ML17277B482

Forwards Request for Addl Info Re Safety Parameter Display Sys.Response Requested within 60 Days of Ltr Receipt

ML17277B482
Person / Time
Site:	Columbia
Issue date:	08/10/1984
From:	Schwencer A Office of Nuclear Reactor Regulation
To:	Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
References
NUDOCS 8408280339
Download: ML17277B482 (6)

Text

August 10, 1984 Docket No.:

50-397 Mr. G.

C. Sorensen, Manager Regulatory Programs Washington Public Power Supply System P. 0.

Box 968 3000 George Washington Way Richland, Washington 99352

Subject:

Request for Additional Information - Safety Parameter Display System (SPDS)

The 'staff has reviewed your submittal concerning the Safety Parameter Display System (SPDS) and conclude that additional information is needed to complete our evaluation.

The requested information is detailed in the attached enclosure.

Pl'ease provide your response within 60 days after receiving this request.

Sincerely,

Enclosure:

As Stated cc w/enclosure See next page A. Schwencer, Chief Licensing Branch No.2 Division of Licensing DISTRIBUTION NRC PDR Local PDR PRC System NSIC LB¹2 Reading B¹ /

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Nr. G. C. Sorensen, Manager Regulatory Programs Washington Public Power Supply System P. 0.

Box 968 3000 George Washington Way

Richland, Washington

- 99352 CC:

Nicholas Reynolds, Esquire

Bishop, Cook, Liberman, Purcell 8

Reynolds 1200 Seventeenth

Street, N.

W.

Mashington, D. C.

20036 Hr. G. E. Doupe, Esquire Washingtoi Public Power Supply System P. 0.

Box 968 3000 George Washington Way

Richland, Washington 99352 Nicholas Lewis, Chairman Energy Facility Site Evaluation Council Mail Stop PY-11 Olympia, Washington 98504 I'.

L. Powell, Licensing Manager Washingtcn Public Power Supply System P. 0.

Box 968

Richland, Washington 99352 Mr. M. G. Conn, Sr. N/N Group Supervisor Burns and Roe, Incorporated 1 Mil'liams Boulevard

Richland, Mashington 99352 R. B. Glasscock, Director Licensing and Assurance Washington Public Power Supply System P. 0.

Box 968, HD 650

Richland, Washington 99352 ter. J.

D. Martin WNP-2 Plant Manager Washington Public Power Supply System P. 0.

Box 968

Richland, Washington 99352

REQUEST FOR ADDITIONAL INFORMATION CONCERNING TME WNP-2 SAFETY PARAMETER DISPLAY SYSTEM Each operating reactor shall be provided with a Safety Parameter Display System (SPDS).

The Commission approved requirements for an SPDS are defined in NUREG-0737, Supplement 1.

In the Regional Workshops on Generic Letter 82-33 held during March 1983, the NRC discussed these requirements and the staff's review of the SPDS.

Prompt implementation of the SPDS in operating reactors is a design goal of prime importance.

The staff's review of SPDS documentation for operating reactors called for in NUREG-0737, Supplement I, is designed to avoid delays resulting from the time required for NRC staff review.

The NRC staff will not review operating reactor SPDS designs for compliance with the requirements of Supplement I of NUREG-0737 prior to implementation unless a

preimplementation review has'een specifically requested by licensees.

The licensee's Safety Analysis and SPDS Implementation Plan will be reviewed by the NRC staff only to determine if a serious safety question is posed or if the analysis is seriously inadequate.

The NRC staff review to accomplish this will be directed at:

(a) confirming the adequacy of the parameters selected to be displayed to detect critical safety functions, (b) confirming that means are provided to assure that the data displayed are valid, (c) confirming that the licensee has committed to a

human factors program to ensure that the displayed information can be readily perceived and comprehended so as not to mislead the operator, and (d) confirming that SPDS will be suitably isolated from electrical and electronic interference with equipment and sensors that are used in safety systems.

If based on this review the staff identifies a serious safety question or seriously inadequate

analysis, the Director of IE or the Director of NRR may require or direct the licensee to cease implementation.

The staff reviewed the SPDS safety analysis and implementation plan provided by WNP-2 (Reference I).

The staff was unable to complete its evaluation because of insufficient information.

The following additional information is required to complete the SPDS evaluations:

ISOLATION DEVICES a

0 For each type of device used to accomplish electrical isolation, describe the specific testing performed to demonstrate that the device is acceptable for its application(s).

This description should include elementary diagrams when necessary to indicate the test configuration and how the maximum credible faults were applied to the devices.

b.

Data to verify that the maximum credible faults applied during the test were the maximum voltage/current to which the device could be exposed, and define how the maximum voltage/current was determined.

c.

Data to verify that the maximum credible fault was applied to the output of the oevice in the transverse mode (between signal and return) and other faults were considered (i.e.,

open and short circuits).

~ d.

Define the pass/fail acceptance criteria for each type of device.

e.

Provide a commitment that the isolation devices comply with the environmental qualifications (10 CFR 50.49) and wish the seismic qualifications which were the basis for plant licensing.

Provide a description of the measures taken io protect the safety systems from electrical interference (i.e.,

Electrostatic

Coupling, EMI, Common Mode and Crosstalk) that may be generated by the SPDS.

HUMAN FACTORS PROGRAM Provide a description of the display system, its human factored

design, and.the methods used and results from a human factors program to ensure that the displayed information can be readily perceived and comprehended so as not to mislead the operator.

PARAMETER SELECTION NUREG-0737, Supplement 1 includes Radioactivity Control as a Safety function for which information should be available to assess the safety status of the plant.

Expand your safety analysis report to include a discussion of the provisions made for WNP-2 to monitor radioactivity control.

Expand your safety analysis to include discussion of such parameters as hydrogen and oxygen monitors in containment to accommodate expected revisions of the Emergency Procedure Guidelines which address Combustible Gas Control.

Expand your safety analysis to include discussion of Source Range Monitors (SRMs) as an indicator of the Reactivity Critical Safety Function during periods of shutdown and startup.

UNREVIENED SAFETY (QUESTIONS Provide conclusions regarding unreviewed safety questions.

REFERENCE 1.

Letter to:

A. Schwencer, NRC, from: G.

D. Bouchey,

>1anager, Nuclear Safety and Regulatory

Programs, Washington Public Power Supply System, subject:

Nuclear Project No. 2, Safety Parameter Display System (SPDS),

Safety Analysis Report, Submittal of July 1, 1983.