ML20070N702
| ML20070N702 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 01/14/1983 |
| From: | Edelman M CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| PY-CEI-NRC-0003, PY-CEI-NRC-3, NUDOCS 8301250585 | |
| Download: ML20070N702 (4) | |
Text
O T H E C L E V E L A N D E L E C T R I C I L i. U id ! H AT I N e CG WP ANY P.o. Box 5000 - CLEVELAND, oHlo 44101 - TELEPHONE (216) 622-9800 - ILLUMINATING BLDG. - 55 PUBLIC SQUARE Serving The Best Location in the Nation MURRAY R. EDELMAN VICE PRESIDENT NUCLIAR January 14, 1983 PY-CE!/NRC-0003 L Mr. B. J. Youngblood, Chief Licensing Branch No. I Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Equipment Qualification for Hydrodynamic Loads
Dear Mr. Youngblood:
This letter and its attachments are provided in response tc the letter dated August 12, 1982 from A. Schwencer to D. R. Davidson regarding qualification of safety related equipment for hydrodynamic loads, (Perry Units 1 and 2).
Draf t FSAR change pages are provided to address the staff concerns expressed in Enclosure I to that letter. These will be incorporated in a future FSAR Amendment.
If you have any questions, please let me know.
Very truly yours, Murray R. Edelman Vice President Nuclear Group MRE:kh O/
D cc:
Jay Silberg, Esq.
John Stefano Max Gildner Dave Reiff Ken Matheny Attachments 8301250585 830114 PDR ADOCK 05000440 0
Attachment to:
PY-CEI/NRC-.0003 L 3.10.1.3 Input Motion The input motion for the qualification of equipment and supports is defined by either response spectra or static g-levels. The floor response spectra are generated from the building dynamic analysis. They are grouped by buildings and by elevations. The required response spectra (RRS) for the seismic and i
hydrodynamic loads were provided to the equipment vendors.
When one type of equipment is located at several elevations and/or in several buildings, the governing rasponse spectra are specified.
3.10.1.4 Qualification for Hydrodynamic Loads 3.10.1.4.1 Uncertainty in Hydrodynamic Loads Uncertainties in hydrodynamic load amplitude and frequency that arise from the use of an axisymmetric model, variations in the properties of structure and foundation, and the inability of analytical model-forcing function combinations to accurately predict high frequency response are accounted for as follows:
Non-axisymmetric forcing functions are employed.
a.
b.
Envelopes of radial and tangential response are used in combination with azimuthal envelopes.
1 The conservative CE load definition has generally been " tuned" to provide c.
maximum response, d.
Events are enveloped.
Equipment RRS have been broadened in accordance with standard procedures e.
f.
The general problem of high frequency "exceedances" is being addressed in a manner similar to that described in " Generic Criteria for High-Frequency Cut-off for BWR Equipment", NEDE-25250.
i 3.10-2
O g.
Where equipment is qualified by test, frequencies up to at least 100 Hz are considered.
3.10.1.4.2 Input Load for Equipment Various hydrodynamic loads are combined with SSE or OBE for equipment qualification as follows:
OBBA = OBE + SRV (2% damping) a.
b.
del = SSE + Pool Swell (3% damping)
^
c.
LC3 = SSE + SRV + CO (3% damping) d.
LC4 = SSE + SRV + Chug (3% damping) e.
DE2 = Higher of LC3 or LC4 f.
SSBA = Higher of del or DE2 The combinations are by SRSS, the basis for which is contained in " Study to Demonstrate the Generic Applicability of SRSS Combination of Dynamic Responses for Mark III Nuclear Steam Supply System a'nd Balance-of-Plant Piping and Equipment Components", SMA 12109.01-R001.
Individual spectra were developed by time history analysis for the following dynamic loads:
a.
OBE b.
SSE c.
SRVA (1, 8, and 19 valves) d.
Pool Swell (including main vent cleaning) e.
Chug j
f.
Condensation Oscillation The hydrodynamic loads are discussedin detail in Appendix 3B, Whenever envelopes are employed, they are based on the highest acceleration at any given frequency.
3.10-2a
O 3.10.1.4.3 Effect of Number of Cycles Where qualification is by. analysis, all stress cycles on critical sections plant normal, abnormal, and accident conditions including the effect of thermal cycles and hydrodynamic and earthquake load cycles are considered. Where qualification i
is by testing, shake tables using random motion compatible with the required response spectra in accordance with IEEE 344-1975 are preferred.
J e
2 3.10-2b
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