division of Licensing V/ JP Office of Nuclear Reactor Regulation Y(5 / / l ft \\ ' ~~ United States Nuclear Regulatory Commission Washington, D. C. 20555

Reference:

Your letter, dated December 22, 1980, regarding the subject of " Control of Heavy Loads" Clinton Power Station Units 1 & 2 Docket Nos. 50-461 and 50-462 A review program is underway to determine if the Clinton Power Station's heavy load handling systems comply with the provisions of NUREG 0612. Clinton's BWP 6, Mark III design obviates the majority of concerns addressed in NUREG 0612. Cranes, lifting devices, and refueling platforms used to make critical lifts are single-failure proof. The plant layout provides for..nysical separation of safe shutdown equipment, thereby eliminating the possibility of damage to redundant systems from a single load drop. Mechanical stops prevent the fuel building crane from traveling over the spent fuel pool, whose fuel storage racks are of the boral poison can design. Also, a fuel cask drop analysis has been per-formed. The conclusions are state 6. in Section 15.7.5 of the CPS-FSAR. The Clinton Power Station operating staff will write and implement procedures, in accordance with NUREG 0612, for crane operator training and qualification, as well as crane inspection, i testing, and maintenance to support a January 1983 fuel load date. For simplification purposes, IP has categorized the handling systems into four groups for the purpose of eliminating non-problem systems and to highlight systems which will require in-depth study. These categories are: 1. Single-failure proof handling system designs. 2. Handling systems which are not operated near safe shut-down equipment, spent fuel, or the reactor. l s ll0 f 8105220p.l>

4* U-0234 L30-81(05-18)-L Mr. Darrell G. Eisenhut Page 2 May 18, 1931 3. Handling systems which are not operated near safe shutdown equipment, spent fuel, or the reactor, but do not pose a danger for one or more reasons. 4. All those handling systems remaining, which will be-analyzed on an individual basis. Our continuing activities will be to focus on category 4, and to prepare a comprehensive response to meet the requirements of the NRC June 22, 1981, six-month deadline. Sincerely, G. E. Wuller Supervisor--Licensing Nuclear Station Engineering SWS:ks cc: C. I. Grimes, NRC Clinton Project Manager H. H. Livermore, NRC Resident Inspector 1 l l ,~. ..}}