ML18004A572
| ML18004A572 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 09/29/1986 |
| From: | Zimmerman S CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NLS-86-357, NUDOCS 8610080393 | |
| Download: ML18004A572 (6) | |
Text
RE('UL RY INFORMATION DISTR IBUTI SYSTEM (R IDS>
~ACCESSION NBR: 8610080393 DOC. DATE: 86/09/29 NOTARIZED:
NO DOCKET ¹ FACIL:50-400 Sheav on Hav v is Nuclear Power Planti Unit ii Carolina 05000400 AUTH. NANE AUTHOR AFFILIATION ZINNERNAN>S. R.
Cav olina Powev 5 Light Co.
REC IP. NANE RECIPIENT AFFILIATION DENTON> H, R.
Office of Nuclear Reactor Regulationi Divectov (post 851125
SUBJECT:
Discusses cv iteria fov choice of 5-inch conduit containing thv ee 750-kcmili 15 kV power cables as wov st'ase.
Cables have gv'eatest heat capacitance 5
gv eatest potential to heat cables in adjacent tray to conduit.
DISTRIBUTION CODE:
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TITLE: Licensing Submittal:
PSAR/FSAR Amdts Zc Related Cov respondence NOTES: Application fov pev'mit renewal filed.
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@ME, Carolina Power 8 Light Company SEP 29 gag SERIAL: NLS-86-357 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO.
1 - DOCKET NO.50-000 ELECTRICALSEPARATION ANALYSIS
REFERENCE:
Letter dated 3une 19, 1985 (NLS-85-200) from S. R. Zimmerman (CPRL) to H. R. Denton (NRC)
Dear Mr. Denton:
Carolina Power R Light Company provides supplemental information to the referenced letter.
The SINDA Code was developed and verified by TRW Systems Group for NASA (Contract 9-10035).
The code documentations are provided in:
1.
"SINDA User's Manual", by 3. P. Smith, TRW Report 10690-H001-R0-00, April 1971.
2.
"SINDA Engineering Program Manual", by T. Ishimoto and L. C. Frink, 3une 1971.
3.
"SINDA/SINFLOWComputer Routine", Report No. 2-53002/OR-3167, (LTV to TRW), February 1975.
This code utilizes generalized heat transfer equations.
It is applicable for the steady state and transient problems with internal heat generation, heat conduction, convection, radiation or combination of these.
The support and leasing of the code has been administered by COSMIC Software Center of NASA. The version used by the current analysis was installed on the Cray-1 computer of UIS (SIS).
The installation and verification was performed by PROSE, Inc., of California. It has been used in similar electrical analyses for another nuclear utility.
The choice of utilizing a 5-inch conduit containing three 750 kcmil, 15 kV power cables as the worst case was questioned by the NRC staff. This is case la of Table 3 (attached).
Case la was chosen because these cables have the greatest heat capacitance, therefore, the greatest potential to heat the cables in the tray adjacent to the conduit.
Because these cables have the highest heat capacitance, it takes them the longest time 8610080393 860929 PDR ADOCK 05000400
/
PDR 411 Fayettevilte Street o P. O. Box 1551 o Raleigh, N, C. 27602
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g \\'r. Harold R. Denton NLS-86-357 / Page 2
to melt. As previously stated, the 6.9 kV switchgear at the Shearon Harris Nuclear Power Plant have multiple levels of protection to interrupt faults.
Each feeder has overcurrent protection, and each bus has undervoltage as well as overcurrent and differential protection.
If you have any questions, please contact me at your convenience.
Yours very truly, GAS/pgp (5015GAS)
Attachment S.. Zim erman Man er Nuclear icensing Section cc:
Mr. B. C. Buckley (NRC)
Mr. G. F. Maxwell (NRC-SHNPP)
Dr. 3. Nelson Grace (NRC-RII)
TASIZ 3 CAROLINA tSfER & LICHT OOKFAlIY
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