ML19270F354

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Forwards Round 4 Response to NRC Request for Addl Info Re Spent Fuel Pool Storage Capacity Expansion.Provides Ductility Ratios,Numerical Values of Hydrodynamic Mass Used in Analysis of Racks, & Info Re Spent Fuel Liner
ML19270F354
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 01/26/1979
From: Naughton W
COMMONWEALTH EDISON CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
NUDOCS 7902060297
Download: ML19270F354 (33)
v • d • e


Text

THIS DOCUMENT C0flTAINS

/

Commonwealth Edison POOR QUAUTY PAGES one First National Plata. Chicago. Ilknots Address Reply :o: Post Office Box 767 Chicago. lilinois 60690 January 26, 1979 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C.

20555

Subject:

Zion Station Units 1 and 2 Additional Information on Proposed Expansion of Spent Fuel Storage Capacity NRC Docket Nos. 50-295 and 50-304

Dear Mr. Denton:

Recently, the NRC Staff requested Commonwealth Edison Company to provide additional information in support of its request to expand the storage capacity of the Zion Unit 1 and 2 spent fuel pool.

Attachment I to this letter contains Common-wealth Edison's responses to the NRC Staff's request.

Please address any additional questions that you might have to this office.

One (1) signed original and thirty-nine (39) copies are provided for your use.

Very truly yours, auLh h.

f William F. Naughton Nuclear Licensing Administrator Pressurized Water Reactors attachment 780206 @ 97

NRC Docket Nos.

50-295 and 50-304 ATTACllMENT I Round 4 Response to NRC Request for Additional Infomation on Zion Units 1 and 2 Spent Fuel Pool Storage Capacity Expansion

I NRC Docket Nos.

50-295 and 50-304 QUESTION NU).GER 1:

What is the maximum load that can be transported over the fuel pool? Was the potential damage to the fuel racks from the maximum energy at impact from any heavy load over the pool considered? Provide the ductility ratios assumed.

RESPONSE

The crane in the fuel building is not utilized to transport objects over fuel storage areas.

It is used to install and remove items, such as storage racks and fuel inspection stands, in the pool.

However, these operations are conducted under the supervision of licensed fuel handlers and performed in such a manner as to prevent moving objects over s' re-fuel.

Fuel handling operat.... are conducted from the pool bridge utilizing a hoist crane. Of the items involved in fuel movements, the fuel is the maximum load which can impact the racks. Interlocks on the hoist limit the distance between the transported fuel and rack to 24".

Drop of only one fuel bundle was considered in the analysis of racks. A 24-inch drop was postulated and the consequences were evaluated by a simple, but conservative elasto-plastic analysis method.

In this method, the length of the rack that might be crushed to absorb the energy of the dropped bundle was computed by equating this energy to the vork done in local crushing of the area in the vicinity of the drop. Rack configuration is such that the cell walls immediately under the impacting fuel bundle yielded in compression before buckling. Also, since the structural integrity of the rack did not depend on the ductility of this localized crushed region, the consideration of ductility ration was not necessary.

Q1.1

NRC Docket Nos.

50-295 and 50-304 QUESTION NUMBER 2:

Provide the numerical values of hydrodynanic mass used in the analysis of the racks. Also prnvide tiie five modal frequencies of each different rack and the iesponse spectral curve used in the seismic arialysis.

RESPONSE

Numerical values of hydrodynamic masses used in the analyses are shown in Table 2-1.

Modal f requencies an' prnvided in Table 2-2.

Response spec trui:i curve-.. s ed in the seismic analyses are shown in figures 7.1 and P./.

Q2.1

NRC Docket Nos.

50-295 and 50-304 TABLE 2-1 IlYOR0 DYNAMIC MASSLS USLD IN ?EISMIC ANALYSES 2

RACK HYDRODYNAMIC MASSES (LI.-SEC / IN) FOR SIZES MOTION PARALLEL TO

~

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~ ~ ~ ~

.._5IRIR H_ _I.ii.ET~Tfi.R!. ~ ~

5x7 89./6?

'>0. / /3 5 x 10 177.396 S4.549 7 x 11 219.163 103.848 10 x 11 230.306

.96.396 NOTE: The dynamic behavior of 7 x 10 and 10 x 10 size racks was judged to be close to and less critical trun that of 7 < 11 and 10 x 11 size racks respectively (Noti-all the r wk si/i", have similar structural conf igurations).

02.2

NRC Docket Nos.

50-295 and 50-304 TABLE 2-2 FREQUENCY RESPONSE OF VARIOUS RAC< SIZES Frequency (Hertz) for Rack Size 5x7 5 x 10 7 > 11 10 x 11 Mode No.

1 7.19 6.6 11.88 10.46 2

14.43 17.08 12 17 13.84 3

28.47 25.69 36.60 32.17 4

48.91 47.80 40.53 42.49 5

53.60 52.52 62.44 55.23 6

87.17 77.65 73.77 77.46 NOTE: The dynaniit behavior of ' x 10 and to x 10 s i / c r.u k. wa*. j udged to be close to and less critical than that of 7x 11 and 10 x 11 size racks respectively (Note: all the rack sizes have siniilar structural configurations).

Q2.3

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NRC Docket Nos. 50-295 and 50-304 QUESTIGi NUMBER 3: Statement needed on integrity of spent fuel liner with regard to tears, etc.

RESPONSE

The Zion storage racks will be set on the existing embedment plates in the spent fuel pool. These plates are attached to the building structural beams and protrude through the floor and liner of the spent fuel pool. In the south area of the pool, the last row of racks will only have one side of the base plates placed on the embedments. The other side of the south rack row will have a continuous beam support structure placed directly on the pool liner, but in the area where the liner is over the floor support beam. Placement of the racks over the support beams, and the use of the continuous support in the one case of liner contact, will reduce any possibility of tearing or damaging the pool liner and integrity. 03.1

NRC Docket Ncis. 50-295-and 5-304 QUESTION NUMBER 4: Quality control statement (ASME, ANSI, etc.) on procedures used for fabrication of racks. References are sufficient

RESPONSE

The following are the referenced codes and standards from the Zion Fuel Rack Procurement Speci fica tion: Codes and _ Standards 1 The latest issue, as of the date of thic tontrac t, of the applicable parts of the following sections of the ASMi iloiler and Pressure Vessel Code shall apply to the work done under this Specification: Section II - Material Specifica tion, Part C, Welding Rods, El ec troder., ani! f il l Ma t.eria ls Section 111 - Nuclear Power Plant Coteonents, Subsection NF 3300. Section V - Nondestructive Examina tion, Art icle 6, Liquid Penetrant Lxamination Section IX - Welding and Brazing Qualifications 2 Code Stamping Not Applicable Continued..... 04.1

NRC Docket Nos. 50-295 and 50-3]4 3 The latest issue, as of the date of this contract, of the appli-cable parts of the following American National Standards Institute (ANSI) Standard shall apply to the work done under this Specification. N45.2.2, " Packaging, Shipping, Receiving Storage, and Handling of Items for Nuclear Power Plants." 4 All reference to Americ an Society for Testing Materials (ASTM) Standard Specifications, other similar standard publications, and applicable supplements are to the latest issue of each as of the date of this contract. Q4.2}}

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