ML19211D276

Submits Supplemental Info Re Confirmatory Piping Analysis. Informs That Single Vertical Response Spectra Is Applicable at All Reactor Pressure Vessel Node Points

ML19211D276
Person / Time
Site:	LaSalle
Issue date:	01/11/1980
From:	Delgeorge L COMMONWEALTH EDISON CO.
To:	Parr O Office of Nuclear Reactor Regulation
References
NUDOCS 8001170397
Download: ML19211D276 (5)

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Commonwealth Edison One First National Plaza. Chicago. Ilknois Address Reply to: Post Office Box 767 Chicago, Ilknois 60690 January 11, 1980 Mr. Olan D. Parr, Chief Light Water Reactors - Branch 3 Division of Project Management U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Supplemental Information Concerning Confirmatory Piping Analysis for LaSalle County Station Units 1 and 2 NRC Docket Nos. 50-373 and 50-374 Re fe rence : L. O. Del George letter to O. D. Parr dated Decem~er o 5, 1979

Dear Mr. Parr:

The enclosed information completes our submittal of the information delineated in Reference (a). Specifically, the following response spectra are provided for the confirmatory analysis of Subsystem RH-04. .

1. Horizontal, East-Wtst, OBE Response Spectra for Mass Point 178, dated 11-17-77 (0.5% damping)

2. Horizontal, North-South OBE Response Spectra for Mass Point 178, dated 11-17-77 (0. 5% damping)

3. Vertical acceleration at Node 8 due to OBE, dated 01-01-77 (utilize 0.5% damping values)

Please note that a single vertical response spectra is applicable at all RPV node points; the re fo r e , the fact that the node points for items 1 and 2 do not correlate with item 3 is not significant. Also, different RPV models are used to obtain the vertical and horizontal responses.

It should also be pointed out that the vertical response spectra (item 3) has not been widened. The spectra peaks should be widened by 20% before use. The horizontal spectra (items 1 and 2) have already been widened; and, therefore, can be used directly. Also note that the 0.5% damping spectra should be utilized for item 3.

1762 268 eco1170397h foOgfij

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Commonwealth Edison NRC Docket Nos. 50-373 50-374 Mr. Olan D. Parr, Chief January 11, 1980 The following data was given to NRC representatives (Mr. R. Stevens, et al.) at the December 19, 1979 meeting at the LaSalle County site: ,

1. Magnetic computer tape, serial number 2172, containing GBE displacement time histories

2. Magnetic compucer tape, serial number 893, contain-ing SRV-Quencher Symme tric displacement time histories

3. One copy of the printout of the information contained on the computer tapes listed in items 1 and 2

4. A microfiche record of the printout listed in item 3 The tapes have the following format:

1. 9 track, 1600 BPI, unlabeled

2. IBM-EBCDIC format

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3. 80 character record length

4. 1600 character block size Tape number 2172 has two files, as follows. One file for X and Z time histories at nodes 39, 40, 50, 51 and 53, and the other file for Y time histories for nodes 17 and 61.

Tape number 893 has one file containing X, Y and Z time histories for 17 load cases at nodes 299, 303, 307, 317, 320 and 324. The card image form is 80 columns per card with each time history comprising 362 cards. The first card, an identifier, specifies the node number, direction (X, Y and Z) and a load number. The next 361 cards contain four sets per card of time-displacement pairs. The 361 cards have 8E10.5 format.

With regard to the magnetic tapes discussed above, you are requested to return them upon completion of your analysis or extraction of the necessary information whichever occurs first.

If there are any further questions in this regard, please direct them to this office. -

Very truly yours, F762 269 f(2if

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L. O. Del George Enclc.sure Nuclear Licensing Administrator

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