ML20094S060
| ML20094S060 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 11/29/1995 |
| From: | Terry C, Walker R TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TXX-95299, NUDOCS 9512060012 | |
| Download: ML20094S060 (4) | |
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Log i TXX 95299 File f 916 (5.6) 53:
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10010 lilELECTRIC c L==e Twer November 29, 1995
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Grosqp Vkv PresMrst.Nadeer U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 t
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SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS, 50 445 AND 50 446 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ON LICENSE AMENDMENT REQUEST 94-022 SPENT FUEL STORAGE CAPACITY INCREASE REF:
the NRC, dated December 30, 1994 Gentlemen:
TV Electric transmitted License Amendment Request 94 022 (Reference 1) which revises the specification for fuel storage to authorize usage of the i
high density fuel storage racks, to increase the spent fuel storage capacity, and to adopt the wording, content, and format of the Improved Standard Technical Specifications. During recent conversations with the NRC several requests for additional information were discussed. Attachment 1 provides the requests for additional information and TU Electric's responses.
The information provided in Attachment 1 does not affect the proposed Technical Specification changes, the safety analysis of those changes, or the determination that the proposed changes do not involve a significant hazard consideration (provided by Attachments 2 and 3 of Reference 1).
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i TXX 95299-Page 2 of 2 4
Should you have any questions, please contact Carl B. Corbin at (214) 812 8859 or David A. Bersi at (817) 897 8134.
Sincerely, j
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C. L. Terry By:
9 Roger D. Walker Regulatory Affairs Manager CBC/cbc
Attachment:
Response to Request for Additional.Information Regarding Spent Fuel Pool Storage Increase i
c-Mr. L. J. Callan, Region IV Mr. T. J. Polich, NRR Mr. W. D. Johnson, Region IV Resident Inspector, CPSES Mr. D. K. Lacker Bureau of Radiation Control Texas Department of Public Health 1100 West 49th Street Austin, Texas 78704 i
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i Attachemnt 1 to TXX 95299 Page 1 of 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING SPENT FUEL POOL STORAGE INCREASE NRC RAI # 1:
What are the total number of computer runs for single and multi-rack analyses, respectively?
TU Electric Resoonse to RAI # 1 :
1 The single rack and multi rack analyses were each analyzed for four different cases which comprise the range of seismic loading and friction coefficient. The four cases are:
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OBE with 0.2 friction coefficient 2.
OBE with 0.8 friction coefficient 3.
SSE with 0.2 friction coefficient 4.
SSE with 0.8 friction coefficient Thus, a total of eight different cases were evaluated. Of course, each individual case requires several separate computer runs, and several computer runs were used to generate stiffness and mass properties for the finite element models.
i NRC RAI # 2:
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What loading conditions were considered for each analysis (i.e. full.
half full, almost empty)?
TU Electric Resoonse to RAI # 2 :
The eight cases identified in Response # 1 considered fully loaded racks, both in the single rack and the multi-rack analyses. The fully loaded configuration has been determined to produce the limiting conditions for the racks in terms of displacements (both sliding and rocking), loads, and stresses. Calculations have been performed for partially loaded (i.e., one row full, two rows full.
.... all rows full) racks to demonstrate acceptable margin against overturn.
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~ Attachment 1 to TXX 95299 Page 2 of 2-NRC RAI # 3:
f What are the_ dimensions of racks considered in each analysis (e.g. 12 i
x 14 x what height)?
S TU Electric Resnonse to RAI # 3 :
t The CPSES spent _ fuel' pool contains two different rack sizes: 11 x 14 3-
.(99.88 inches x 126.88 inches) and 12 x 14 (108.88 inches x 126.88 inches).- All-racks have a height of 168.25 inches. The single rack' analysis modeled the 11 x 14 size rack since it has the largest i-height to width _ aspect ratio and thus has more propensity to rock and lift a support pad off the pool floor. The multi-rack analysis modeled all the racks within the pool and therefore considered both
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11 x 14 and 12 x 14 rack sizes.
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NRC RAI # 4:
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What Coefficients of Friction were considered in each ' analysis?
i TU Electric Resnonse to RAI # 4 :
As mentioned in Response # 1, two bounding friction coefficients were considered in each analysis: 0.2 and 0.8.
These extreme values j
capture the maxima'of the racks' seismic response in terms of sliding l
e displacements, rocking displacements, and internal loads and stresses.
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NRC RAI # 5:
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What dimensions of the spent fuel pool (length, width, and height) were used in the ANSYS analysis?
' TU Electric Resnonse to RAI # 5 :
I The inside dimensions of the spent fuel pool used in the ANSYS
' analysis were 40' 3"_(length). 30' 0" (width), and 41' 6" (height).
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