ML17329A353

Forwards Request for Addl Info Re Spent Fuel Pool Reracking, Per Review of 910726 Submittal.Response Requested within 45 Days

ML17329A353
Person / Time
Site:	Cook
Issue date:	01/13/1992
From:	Colburn T Office of Nuclear Reactor Regulation
To:	Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
References
TAC-M80615, TAC-M80616, NUDOCS 9201170206
Download: ML17329A353 (6)

Text

January 13, 1992 Docket Nos.

50-315 and 50-316 Mr. E.

E. Fitzpatrick, Vice President Indiana Michigan Power Company c/o American Electric Power Service Corporation 1 Riverside Plaza

Columbus, Ohio 43216 DISTR IBUTION:

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PDR PDI II-1 r/f BBoger JZwolinski LBMarsh PShuttleworth TColburn OGC EJordan ACRS(10)

PDIII-1 Gray EGreenman, RIII CMcCracken Nh'agner ADummer GHubbard

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION, D. C.

COOK UNITS 1 AND 2 SPENT FUEL POOL RERACKING (TAC NOS.

M80615 AND M80616)

In conducting our review of your July 26, 1991 submittal relating to the above subject for your facilities, we have identified the need for additional information as described in Enclosure 1.

In order for us to maintain our review schedule, we request that you respond to our request for additional information within 45 days receipt of this letter.

This request affects fewer than ten respondents, therefore, OMB clearance is not required under P.

L.96-511. If you have any questions, please contact me at (301) 504-1341.

Sincerely,

Enclosure:

As stated cc:

See next page Original signed by Timothy G. Colburn, Senior Project Manager Project Directorate III-1 Division of Reactor Projects III/IY/V Office of Nuclear Reactor Regulation Iltg P)g gp~>@pa gapy g

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Mr. E.

E. Fitzpatrick Indiana Michigan Power Company Donald C.

Cook Nuclear Plant CC:

Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Attorney General Department of Attorney General 525 West Ottawa Street Lansing, Michigan 48913 Township Supervisor Lake Township Hall Post Office Box 818 Bridgman, Michigan 49106 r

Al Blind, Plant Manager Donald C.

Cook Nuclear Plant Fost Office Box 458 Bridgman, Michigan 49106 U.S. Nuclear Regulatory Comnission Resident Inspectors Office 7700 Red Arrow Highway Stevensville, Michigan 49127 Gerald Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.W.

Washington, DC 20037 Mayor, City of Bridgman Post Office Bcx 366 Bridgman, Michigan 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, Michigan 48909 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health Department of Public Health 3423 N. Logan Street Post Office Box 30195 Lansing, Michigan 48909 Mr. S. Brewer American Electric Power Service Corporation I Riverside Plaza

Columbus, Ohio 43216

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Encl osure REQUEST FOR ADDITIONAL INFORMATION DONALD C.

COOK NUCLEAR PLANT RERACKING THE SPENT FUEL POOL DOCKET NOS.

50"315, 50"316 1.

Heavy loads handling:

The following questions refer to Holtec Report HI-90488, Section 2.4, "Existing Rack Modules and Proposed Reracking Operation."

a ~

A "single failure-proof hook" was mentioned in the report.

For heavy loads handling, a single failure proof handling system or an analysis of a load drop is required.

Provide documentation of the single failure proof handling system or the analysis of the worst case load drop.

Show how the hook complies with the single failure-proof criteria of NUREG-0612.

b.

The report states:

"A module change-out scheme will be developed which ensures that all modules being handled are empty when the module is moving at a height which is more than 12" above the pool floor."

The accident analysis section of the licensing report does not include an analysis of a rack containing fuel being dropped or impacting another rack or the pool wall.

(1) If DC Cook does not have a single failure proof handling system, either provide an analysis of rack movement and rack drop with fuel assemblies in the rack or clarify the rack movement procedure to preclude movement of racks with fuel in them.

(2) If DC Cook has an approved single failure proof handling

system, provide an explanation of the rack movement procedure for handling loaded racks, including limitations for the movement of these racks.

C.

Show that a single attachment break in the. single failure proof handling system will not result in the heavy load (such aS a fuel rack loaded with fuel) winging or rotating, so as to impact the pool or fuel racks.

Otherwise, provide an analysis of the results of such swing(s) or rotation(s).

2.

Decay Heat Loads:

Standard Review Plan 9. 1.3 provides guidelines for cooling and sources of make-up water to the SFP.

(1) The SFP cooling system should be designed to seismic Category I requirements or (2) the fuel pool make-up water source, its source, the fuel pool building and its ventilation and filtration system should be designed to seismic Category I requirements.

The FSAR for DC Cook does not specify the SFP cooling system as seismic Category I or specify a make-up water

system and its source as seismic Category I.

Show which alternative, 1 or 2, above, is applicable, and provide the details of compliance with that guideline.

Table 5.5.1 of the Holtec report shows that for a normal refueling load including a single failure in the cooling system, the temperature of the SFP will rise to 159.54 F.

Justify the deviation from the design basis of below 140 F for a normal refueling and below 130'F for a full core offload with both SFP cooling system trains in operation.

At the maximum pool temperature, what is the concrete temperature?

Show that the concrete integrity is maintained for both normal and abnormal conditions.