ML20206S826

Forwards Final Summary Rept of Human Factors Review for Lasalle Station Spds. Parameters Currently Displayed Sufficient to Aid Plant Operators in Maintaining Plant Critical Safety Functions

ML20206S826
Person / Time
Site:	LaSalle
Issue date:	06/30/1986
From:	Allen C COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20206S831	List: ML20206S826 ML20206S857
References
RTR-NUREG-0737, RTR-NUREG-737 1827K, NUDOCS 8607070435
Download: ML20206S826 (2)

Text

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Commonwealth Edison Z_ ; 72 West Adams Street, Chicago, Illineis U

Address Reply tz Post Offics Box 767 t

Chicago, Illinois 60690-0767 i

June 30, 1986 1

l e

Mr. Harold R. Denton, Director i

Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission l

Washington, DC 20555 l

i

Subject:

LaSalle County Station Unts 1 and 2 Safety Parameter Display System 1

Human Factors Review and Parameter Selection Verification NRC Docket Nos. 50-373 and 50-374 References (a): LaSalle County Station Unit 2 License NPF-18, Facility Operating License (Att. 2)

(b): Commonwealth Edison Company (CBCo) letter, I

i E. Swartz (Ceco) to H. Denton Nuclear Regulatory Commission (NRC) dated I

December 29, 1983 with attachment.

(c): NRC Safety Parameter Display System Safety Evaluation for Dresden, Quad Cities and LaSalle to D. L. Farrar (CECO) from D. M.

Crutchfield (NRC) dated June 23, 1984.

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Dear Mr. Denton:

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Enclosed is commonwealth Edison Company's document entitled " Final Summary Report of the Human Factors Review for the LaSalle Station Safety Parameter Display System" dated June 26, 1986. We are transmitting this information to you in response to the requirement contained in Attachment 2 4

l of Reference (a), Items 1.(a).ii and 1.(a).iii. This transmittal covers the j

human factors review of the SPDS data display and functions and provides j

additional verification data supporting the SPDS parameter selection.

f Commonwealth Edison initially submitted our SPDS safety analysis and I

criteria for parameter selection for LaSalle County Station on December 29, 1983 (Reference (b)). Subsequently, the NRC issued a Safety Evaluation f

Report (Reference (c)) which found the SPDS parameter selection process and variables acceptable and that the SPDS design should continue to be coordinated with the Emergency Procedure Guidelines. Section 6.3 in the enclosed report discusses at length the evaluation of SPDS parameters with i

respect to the DCRDR Task Analysis and Validation Data. This task analysis survey was based on the control room responses and actions required to effectively mitigate those emergency symptoms identified in the GE BNROG j

EPG's.

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8607070435 860630 Y

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Mr. H. R. Denton June 30, 1986 In summary, the findings of this evaluation confirm that the parameters currently displayed on the SPDS are sufficient to aid the plant operator in accomplishing and maintaining the plant critical safety functions. They also confirm that this SPDS effort has been sufficiently integrated with the other NUREG-0737, Supplement 1 initiatives. We also conclude that human factors engineering principles have been sufficiently addressed in the design and installation of this SPDS. The human factors deficiencies identified in this review will be resolved on a schedule consistent with the integration effort on the other NUREG 0737 Supplement 1 initiatives and completion of the SPDS Verification & Validation program.

If you have any questions or comments relating to this information, Please do not hesitate to contact me.

Very truly yours, C. M. Allen Nuclear Licensing Administrator im Enclosures cc:

Dr. A. Bournia LaSalle Resident Inspector 1827K L

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