JPN-98-045, Submits Corrected 90 Day Response to GL 97-04, Assurance of Sufficient NPSH for ECC & Containment Heat Removal Pumps
| ML20155G465 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/02/1998 |
| From: | James Knubel POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-97-04, GL-97-4, JPN-98-045, JPN-98-45, NUDOCS 9811090060 | |
| Download: ML20155G465 (2) | |
Text
.
123 Main Street Wh te Plains. New York 10301 914 681.6950 914 287.3309 (Fax)
M NewYorkPower a.m.. x es.'
4# Authority 27172,"#
November 2,1998 JPN-98-045 United States Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 Washington, D.C. 20555
Subject:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Correction to 90-day Response to NRC Generic Letter 97-04
References:
1.
NYPA letter, J. Knubel to USNRC dated December 23,1997 (JPN-97-039/IPN-97-176) regarding 90-day response to NRC GL 97-04.
2.
NRC Generic Letter 97-04, " Assurance of Sufficient Net Positive Suction Head for Emergency Coro Cooling and Containment Heat Removal Pumps," dated October 7,1997.
Dear Sir:
The Authority has identified the need for a enrrcotion to its response (Reference 1) to NRC Generic Letter 97-04 (R3ference 2) for the FitzPatrick plant.
In response to Question 4, the Authority stated " Torus overpressure is initia//y required at approx / mate /y the eighteenth hour after the initiation of the event" (emphasis added). This statement should have read " Torus overpressure peaks during the eighteenth hour..." (emphasis added).
Note that Figures 1 and 2, which show graphically containment press vs. time after initiation of the event, were correct and accurately reflect the revised statement.
The text of the response to Question 4 was not consistent with the information presented in Figures 1 and 2.
This change does not affect the overall conclusion of the letter. Available NPSH (net positive suction head) for the emergency core cooling and containment heat removal systems at FitzPatrick is adequate.
I 9s11090060 9eij'oN 3 h
fDR ADOCK 05000333 PDR
~
e
?
There are no new commitments contained in this letter. If you have any questions, pleage contact Ms. Charlene Faison.
l j
Very truly yours, r
1 Knube l
. Vice President and Chief Nuclear Officer cc:
l l
Regional Administrator United States Nuclear Regulatory Commission 475 Allendale Road l
King of Prussia, PA 19406 l
Office of the Resident inspector l
United States Nuclear Regulatory Commission P.O. Box 136 Lycoming, NY 13093 Mr. Joseph Williams, Project Manager Project Directorate I-1
[
Division of Reactor Projects - 1/ll United States Nuclear Regulatory Commission Mail Stop OWFN 1482 Washington, D.C. 20555 i
I s
t 1
.