ML20236U742
| ML20236U742 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/28/1998 |
| From: | Tam P NRC (Affiliation Not Assigned) |
| To: | NRC |
| References | |
| GL-96-06, GL-96-6, TAC-M96794, TAC-M96795, NUDOCS 9807300409 | |
| Download: ML20236U742 (2) | |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - - _ - _ _ _ - _ _ - _ - _ - _ - _ _ _ _
d f
l J
UNITED STATES p,
j NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 2066tHm01
\\...../
July 28,1998 MEMORANDUM FOR:
Docket File FROM:
Peter S. Tam, Senior Project Manager Project Directorate 11-2 Division of Reactor Projects -l/II M
Office of Nuclear Reactor Regulation
SUBJECT:
CATAWBA NUCLEAR STATION - FACSIMILE COMMUNICATING QUESTIONS ON THE LICENSEE'S
~ RESPONSE TO GENERIC LETTER 96-06 (TAC M96794 AND M96795)
The attached questions were transmitted by fax today to Martha Purser of Duke Energy Corporation (DEC) to prepare her and others for an upcoming conference call. This memorandum and the attachment do not convey a formal request for information or represent an l
NRC staff position.
i
/
Docket Numbers 50-413 and 50-414 Distribution PUBLIC H. Berkow
$$ h,gi bunm Ma }f o_
y-r-
(?! N3 i
.;o 9807300409 980728
~
PDR ADOCK 05000413 P
PM 3
./
t l
CATAWBA NUCLEAR STATION, UNITS 1 AND 2 RESPONSE TO GENERIC LETTER 96-06 In the January 28,1997, submittal, Duke indicated that a total of 3 pipe segments in each unit were susceptible to thermally-induced pressurization which are isolated by soft seat plug valves. Duke stated that testing has been performed which demonstrated that these valves would leak enough fluid to prevent overpressurizing the piping above the maximum Code-allowable pressure, in order to complete its review of Duke's response, the staff needs the following information for these penetrations:
Describe the applicable design criteria for the piping and valves. Include the required load combinations; Provide a drawing of the valve. Provide the pressure at which the valve was determined to lift off its seat or leak and describe the method used to estimate this pressure.
Discuss any sources of uncertainty associated with the estimated lift off or leskage pressure; Provide the maximum-calculated ess in the piping run based on the estimated lift off or leakage pressure.
In the submittal, Duke also indicated that the Equipment Decontamination (WE) piping has a design pressure of 8015 psia which would withstand the pressurization due to heatup. In order to complete its review of Duke, the staff needs the following information for these penetrations:
Provide the applicable design criteria for the piping and the valves. Include the required load combinations; Provide a drawing of the piping run between the isolation valves. Include the lengths and thicknesses of the piping segments and the type and thickness of the insulation; Provide the maximum-calculated temperature and pressure for the pipe run. Describe, in detail, the method used to calculate these pressure and temperature values. This should include a discussion of the heat transfer model used in the analysis and the basis for the heat transfer coefficients used in the analysis.
l
. - _ _ _.