ML20202D825
| ML20202D825 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 11/26/1997 |
| From: | Langenbach J GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20202D831 | List: |
| References | |
| 6710-97-2441, IEIN-97-079, IEIN-97-79, NUDOCS 9712050165 | |
| Download: ML20202D825 (2) | |
Text
j GPU % cleat,Inc.
(
Raste 441 South NUCLEAM Midd etowri,l'A 17057 0480 Tel717-944 7621 (717) 948 8005 November 26, 1997 6710 97 244i U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:
Sut> ject:
Three Mile Island Nuclear Station, Unit I (TMI 1)
Operating 1.icense No. DPR 50 Docket No. 50-289 Leakage A;sessment Methodology for TMI l Once-Through Steam Generator (DTSG) Kinetic Expansion Examinatio,i in accordance with NRC's request via conference call on August 28, 1997, this letter prosides the descrirtion of the accident induced leakage assessment methodology for TMI l OTSG kinetic expansion examirationr perfonned during the 12R outage. The attached description outlines the metkJology used to evaluate total accid rd induced piimary-to-secondary leakage from the kinetic expansion region that may be postulated to occur during a dceign basis main steam line break accident. GPU Nuclear has reviewed the issues described in NRC Infonnation Notice No.97-079, dated November 20,1997, and confmned that the TMI l leakage auessment methodology adequately corrects for potential density differences when detemtining the total volumetric leakage flow rate.
GPU N.iclear is available to discuss any NRC questions on this material. If any additional intbrmation is needed, please contxt Mr. David J. Distel, GPU Nuclear, Regulatory AfTairs at (201) 316 7955.
Sincerelg /MW g
James V, Langenbach Vice President and Director, TMI
/DJD-
- Att, I
Cc: Administrator, Region I TMI Senior Resident inspector TMI l Senior Project Manager 0 V-l g 9712050165 971126
$\\\\{$.
t PDR ADOCK 03000289 e
con.
\\
unovus
- ATTACHMENT i
i LEAKAGE ASSESSMENT METHODOLOGY FOR TMI l -
I OTSO KINETIC EXPANSION EXAMINATION -
GPU NUCLEAR TOPICAL REPORT #1.'6 i
REVISION 0 r
P 2
t
+
k i
+
?
[
t-f f
f i
t
_.._...-_.,_.--,l
- .~,... -. _., ~... _ - _, - _ _ _ _, _ _ _. -.... _........
,,.... ~ _