ML20133G725

Notifies That Audit of SPDS Originally Scheduled for 850729-30 Will Be Conducted on 850925-29.Revised Agenda Encl

ML20133G725
Person / Time
Site:	Waterford
Issue date:	07/23/1985
From:	Knighton G Office of Nuclear Reactor Regulation
To:	Leddick R LOUISIANA POWER & LIGHT CO.
References
NUDOCS 8508090052
Download: ML20133G725 (6)

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! JUL 2 31985 l

• - Docket No.: 50-382 Mr. R. S. Leddick Louisiana Power and Light Company 317 Baronne Street, Mail Unit 17 i New Orleans, Louisiana 70160 l

SUBJECT:

REVISED AUDIT AGENDA FOR WATERFORD 3 SAFETY PARAMETER DISPLAY SYSTEM l-l' The audit of the Waterford 3 Safety Parameter Display System originally scheduled for July 29-30, 1985 will now be conducted at the site on September 25-29, 1985.

The revised agenda (Enclosure) is being provided so that you may make preparations for the audit.

If you have any qtiestions, contact J. Wilson, the NRC Project Manager at

( (301) 492-7702.

l Sincerely, l

George W. Knighton, Chief Licensing Branch No. 3 j Division of Licensing l

Enclosures:

l As stated cc: See next page Distribution 50 ewer +ned# OELD, Attorney l NRC PDR ACRS (16)

Local PDR PRC System NSIC LB#3 Reading JLee i JWilson JPartlow BGrimes  ;

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Waterford 3 Mr. R. S. Leddick Vice President - Nuclear Operations Louisiar.a Power & Light Company 142 Delaronde Street New Orleans, Louisiana 70174 W. Malcolm Stevenson, Esq. Regional Administrator - Reofon IV Monroe & Leman d. S. Nuclear Regulatory Commission 1432 Whitney Building 611 Ryan Plaza Drive New Orleans, Louisiana 70130 Suite 1000 Arlington, Texas 76012 Mr. E. Blake Shaw, Pittman, Potts and Trowbridge Carole H. Burstein, Esq.

1800 M Street, NW 445 Walnut Street Washington, DC 20036 New Orleans, Louisiana 70118 Mr. Gary L. Groesch Mr. Charles B. Brinkman, Manager P. O. Box 791169 Washington Nuclear Operations New Orleans, Louisiana 70179-1169 Combustion Engineering, Inc.

7910 Woodmont Avenue Suite 1310 Mr. F. J. Drummond Bethesda, Maryland 70814 Project Manager - Nuclear Louisiana Power and Light Company 142 Delaronde Street .

New Orleans, Louisiana 70174 Mr. K. W. Cook Nuclear Support and Licensing Manager Louisiana Power & Light Company 142 Delarande Street New Orleans, Louisiana 70174 Luke Fontana, Esq.

, 824 Esplanade Avenue New Orleans, Louisiana 70116 Resident Inspector /Waterford NPS P. O. Box 822 Kiliona, Louisiana 70066 Mr. Jack Fager Middle South Services, Inc.

l P. O. Box 61000 '

New Orleans, Louisiana 70161 i

Chairman

' Louisiana Public Service Commission One American Place, Suite 1630 Baton Rouge, Louisiana 70804 l

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ENCLOSURE REVISED AUDIT PLAN FOR EVALUATION OF THE WATERFORD 3 SAFETY PARAMETER DISPLAY SYSTEM

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Background

All holders of operating licenses issued by the Nuclear Regulatory Commission (licensees) and apolicants for an operating licensee (OL) must provide a Safety Parameter Display System (SPDS) in the control room of their plant.

The Commission approved requirements for the SPDS are defined in Supplement I to NUREG-0737.

