ML20128L178

Advises That Audit of SPDS for Facility Rescheduled for 850812-14,per NRC .Revised Audit Plan Encl

ML20128L178
Person / Time
Site:	Three Mile Island
Issue date:	07/09/1985
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Hukill H GENERAL PUBLIC UTILITIES CORP.
References
NUDOCS 8507240353
Download: ML20128L178 (9)

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July 9,1985 Mf3 Glh Docket No. 50-289 Mr. Henry D. Hukill, Vice President ,

and Director - TMI-I GPU Nuclear Corporation P. O. Box 480 Middletown, Pennsylvania 17057

Dear Mr. Hukill:

l Our letter dated April 5,1985, informed you that the staff's audit of your Safety Parameter Display System (SPDS) for Three Mile Island, Unit I would be rescheduled. With your staff's agreement, the audit is now scheduled for August 12-14, 1985, at the plant site beginning at 10:00am on August 12. A revised audit plan is enclosed for your information. Additional information can be obtained from the Project Manager, Owen Thompson (302-492-7471).

Sincerely, "CDMUd. $1?AT3 U7.#

John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing

Enclosure:

As Stated cc w/ enclosure:

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Mr. Henry D. Hukill Three Mile Island Nuclear Station GPU Nuclear Corporation Unit No. I cc:

Mr. R. J. Toole Mr. Richard Conte 0&M Director, TMI-1 Senior Resident Inspector (TMI-1)

GPU Nuclear Corporation U.S.N.R.C.

Middletown, Pennsylvania 17057 P.O. Box 311 Middletown, Pennsylvania 17057 Richard J. McGoey Manager, PWR Licensing GPU Nuclear Corporation Regional Administrator, Region I 100 Interpace Parkway U.S. Nuclear Regulatory Comission Parsippany, New Jersey 70754 631 Park Avenue King of Prussia, Pennsylvania 19406 Mr. C. W. Smyth THI-1 Licensing Manager Mr. Robert B. Borsum GPU Nuclear Corporation Babcock & Wilcox P. O. Box 480 Nuclear Power Generation Division Middletown, Pennsylvania 17057 Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 G. F. Trowbridge, Esq.

", Shaw, Pittman, Potts & Trowbridge Governor's Office of State Planning 1800 M Street, N.W. and Development Washington, D.C. 20036 ATTN: Coordinator, Pennsylvania State Clearinghouse Ivan W. Smith, Esq., Chairman P. O. Box 1323 Atomic Safety and Licensing Board Harrisburg, Pennsylvania 17120 U.S. Nuclear Regulatory Comission Washington, D.C. 20555 Mr. Earl B. Hoffman Dauphin County Commissioner Sheldon J. Wolfe, Esq., Chairman Dauphin County Courthouse Atomic Safety and Licensing Board Front and Market Streets U.S. Nuclear Regulatory Comission Harrisburg, Pennsylvania 17101 Washington, D.C. 20555 Dauphin County Office of Emergency Mr. Gustave A. Linenberger, Jr. Preparedness Atomic Safety and Licensing Board Court House, Room 7 U.S. Nuclear Regulatory Comission Front and Market Streets Washington, D.C. 20555 Harrisburg, Pennsylvania 17101 Dr. James Lamb, III Mr. David D. Maxwell, Chairman Administrative Judge Board of Supervisors 313 Woodhaven Road Londonderry Township Chapel Hill, North Carolina 17514 FRD#1 - Geyers Church Road Middletown, Pennsylvania 17057 Mr. David Hetrick Administrative Judge Mr. Thomas M. Gerusky, Director Professor of Nuclear Energy Bureau of Radiation Protection University of Arizona Pennsylvania Department of Tucson, Arizona 85721 Environmental Resources P. O. Box 2063 Harrisburg, Pennsylvania 17120

GPU Nuclear Corporation Three Mile Island, Unit I cC*

Thomas Y. Au, Esq. Sen. Allen R. Carter, Chairman Office of Chief Counsel Joint Legislative Cortnittee on Energy Department of Environmental Resources P. O. Box 142 505 Executive House Suite 513 P. O. Box 2357 Senate Gressette Building Harrisburg, Pennsylvania 17120 Columbia, South Carolina 29202 Mr. Bob Stein, Director of Research Ms. Frieda Berryhill, Chairman Committee on Energy Coalition for Nuclear Power Plant P. O. Box 11867 Postponement 104 Blatt Building 2610 Grendon Drive Columbia, South Carolina 29211 Wilmington, Delaware 19808

'Ms. Jane Lee William S. Jordan, III, Esq.

