ML18004A548
| ML18004A548 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 09/23/1986 |
| From: | Zimmerman S CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NLS-86-368, NUDOCS 8610060053 | |
| Download: ML18004A548 (4) | |
Text
f REQULAT' INFORNATION DISTR IBUTIOl'YSTEtl (R IDS)
~ ~
ACCESSION NBR: 86 j0060053 DOC. DATE: 86/09/23 NOTARIZED:
NO DOCKET FACIL: 50-400 Sheav on Hav ris Nucleav Power Plant>
Unit ji Carolina 05000400 AUTH. NANE AUTHOR AFFILIATION ZINNERNAN>S. R.
Cavolina Potoer hc Light Co.
REC IP. NANE RECIPIENT AFFILIATION DENTON, H. R.
OFfice of Nuclear Reactov Regulationi Directov (post 85ii25
SUBJECT:
Fov wards addi info to suppl util 860919 ltv re high energy line breaks outside containment.
D1STRIBUTION CODE:
BOOiD COPIES RECEIVED: LTR ENCL SI ZE:
TITLE: Licensing Submittal:
PSAR/FSAR *mdts Zc Related Correspondence NOTES: Application for pevmit v eneual Wiled.
05000400 RECIPIENT ID CODE/NAI'lE PNR-A EB PNR-A FOB PNR-A PD2 PD P(N-A PSB INTERNAL: ADN/LFNB XE FILE IE/DGAVT/GAB 2i NRR PWR-B ADTS NRR/DHFT/llTB RQN2 EXTERNAL: BNL(AI')DTS ONLY)
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PNR-A RSB ELD/HDSi IE/DEPER/EPB 36 NRR BWR ADTS NR ROE> J'1. L EQ FIL NIB 04 DMB/DSS (ANDTS)
NRC PDR 02 PNL QRUELiR COPIES LTTR ENCL 2
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@ME Carolina Power 8 Light Company SEP 23 MSG SERIAL: NLS-86-368 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 HIGH-ENERGY LINE BREAKS OUTSIDE CONTAINMENT
REFERENCE:
Letter dated September 19, 1986 (NLS-86-310) from S. R. Zimmerman (CPRL) to H. R. Denton (NRC)
Dear Mr. Denton:
Carolina Power Bc Light Company submits the attached information to supplement the information provided in the referenced letter.
If you have any questions, please contact me at your convenience.
Yours very truly, GAS/pgp (5006GAS)
Attachment cc:
Mr. B. C. Buckley (NRC)
Mr. G. F. Maxwell (NRC-SHNPP)
Dr. 3. Nelson Grace (NRC-RII)
S.. Zi erman ager Nuclear Licensing Section 8610060053 860923 PDR ADOCK 05000400!
A P DRi~'
411 Fayettevilte Street o P. O. Box 1551
~ Raleigh, N. C. 27602
ATTACHMENT TO NLS-86-368 From the cases presented in Table 3 of the referenced letter, where auxiliary feedwater isolation does not occur, it is clear that lower component temperatures are reached with smaller break sizes.
Realistically, the differences between isolation and non-isolation become less significant with decreasing break size because (1) both cases are identical for a longer period before the tube bundle uncovery occurs and (2) the temperature rise following tube bundle uncovery willbe similar in magnitude and duration differing only in the time at which the temperature rise takes place.
This difference is minimized by the fact that for smaller breaks isolation willoccur after the component surface temperature reaches equilibrium with the saturated steam conditions.
This means that as you decrease in break size, both cases with and without auxiliary feedwater isolation converge toward the same value, which decreases in magnitude as the break size becomes spaller.
Therefore, the maximum surface temperature of 315.7 calculated for the 0.5 ft. break with:
. auxiliary feedwater isolation willbound smaller breaks with or without auxiliary feedwater isolation.