ML20153F408
| ML20153F408 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 05/04/1988 |
| From: | Nauman D SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8805100317 | |
| Download: ML20153F408 (2) | |
Text
%
th Caronna Electric & Gas Company A.
Jenkinsville. SC 2906$
Nuclear Operations SCEAG
. ~...
May 4, 1988 Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. C. 20555
SUBJECT:
Virgil C. Summer Nuclear Station Docket Nc. 50/395 Operating License No. NPF-1 Implementation of ATWS Rule (10CFR50.62) Supplemental Information Gentlemen:
As requested by your Staff during a conference call on April 20, 1988, the attached provides the supplemental information supporting the South Carolina Electric & Gas Company March 24, 1988 submittal for implementation of tM ATWS rule.
Should you have any questions, please call at your convenience.
Very truly yours, dk ds?
O. A. Nauman M08:0AN/1cd Attachment pc:
J. G. Connelly, Jr./0. W. Dixon, Jr./T. C. Nichols, Jr.
E. C. Roberts W. A. Williams, Jr.
G. O. Percival J. N. Grace R. L. Prevatte J. J. Hayes, Jr.
J. B. Knotts, Jr.
General Managers M. D. Blue i
C. A. 1 rice T. L. Wessner R. B. Clary NSRC W. R. Higgins RTS (LTR000620)
R. M. Campbell, Jr.
NPCF K. E. Nodland File (810.12)
J. C. Snelson b*
8005100317 880504 DR p
ADOCK 05000395 PDR
\\
I AMSAC SAFETY EVALUATION REPORT SUPPLEMENTAL RESPONSE FOR VIRGIL C. SulWER NUCLEAR STATION UNIT 1 On March 24, 1988, South Carolina Electric & Gas Company submitted a report to the Nuclear Regulatory Commission in response to the Safety Evaluation of i
the Westinghouse Oxners Group Topical Report WCAP-10858, "AMSAC Generic l
Design Package," dated February 23, 1987.
l On May 20, 1988, the NRC Staff requested supplemental information in clarification of the following items from the March 24, 1988 submittal.
Safety-Related Interfacq The interface between AMSAC and the reactor protection system (RPS) is in accordance with the Virgil C. Summer Nuclear Station design basis as described in the Final Safety Evaluation Report (FSAR) Section 7.1 and fully complies with the requirements of IEEE Standard 279-1971, "Criteria for Protection Systems for Nuclear Power Generation Stations." The installation and interface of AMSAC will not affect the ability of the RPS to perform its design function as described in FSAR Section 7.0.
In addition, all isolation devices utilized with AMSAC meet IEEE Standard 344-1975, "IEEE Standard for Seismic Qualification of Class 1E Electrical Equipment for Nuclear Power Generation Stations."
Testability at Power The AMSAC actuation logic shall be tested at least every 62 days. Testing of the actuation logic verifies analog channel accuracy, setpoint accuracy, coincidence logic operation (operation and accuracy of all timers), and continuity through the output relay coils.
Every refueling outage through a series of surveillance tests, the system will be tested from end-to-end, that is, from the sensor through the final actuation devices.
The sensors for steam generator narrow range level and turbine first stage pressure will be tested as a part of the normal reactor protection system testing. The AMSAC actuation logic will be tested using the surveillance test described above.
Lastly, an additional surveillance test will test output relay actuation and' equipment actuation.
j Completion of MitiQative Action Positive operator action must be taken to recover from the AMSAC actuation.
The reset of the AMSAC signal will not result in any changes to equipment status or alignment.
__-_-