ML20133B142

Forwards Rev 0 to SPDS SAR for Georgia Power Co, Alvin W Vogtle Nuclear Power Plant. Rept Provides SPDS Implementation Plan & Sar,Per Requirements of Suppl 1 to NUREG-0737

ML20133B142
Person / Time
Site:	Vogtle
Issue date:	09/27/1985
From:	Bailey J GEORGIA POWER CO., SOUTHERN COMPANY SERVICES, INC.
To:	Adensam E Office of Nuclear Reactor Regulation
Shared Package
ML20133B144	List: ML20133B142 ML20133B158
References
RTR-NUREG-0737, RTR-NUREG-737 GN-709, NUDOCS 8510030044
Download: ML20133B142 (3)

Text

g . - - -

Georgia Power Company

, Routs 2. Box 299A Wyisboro, Georco 30830 Telephone 404 554 9961 404 724-8114 Southern Company Serwces, Inc.

Post Office Box 2625 Birmingham, Alabama 35202 Telephone 205 8704011 l September 27, 1985 l

l l

i Director of Nuclear Reactor Regulation Logt GN-709 Attention Ms. Elinor G. Adensam, Chief Files X5AB04 Licensing Branch #4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 l NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 A!;D CPPR-109 V0GTLE ELECTRIC GENERATING PLANT-UNITS 1 AND 2 l SAETY PARAMETER DISPLAY SYSTEM IMPLEMENTATION l

l Dear Mr. Dentont l

Attached for your review are five (5) copies of information related to the implementation of a Safety Parameter Display System (SPDS) for Plant Vogtle-Units 1 and 2. The attachments provide the SPDS implementation plan and the SPDS Safety Analysis Report prepared for Georgia Power Company by Energy Incorporated. This infortsation is provided in accordance with the requirements of NUREG-0737, Supplement 1.

If your staff requires any additional information please do not hesitate to contact me.

Sincerely,

.h.

J. A. Bailey l

Project Licensing Manager JAB /rik/can l Attachment xet D. O. Foster G. Bockhold, Jr.

R. A. Thomas T. Johnson (w/o att.)

J. E. Joiner, Esquire D. C. Teper (w/o att.)

l B. W. Churchill, Esquire L. Fowler M. A. Miller (2) W. C. Ramsey B. Jones (w/o att.) Vogtle Project File L. T. Gucwa l

S,BA'*1880A 5%J4 M I h

---

_-------------__--------------_------a

l i

l l

SPDS IMPLEMENTATION PLAN As a result of the Three Mile Island nuclear power plant accident on March 28, 1979, and the subsequent studies of needed improvements to nuclear power plant l

safety, the Nuclear Regulatory Commission (NRC) and the nuclear industry I

identified the need for a Safety Parameter Display System (SPDS). The SPDS will provide a concise display of critical plant parameters to the control-room operators to aid them in rapidly and reliably determining the safety status of the plant. The SPDS is in addition to the control-room instrumentation required by General Design Criteria 13 and 19 of Appendix A to 10 CFR 50 that provides the operators with the information necessary for safe reactor operation under normal, transient, and accident conditions. The SPDS, therefore, represents an improvement to the centrol room as it enhances the operator's ability to rapidly comprehend plant conditions and to interact in situations that require human intervention.

The SPDS for the Vogtle Plant will be integrated into a comprehensive computer system that includes the emergency response facilities (ERF) data acquisition, data processing, and display functions. The SPDS will utilize cathode-ray tube (CRT) monitors, strategically placed and having appropriate man-machine interfaces. By means of user-called displays, an abundance of information on the safety status of the plants can be quickly made available to operations and technical staff.

j NUREG-0737, Supplement 1, requires that, as a minimum, the SPDS must provide safety status information to plant operators that includest (1) reactivity control, l

(2) reactor core cooling and heat removal from the primary system, I (3) reactor coolant system integrity, (4) radioactivity control, and (5) containment conditions.

The Vogtle SPDS will use the following categories based on the Emergency Response Guideline recommendations of the Westinghouse Owner's Group for critical safety function status monitoring: l (1) reactivity, (2) core cooling, (3) heat sink.

(4) reactor cooling system integrity,

! (5) reactor cooling system inventory, and l (6) containment l

I 0164V

SPDS Implementation Plan Page 2 In addition to the parameters necessary to provide information on the status of the critical safety functions, the operator has information available from the Plant Effluent Radiation Monitoring System (PERMS) as well as other Regulatory Guide 1.97 parameters and other parameter inputs into the ERF computer. The SPDS Safety Analysis Report provides a detailed discussion of the parameters selected for the SPDS and their justification. The control room will have two (2) CRT consoles for SPDS and one CRT console for use by the Shift Supervisor. The SPDS consoles are interlocked such that the top level SPDS display will be presented on at least one of the two CRTs continuously so that the operator always has the status of the critical safety functions. Inputs to the ERF computer are provided via data links or multiplexer units. All class 1E safety-related input signals to the ERF computer and SPDS are provided with class 1E isolation devices provided by Westinghouse. This prevents the operation of the ERF computer, or faults developing in the ERF computer system, from affecting the operation of the normal safety-related displays in the control room. The control room displays of the individual parameters provide the backup display to the SPDS. The inputs to the ERF computer system, and therefore the SPDS, are validated through the use of validation algorithms which entail the use of such factors as comparison of redundant sensors, comparison of similar sensors, or independent calculation based on separate parameters.

The human factors aspects of the SPDS design will be evaluated as part of the control room design review process. An independent verification and validation review of the SPDS design and installation will be performed by Energy Incorporated using the guidelines available from NSAC and the ERC NUTAC. The SPDS system has been installed on the VEGP simulator for use in operator training and evaluation. This gives the operators hands-on experience in the use of the SPDS and has facilitated valuable feedback from the operators on ways to improve the SPDS displays.

The installation of the SPDS hardware and sof tware in the Unit 1 main control room will be completed prior to fuel load for Unit 1.

l l

l 0164V

. .. .