ML20050C705
| ML20050C705 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 04/08/1982 |
| From: | Jackie Cook CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR NUDOCS 8204090274 | |
| Download: ML20050C705 (4) | |
Text
0 Consumers power James W Cook 00m9any5 Vice President - Projects, Engineering and Construction Generet offices: 1945 West Parnell Road, Jackson, MI 49201 * (517) 788-0453 April 8, 1982 to to 6
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Ilarold R Denton, Director p
Office of Nuclear Reactor Regulation 2
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Division of Licensing 3-gk I
US Nuclear Regulatory Commission p'd Washington, DC 20555 na N
D MIDLAND PROJECT g
MIDLAND DOCKET NOS 50-329, 50-330 RESPONSE TO OPEN ITEMS OF PRELIMINARY DRAFT SER 9.1.4 FILE:
0505.805 SERIAL:
16599 Reference (a): J W Cook Letter to II R Denton, Serial 14928, Dated 12/21/81 Enclos* ire (1): Response to Open Item 1 of Preliminary Draf t SER 9.1.4.
We have reviewed the preliminary draft section of the NRC Staff's Safety Evaluation Report 9.1.4, " Fuel llandling System." Open Item 2 (heavy loads) is addressed by our Part I Response to the Control of Ileavy Loads at Nuclear Power Plants (NUREG-0612) and submitted to the Staff by Reference (a).
Enclosed is our response to Open Item 1 (light loads). This response will be included in the next. FSAR revision.
With the responses provided by Reference (a) and this letter, we believe the Staff can classify the open items of preliminary draft SER 9.1.4 as confirmatory.
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CC RJCook, Midland Resident Inspector Rifernan, US NRC j/
OParr, US NRC DBMiller, Midland Construccion (3)
RWiluston, Washington 8204090274 820408 PDR ADOCK 05000329 E
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MIDLAND 1&2-FSAR 9.1.4.3.10 Analysis of Cask Drop The Midland spent fuel cask handling concept incorporates a single-failureproof overhead crane handling system.
The special safety features incorporated into the design of the main hoisting system of the auxiliary building crane precludes a cask drop accident by preventing a load drop in the event of a single failure in the hoisting or breaking systems.
Detailed information regarding the design of Midland's single-failure proof main hoist may be found in generic topical reports EDR-1(P )-A and EDR-1(NP )-A for nuclear safety-related X-SAM 33 cranes submitted by Ederer Incorporated.N Midland plant-specific crane data, as summarized in Appendix B of Ederer's l18 Generac Topical Report EDR-1(P)-A, may be found in Table 9.1-9.
Compliance with plant-specific regulatory positions, as 29 summarized in Appendix C of Ederer's Generic Topical Report EDR-1(P)-A, may be found in Table 9.1-10.
l 18 It should be noted that the main hoist of Midland's auxiliary building crane is identical to the X-SAM system described in the above referenced generic topical report with the exception that the Midland crane has a single load path lower hook (i.e.,
trunion and attaching points).
Because of lifting envelope limitations, the Midland design was not able to accommodate dual 16 load path attaching points.
In view of this limitation, a factor of safety of 10:1 will be applied to the trunion and attaching point components that have a single load path.
As an added measure of safety, the auxiliary building crane incorporates mechanical stops to preclude heavy loads from passing over the spent fuel pool.
These mechanical stops are designed to stop the crane while it is traveling at design speed (102 fpm) and while it is fully loaded (125 tons payload).
Furthermore, the crane is equipped with end-truck bumpers designed to the requirements of Lection 4.12 of CMAA Specification 70.
During cask handling 18 operations (other than above the railroad bay), the trolley will be prevented from moving on the bridge through electrical interlocks.
The spent fuel shipping cask utilizes a double yoke lifting rig (see Figure 9.1-10), thus preventing an accident in the event of a single failure occurring in the double yoke.
INSERT A -->
9.1.4.4 Inspection and Testing Requirements 9.1.4.4.1 Shop Testing and Inspection After manufacture, shop checkout inspections and operation tests are performed on the following components of the fuel handling system:
a.
Main fuel handling bridge b.
Spent fuel handling bridge 9.1-39 Revision 33 4/81
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INSERT A 9.1.4.3.11 Light Loads Handled Over Spent Fuel A light load is defined as a load weighing less than the combined weight of a fuel assembly and its handling device. Administrative controls and procedures will be provided for the handling of light loads which, if dropped, may impact spent fuel with kinetic energy greater than the kinetic energy of a fuel assembly and its handling device. These procedures and controls will ensure safe handling of these loads over spent fuel.
0-CONSUMERS POWER COMPANY Midland Units 1 and 2 Docket No 50-329, 50-330 Letter Serial 16599 Dated April 8,1982 At the request. of the Commission and pursuant to the Atomic Energy Act of 1954, and the Energy Reorganization Act of 1974, as amended and the 1
Commission's Rules and Regulations thereunder, Consumers Power Company submits response to the Open Items of draf t SER 9.1.4, Fuel Handling System.
CONSUMERS POWER COMPANY By J W Cook, Vice President Pr jects, Engineering and Construction l
Sworn and subscribed before me this 5
day of April 1983 B
Notary Public
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Jackson County, Michigan My Commission Expires Sentember 8. 1984 miO482-0843b131
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