ML20247G406
| ML20247G406 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 03/27/1989 |
| From: | Bailey J GEORGIA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-3.D.1.1, TASK-TM GN-1586, NUDOCS 8904040217 | |
| Download: ML20247G406 (2) | |
Text
_ _ _, _ _. _ _. _. _ _ _ _ _. _
Georgia WW.* Companp Post Off ace Box 282
- Waynesboro, Georgia 30830 q
"Telepho,e 404 554 9 % 1 404 724 8114 Southern Company Services. Inc R
Post Office Box 2625 Birmingham Alabama 35202 Telephone 205 870-6011 Vogtle Proj.ect March 27, 1989 United States Nuclear Regulatory Commission ATTN:
Document Control Desk File:
X7BC35 Washington, D. C.
20555 Log: GN-1586 PLANT V0GTLE - UNIT 2 NRC DOCKET NUMBER 50-425 OPERATING LICENSING NUMBER NPF-79 TMI ITEM III.D.1.1: LEAKAGE OUTSIDE CONTAINENT Gentlemen:
Georgia Power Company hereby submits a report regarding the results of an examination for potential leakage outside containment pursuant to item III.D.1.1 of NUREG 0737.
Should you have questions regarding this submittal, please contact this office.
Si
- erely,
=
. h, J. A. Bailey Project Licensing Manager JAB /PG:pwh Enclosure xc: NRC Regional Administrator NRC Resident Inspector P. D. Rice J. P. Kane R. A. Thomas B. W. Churchill, Esquire J. E. Joiner, Esquire J. B. Hopkins (2)
G. Bockhold, Jr.
R. J. Goddard, Esquire l
R. W. McManus Vogtle Project File l
Gh i
8904040217 890327 PDR ADOCK 05000425 P
^
In accordance with requirements set forth in Facility Operating License NPF-79 and Technical Specifications, Section 6.0, for Vogtle Electric Generating Plant, Unit 2,
the following data is presented to document leakage from primary coolant sources outside containment.
For items A through F below, the leakage was quantitatively mea 1ured for each component identified as leaking in accordance with VEGP procedures 55010-2, 55011-2, 55012-2, 55014-2, 55015-2, and 55016-2.
The Gaseous Waste Processing System leakage assessment was performed under acceptance test 2-4HA-01,
" Waste Processing System-Gas, Leak Rate Test".
For the liquid systems, the leakage survey was performed at or as near as practical to operating temperatures and pressures.
All leakage paths were identified visually.
Gaseous system leakage was measured using a leak rate monitor while a soap bubble solution was used to identify leakage paths.
The following systems were leak tested with the total system leakage as noted:
A.
Residual Heat Removal System
.00075 GPM B.
Containment Spray System (Excluding
.00258 GPM the NaOH portion)
C.
Safety Injection System (Excluding
.01030 GPM the Accumulators)
D.
Chemical and Volume Control System
.02600 GPM (Letdown, Charging and Boron Recycle)
E.
Post Accident Sampling System
.00004 GPM F.
Nuclear Sampling System (Pressurizer
.00007 GPM Steam and Liquid Sample Lines, Reactor Coolant Sample Lines, RHR Sample Lines, CVCS Demineralized, and Letdown Heat Exchanger Sample Lines only) j G.
Gaseous Waste Processing System Gaseous 50 cc/ min Liquid 0
GPM This report satisfies reporting requirements delineated in the aforementioned license and Technical Specifications for Unit 2.
The above leakage is considered acceptable although further efforts will be made to reduce all known leakage to a level as low as practical.
.