ML20214R264

Draft SER Addressing Qualification & Documentation of Isolators as Acceptable Interface Devices Between Class 1E Instrumentation & non-Class 1E Spds,Per NUREG-0737,Suppl 1. Devices Acceptable

ML20214R264
Person / Time
Site:	Beaver Valley
Issue date:	03/13/1987
From:	EG&G IDAHO, INC.
To:
Shared Package
ML20214R246	List: ML20214R244 ML20214R264
References
RTR-NUREG-0737, RTR-NUREG-737 GL-82-33, NUDOCS 8706080058
Download: ML20214R264 (3)

Text

e SAFETY EVALUATION REPORT BEAVER VALLEY POWER STATION, UNIT NO. 1 SAFETY PARAMETER DISPLAY SYSTEM I. BACKGROUND Each operating reactor shall be provided with a Safety Parameter Display System (SPDS). The Commission requirements for an SPDS are defined in NUREG-0737, Supplement 1. In the Regional Workshops on Generic Letter (GL) 82-33, which were held during March 1983, the NRC discussed these requirements and the staff's review of the SPDS.

In order to satisfy the NRC requirements concerning the SPDS, Duquesne Light Company submitted a response to GL 82-33 by letter dated April 15, 1983 (Ref. 1). This response provided a description of the SPDS at the Beaver Valley Power Station, Unit No.1. However, the requirement that the SPDS must be suitably isolated from equipment and sensors that are used in safety systems to prevent electrical and electronic interference was not addressed in sufficient detail in the response.

On April 9, 1986 (Ref. 2), a request for additional information (RAI), which included specific questions on these isolators, was sent to the licensee. The requested information was received in a letter dated February 17, 1987 (Ref. 3).

This evaluation addresses the qualification and documentation of the isolators as acceptable interface devices between Class 1E instrumentation and the non-Class 1E SPDS.

EG&G Idaho, Inc. assisted the staff in the review of the plant-specific submittals.

1 1

8706080058 E70313 4 ADOCK 05000 gDR

e II. DISCUSSION AND EVALUATION TheSPDSattheBeaverdalleyPowerStationUnit1,isa i Westinghouse-supplied system. The system is a computer-based data display system designed to present an account of the overall plant safety status to the control room operators and supervisors.

The SPDS Class 1E inputs are isolated from the non-Class 1E SPDS by.

Westinghouse Series 7100 and 7300 process instrumentation isolation amplifiers. The Series 7100 isolation devices are reported on in WCAP-7819, " Test Report, Nuclear Instrumentation System Isolation Amplifier" (1/72) and-in WCAP-7824, " Isolation Tests Process Instrumentation Isolation Amplifier Westinghouse Hogan Computer Systems Division Model 131-110" (12/71). The Series 7300 isolation devices are reported on in WCAP-8892-A, " Westinghouse 7300 Series Process Control System Noise Test" (6/72).

The Series 7100 isolation devices were reviewed and accepted by the staff in their review of the Trojan SPDS (Ref. 4); the Series 7300 isolation devices were reviewed and accepted by the staff in their review of the Farley SPOS (Ref. 5).

III. CONCLUSION .

Based on the staff's review of the licensee's submittals with respect to the Westinghouse 7100 and 7300 Series isolation devices and on the prior review and acceptance of identical isolators at other plants, the staff concludes that these devices are qualifi.ed isolators and are acceptable for interfacing the SPDS with Class 1E systems. The staff also concludes that this equipment meets the Commission's requirements in NUREG-0737, Supplement 1.

2 l l

1

e IV .- REFERENCES

1. Lett,er dated April 15, 1983, from J. J. Carey (DLCo) to l, D. G. Eisenhut (NRC), " Generic Letter No. 82-33; Supplement 1 to i

NUREG-0737."

2. Letter dated April 9, 1986, from P. S. Tam (NRC) to J. J.'Carey

, (DLCo), " Request for Additional Information, Beaver Valley, Unit 1, Safety Parameter Display System."

3. Letter dated February 17, 1987,~ from J. D. Sieber (DLCo.) to V. S. NRC, " Request for Additional Information of SPDS."

4. Letter dated April 26, 1985, from F. Rosa (NRC) to W. H. Regan (NRC), " Trojan - Review of Isolation Devices that Interface with the SPDS."

5. Letter dated December 7, 1984, from F. Rosa (NRC) to V. A. Moore (NRC), "Farley 1 and 2 - Review of the Isolation Devices that

, Interface with the SPDS."

t

,i i

i r

I f.

3 a

4 4

- . . , . , r..-,, --- .- . . + - , - , - - , , . , . -

, - ,.m. , n,, ,,.,ge,,,,, , , , . ,,,. .,y. , , ,.,, , ~,w., ,, , .--, - , . . -p g ,,-n