ML20198P258
| ML20198P258 | |
| Person / Time | |
|---|---|
| Site: | Waterford |
| Issue date: | 11/05/1997 |
| From: | Ewing E ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-97-04, GL-97-4, W3F1-97-0255, W3F1-97-255, NUDOCS 9711070041 | |
| Download: ML20198P258 (4) | |
Text
- - - _ _ - _ _ _ _ - _. _ _ _ _ _ - _ _
Ente gy per;tions, inc.
f Kdlona LA 70004 Tel 504 739 6242 Early C. Ewing, til a ety & Regulatory AMacs W3F1-97-0255 A4.05 PR November 5,1997 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555
Subject:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 Generic Letter 97-04, " Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps" Gentlemen:
On October 7,1997, the NRC issued Generic Letter 97-04, " Assurance of Sufficient Net Positivo Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps." The purpose of the Generic Letter is to confirm the adequacy of the Net Positive Suction Head (NPSH) available for emergency core cooling (including core spray and decay heat removal) and containment heat removal pumps.
Relative to the respective reactor facility, a review was requested of the current design-basis analyses used to determine the available NPSH for the emergency core cooling (including core sr, ray and decay heat removal) and containment heat removal pumps that meet e"aer of the following criteria:
(1) pumps that take suction from the containment sump or suppression pool
)T following a design-basis LOCA or secondary line break, or I
(2) pumps used in " piggyback" operation that are necessary for recirculation cooling of the reactor core and containment (that is, pumps that are supplied f
by pumps which take suction directly from the sump or suppression pool).
p 9711070041 971105 8 !"
lilE!E!Elt!It!!ylill
^
c
, Generic Letter 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps W3F1-97-0255 Page 2 November 5,1997 Based on this review, within 90 days from the date of this generic letter, NRC requested information outlined below for our facility be provided.' New NPSH analyses are neither requested nor required.
1.
Specify the general methodology used to calculate the head loss associated with the ECCS suction strainers.
2.
Identify the required NPSH and the available NPSH.
3.
Specify whether the current design-basis NPSH analysis differs from the most recent analysis reviewed and approved by the NRC for ww a safety.
evaluation was issued.
4.
Specify whether containment overpressure (i.e., containment pressure above the vapor 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 available NPSH, confirm that an appropriate containment pressure analysis was done-to establish the minimum containment pressure, The subject Generic Letter requests that within 30 days of the date of the Generic Letter a response be provided indicating:- (1) whether or not the requested information will be submitted, and (2) whether or not the requested information will be submitted within the requested time period. Eatergy, Waterford 3, will submit the requested information within 90 days as identified in the Generic Letter.
L c
~
. Generic Letter 97-04, Assurance of Sufficient Net Positive Suction Head for -
Emergency Cors Cooling and Containment Heat Removal Pumps W3F1-97-0255 Page 3 November 5,1997 Please contact me at (504) 739-6242 or Tim Gaudet (504) 739-6666 should there be any questions regarding this letter.
Very truly yours, E.C. Ewing Director Nu lear Safety & Regulatory Affairs ECE/ PRS /ssf cc:
E.W. Merschoff, NRC Region IV C.P. Patel, NRC-NRR J. Smith N.S. Reynolds NRC Resident inspectors Office
l t
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION in the matter of
)
)
Entergy Operations, Incorporated
)
Docket No. 50 382 Waterford 3 Steam Electric Station
)
AFFID/Wil Early Cunningham Ewing, being duly sworn, hereby deposes and says that he is Director, Nuclear Safety & Regulatory Affairs - Waterford 3 cf Entergy Operations, incorporated; that he is duly authorized to sign and file with the Nuclear Regulatory Commission the attached Response to NRC Generic Letter 97-04; that he is familiar with the content thereof; and that the matters set forth therein are true and correct to the best of his knowled e, information and belief.
0
~ 2hIm -
"EarigCunningher/ Ewing N,
N' Director, Nuclear Safety & Regulatory Affairs Waterford 3 STATE OF LOUISIANA
)
) ss PARISH OF ST. CHARLES
)
Subscribed and sworr; to before me, a Notary Public in and for the Farish and State above named this T#3 day of /ph._Z,_
.1997.
N.
c_ L r
Notary Public My Commission expires < d < dor /
l,,
,