The purpose of the SPDS is to provide a concise display of critical plant variables to control room operators to aid them in rapidly and reliably determining the safety status of the plant. NUREG-0737, Supplement 1, requires licensees and applicants to prepare a written safety analysis describing the basis on which the selected parameters are sufficient to assess the safety status of each identified function for a wide range of events, which include symptons of severe accidents. Licensees and applicants shall also prepare an implementation plan for the SPDS which contains schedules for design, development, installation, and full operation of the SPDS as well as a design verification and validation plan. The safety analysis and the implementation plan are to be submitted to the NRC for staff review. The results of the staff's review are to be published in a Safety Evaluation Report (SER).

Section 18.2 of NUREG-0800, " Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants," describes how the staff performs SPDS reviews for applicants of operating licenses. The staff's review process will evaluate the (1) safety analysis report, (2) the implementation plan, and (3) the verification and validation (V8V) plan. In addition, three separate audit meeting / site visits, as described below, may be arranged through the Division of Licensing Project Manager. As dictated by the comprehensiveness of the applicant / licensee's documentatior and the schedule for design and implementation of the SPDS, the objectives of these audits may be met in fewer site visits. ,

Design Verification Audit:

The purpose of this audit meeting is to obtain additional information required to resolve any outstanding questions about the Verification and Validation (V&V) Program, to confirm that the V&V Program is being correctly

.e implemented, and to audit the results of the V&Y activities to date. At this meeting, the applicant should provide a thorough description of the SPDS

a design process. Emphasis should be placed on how the applicant is assuring that the implemented SPDS will: provide appropriate parameters, be isolated from safety systems, provide reliable and valid data, and incorporate good human engineering practice.

Design Validation Audit:

After review of all documentation, an audit may be conducted to review the as-built prototype or installed SPDS. The purpose of this audit is to assure that the results of the applicant / licensee's testing demonstrate that the SPDS meets the functional requirements of the design and to assure that the .

SPDS exhibits good human engineering practice.

Installation Audit:

As necessary, a final audit may be conducted at the site to ascertain that the SPDS has been installed in accordance with the applicant / licensee's plan and is functioning properly. A specific concern is that the data displayed reflect the sensor signal which measures the variable displayed. This audit will be coordinated with and may be conducted by the NRC Resident Inspector.

Based on the advanced state of the Waterford 3 design, the staff plans to do a combined Design Verification and Design Validation audit on September 25-27, 1985.

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NRC Audit Team The NRC Audit Team will consist of a representative from the Human Factors Engineering Branch, assisted by two consultants from Lawrence Livermore National Laboratory (LLNL).

Agenda Wednesday, September 25, 1985:

2:00 P. M. Entrance briefing by NRC, introductions, discussion of audit 2:20 P. M. agenda.

I 2:30 P.M. Short presentation by Louisiana Power and Light (LP&L) 3:30 P.M. describing the design process and current status of the SPDS; definition of the boundaries of SPDS vis-a-vis the Plant Monitor Computer.

3:30 P.M. LP&L presentations describing details of the design program 5:30 P.M. for SPDS with emphasis on:

1. Human factors analysis, standards, ar.d criteria used in the design process,

2. reliability; (a) design characteristics, (b) methods used to estinate reliability,

3. data validation methodology and its effectiveness across normal and abnorwel conditions, Thursday, September 26. 1985:

8:30 A.M. Description of Verification and Validation Program 12:30 P.M. including:

1. Description of V&V team and demonstration of independence from the design team,

2. scope and depth of V&V Program,

3. available documentation for completed tasks and phases,

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4 4 test cases for validation of SPDS parameters and how '-

they demonstrate the representativeness and useability of selected parameters,

5. human factors aspects,

6. plans for and/or results of dynamic simulator testing.

1:30 P.M. NRC questions and review of V&V documentation, 5:30 P.M.

Short tour of control room or simulator.

Friday, September 27, 1985:

8:30 A.M. Demonstration of SPDS page formats in TSC/ EOF / Simulator.

, 12:00 P.M. Walkthrough of a plant-specific E0P that involves confimation of containment isolation.

1:00 P.M. NRC audit of displays, display fonnats, interface devices, 3:30 P.M. access and response times, etc.

. 3:30 P.M. NRC caucus.

4:00 P.M. Exit briefing. .

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