ML20236X317
| ML20236X317 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/03/1998 |
| From: | Trimble D NRC (Affiliation Not Assigned) |
| To: | Keenan J CAROLINA POWER & LIGHT CO. |
| References | |
| GL-97-04, GL-97-4, TAC-M99966, TAC-M99967, NUDOCS 9808070287 | |
| Download: ML20236X317 (2) | |
Text
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8 UNITED STATES
[
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. Sa" "
August 3,1998 Mr. J. S. Keenan, Vice President Carolina Power & Light Company Brunsy
. Steam Electric Plant Post 't.nce Box 10429 Southport, North Carolina 28461
SUBJECT:
COMPLETION OF LICENSING ACTION FOR GENERIC LETTER 97-04,
" ASSURANCE OF SUFFICIENT NET POSITIVE SUCTION HEAD FOR EMERGENCY CORE COOLING AND CONTAINMENT HEAT REMOVAL PUMPS"- BRUNSWlCK STEAM ELECTRIC PLANT, UNITS 1 AND 2 (TAC l
NOS. M99966 AND M99967)
Dear Mr. Keenan:
The U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 97-04, " Assurance of Sufficient Net Posliive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps," to all holders of operating licenses or construction; permits on October 7, 1997. The NRC issued GL 97-04 to confirm the adequacy of the net positive suction head (NPSH) available for emergency core cooling (inc!uding core spray and decay heat removal) and containment heat removal pumps under all design-basis accident scenarios.
In GL 97-04, the NRC staff specifically requested that licensees provide the information out'ined below for each of their facilities.
1.
Specify the general methodology used to calculate the head loss associated with the Emergency Core Cooling System (ECCS) suction strainers.
2.
Identify the required NPSH and the available NPSH.
I 3.
Specify whether the current design-basis NPSH analysis differs from the most recent analysis reviewed and approved by the NRC for which a safety evaluation was issued.
i 4.
Specify whether containment overpressure (i.e., containment pressure above the vapor l
pressure of the sump or suppression pool fluid) was credited in the calculation of available
{
NPSH. Specify the amount of overpressure needed and the minimum overpressure available.
5.
When containment overpressure is credited in the calculation of avail.csle NPSH, confirm that an appropriate containment pressure analysis was done to establish the minimum containment pressure.
In responso 'o GL 97-04, you provided letters dated November 4,1997, and December 22,1997, for the Brunswick Steam Electric Plant, Units 1 and 2. These submittals provided the information requested by GL 97-04. The staff has reviewed your response and has concluded
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August 3,19.:d 2
that all requested information has been provided; therefore, we consider GL 97-04 to be closed for your facilities. Thank you for your prompt and complete response.
If you have any questions regarding this matter, please contact me at (301) 415-2019.
Sincerely, 1
Original signed by David C. Trimble, Project Manager Project Directorate 11-1 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324 cc: See next page DISTRIBUTION:
Docket File PUBLIC PD ll-1 Reading File J. Zwolinski OGC PT Kuo D. Trimble E. Dunnington ACRS OGC D. Skay, Lead PM J. Kudrick, NRR K. Kavanagh, NRR M. Ernstes C. Patterson I
L, Plisco FILENAME-G:\\BRUNSWIC\\BR99966.ltr OFFICE PM PDll-1 LA PDil-1 BC:SCSB BC:S B D.PDti-1
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h PTN;o NAME DTnmbi EDunnington MD C rlinger T
DATE 7/IkB 7/2898
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