ML20235Y077
| ML20235Y077 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 07/20/1987 |
| From: | Gucwa L GEORGIA POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM SL-2889, NUDOCS 8707250069 | |
| Download: ML20235Y077 (3) | |
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Georgia Power Company
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333 Piedmont Avenue Atlanta, Georgia 30308 Telephone 404 5266526 Maibng Address f%t Office Box 4545 Atlanta, Georgta 30:l02 h
GeorgiaPower aa_
ve.~ w m:c u vm M~1 nager Nuclear Safety and Licensing SL-2889 0423m l
l July 20, 1987 U. S. Nuclear Regulatory Commission I
ATTN:
Document Control Desk j
Washington, D.C.
20555 i
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oLANT V0GTLE - UNIT 1 l
NRC DOCKET 50-424 i
OPERATING LICENSE NPF-68 REACTOR VESSEL LEVEL INDJCATION SYSTEM C
l Gentlemen:
l This letter documents the June 18, 1987 conference call between i
Georgia Power Company (GPC) and NRC regarding the Reactor Vessel Level J
Indicatica System (RVLIS).
The purpose of the call was to respond to the NRC's verbal rrquest on June 15, 1987 to describe differences between the Vogtle RVLIS and other RVLIS designs used by Westinghouse.
The Westinghouse RVLIS design has not changed significantly since its fi rs t implementation.
It remains in essence a system which provides indication of reactor vessel level by measuring differential pressure under conditions of forced or natural circulation in the Reactor Coolant l
System.
There have been, however, some modifications to accommodate different Reactor Coolant System configurations, as well as some modifications which are evolutionary in nature.
ELPJHG Some plants employ Upper Head Injection (UHI) to the reactor vessel head while others, such as 'fogtle, do not.
The upper RVLIS connection in UHI plants is taken from the reactor coolant hot legs; in non-UHI plants it is taken from the standpipe connection on the reactor vessel head.
There are also differences in the connection point for the middle RVLIS tap (used for upper range indication).
Some non-UHI plants, such as Vogtle, utilize a reactor coolant system hot leg tap, while others utilize an RTD bypass manifold tap.
8707250069 070720 f
DR ADOCK 05000424 PDR go
i U. S. Nuclear Regulatory Commission j
July 20, 1987 Page Two ELECTRONI_CS i
i Di f ferences in this area are evolutionary.
The original design utilized analog-based signal processing using the 7300 Process i
Instrumentation System.
This sysdem provided a panel-mounted display meter for indication.
This system was replaced by a digital-based system
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using an 8080 microprocessor, which evolved to one using an 8086 1
microprocessor such as that used at Plant Vogtle.
The digital system electronics are part of the Plant Safety Monitoring System (PSMS) and utilize either CRT display or plasma display, such as at Vogtle, at the main control board.
The Vogtle RVLIS is installed in accordance with the Westinghouse design which was reviewed and approved by NRC as discussed in Supplement 4 to the Vogtle SER.
The RVLIS as well ac the core exit thermocouple are fully operational, thus completing the requirements of NUREG-0737 Item II.F.2, Instrumentation for Detection of Inadequate Core Cooling, for Vogtle Unit 1.
Please contact this office if you have any questions.
Sincerely, W =& + =
L. T. Gutwa JH/lm c:
(see next page) l mus
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Georgia Power 1 1
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U. S. Nuclear Regulatory Commission July 20, 1987 Page Two I
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Georgia Pow _gtr JampAny Mr. R. E. Co.rway Mr. J. P. O'Reilly l
Mr. G. Bockhold, Jr.
Mr. J. F. D'Amico Mr. C. H. Hayes GO-NORMS l
Southern Company _Strvices j
Mr. R. A. Thomas Mr. J. A. Bailey Shaw. Pittman. Potts & Trowbridge Mr. B. H. Churchill, Attorney-at-Law Troutman. Sanders. L&ckerman & Ashmore l
Mr. A. H. Domby, Attorney-at-Law U. S. Nucigan Rgtgillatory Commission I
Dr. J. N. Grace, Regional Administrator Ms. M. A. Miller, Licensing Project Manager, NRR (2 copies)
Mr. J. F. Rogge, Senior Resident Inspector-0perations, Vcgtle
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l GeoroianLAg_ainst Nucleaf Enerav
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Mr. D. Feig 1
Ms. C. Stangler j
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