ML20238C437
| ML20238C437 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 09/01/1987 |
| From: | Bailey J GEORGIA POWER CO., SOUTHERN COMPANY SERVICES, INC. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| GN-1395, NUDOCS 8709100103 | |
| Download: ML20238C437 (2) | |
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Gecrgia Power Company Fbst Othce Box 282 Waynesboro, Georgia 30830 Telephone 404 554 9961 404 724-8114 Southern Company Services, Inc.
l Fbst Office Box 2625 h
Birmingham, Alabama 35202
. Telephone 205 870 6011 Vogtle Project L
i-September 1, 1987 i
United States Nuclear Regulatory Commission Attn: Document Control Desk File: X7BC35 Washington, D. C.
20555.
Log: GN-1395 NRC DOCUMENT NUMBER 50-425 CONSTRUCTION PERMIT NUMBER CPPR-109 V0GTLE ELECTRIC GENERATING PLANT UNIT 2 PLANT SAFETY MONITORING SYSTEM VERIFICATION AND VALIDATION Gentlemen:
A verification and validation (V&V) program was conducted on the Plant Vogtle Unit 1 Plant Safety Monitoring Systet (PSMS) to ensure
' the functionality of the system to a level commensurate with that described in the system requirements.
The V&V program was completed in May 1987 with the results transmitted to the NRC in letter GN-1373 dated June 1,
1987.
The NRC staff has reviewed this submittal and concluded that the Vogtle PSMS V&V program is acceptable (letter dated August 25,1987).
Following completion of V&V on Unit 1, the software and hardware differences with Unit 2 were determined.
The only differences
' identified were determined to be minor software changes in the display units.
The software change:: affected only Page 2 Primary Trends, Page 3 Primary Trends, Page 6 Detail Data and Core Temp T/C display pages.
These changes impacted only 5 units of code specific to the plasma displays.
No trouble or clarification reports were issued during the verification process. Furthermore, no trouble or clarification reports were filed during the validation process.
h M 24 N
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A File:
X7BC35 Log: GN-1395 September 1, 1987 Page two In summary, following the completion of the Plant Vogtle Unit 1 PSMS V&V program, the differences between the Unit I and Unit 2 hardware and software were determined.
Only 5 sof tware units were determined to differ between the two units.
In addition, only 4 plasma display pages were impacted.
The results of the V&V testing of the differences between the two units indicated that no verification and validation trouble and clarification reports were generated.
As such, the V&V program on the Plant Vogtle PSMS is considered to be completed successfully.
Should you have any questions, please inquire.
')
Sincerely,
~ ~
b. Ib J. A. Bailey Project Licensing Manager l
A JAB /wk1 xc: NRC Regional Administrator NRC Resident Inspector J. P. O'Reilly R. E. Conway P. D. Rice L. T. Gucwa R. A. Thomas J. E. Joiner, Esquire M. A. Miller (2)
G. Bockhold, Jr.
R. Goddard, Esquire D. Feig R. W. McManus Vogtle Project File i
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