183 Valley Road Harmon, Weiss & Jordan Etters, Pennsylvania 17319 20001 S Street, N.W.

Suite 420 Ms. Marjorie M. Aamodt Washington, D.C. 20009 Mr. Norman Aamodt 200 North Church Street Lynne Bernabei Esq.

Parkesburg,' Pennsylvania 19365 Government Accountability Project 1555 Connecticut Ave., N.W.

Ms. Louise Bradford Washington, D.C. 20009 TMIA 1011 Green Street Michael W. Maupin, Esq.

Harrisburg, Pennsylvania 17102 Hunton A Williams 707 East Main Street Mr. Marvin I. Lewis P. O. Box 1535 6504 Bradford Terrace Richmond Virginia 23212 Philadelphia, Pennsylvania 19149 Jordan D. Cunningham, Esq.

Mr. Chauncey Kepford Fox, Farr and Cunningham Ms. Judith H. Johnsrud 2320 North 2nd Street Environmental Coalition on Nuclear Power Harrisburg, Pennsylvania 17110 433 Orlando Avenue State College, Pennsylvania 16801 Ms. Ellyn R. Weiss

, Hannon, Weiss & Jordan Mr. Bruce Molholt 2001 S Street, N.W.

Haverford College Suite 430 Haverford, Pennsylvania 19041 Washington, D.C. 20009 Mr. Donald E. Hossler Michael McBride, Esq.

501 Vine Street LeBoeuf, Lamb, Leiby & McRae Middletown, Pennsylvania 17057 Suite 1100 1333 New Hampshire Avenue, N.W.

Mr. Ad Crable Washington, D.C. 20036 Lancaster New Era 8 West King Street Lancaster, Pennsylvania 17602

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GPU Nuclear Corporation Three Mile Island, Unit I cc:

Atomic Safety & Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Atomic . Safety & Licensing Appeal Board Panel (8)

U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Docketing and Service Section Office of the Secretary U.S. Nuclear Regulatory Commission Washington, D.C. 20555 l

AUDIT PLAN FOR THE THREE MILE ISLAND UtlIT 1 SAFETY PARAMETER DISPLAY SYSTEM

, Background All holders of operating licenses issued by the Nuclear Regulatory Commission (licensees) and applicants for an operating license (0L) 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 flVREG-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 symptoms 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).

NRC Audit Team The NRC Audit Team will consist of a representative from the Human Factors Engineering Branch assisted by personnel from Science Applications International Corporation (SAIC).

Licensees Preparations Data, infonnation, and documents on the design, development and test of the SPDS should be available for the NRC Audit Team's use and review. Also, personnel knowledgeable in the design, development, and test of the SPDS should be available to answer questions from the NRC Audit Team.

Audit Tasks The audit is composed of six tasks that are defined as:

I. Entry Briefing, II. SPDS Design Process and Human Factors Engineering, III. Design Verification and Validation, IV. Data validation, 4

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l- V. Unreviewed Safety Question, VI. Exit Briefing.

Details on each of these tasks are provided next.

I. ENTRY BRIEFING

1. The NRC Audit Team will conduct an entry briefing to discuss schedule and the audit plan.

2. The licensee is to define the scope of the SPDS within the computer system in which it is implemented.

Define location of SPDS formats /pages which contain data on each of the Critical Safety Functions.

II. SPDS DESIGN PROCESS AND HUMAN FACTORS ENGINEERING

1. SPDS System's Specifications:

Evaluate Human Factors Standards and Guidelines specified for designer's use in development of display system; Evaluate design basis of display system; Evaluate specifications for performance requirements:

display devices, response time to user's requests, user-display interface devices.

- updating of data,

- use of color,

- information density,

- display hierarchy and access to data, labels and units for data sets.

2. Detailed Design Specification:

Evaluate process used to decompose display system specifications to design details:

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display devices, response time to user's request, user-display interface devices, use of color.

information density.

display hierarchy and access to data.

labels and units for data sets.

3. Computer Code and Data Base:

audit computer code and data base for conformance to design specifications.

4. Display Formats:

Evaluate use of labels and units, Evaluate use of color, Evaluate information density / clutter, Evaluate access to all data needed to evaluate each Critical Safety Function, ,

Evaluate update of data.

5. Display Devices and Display System Interfaces:

Determine if the display screen flickers, Evaluate display controls.

Evaluate keyboards, keypads, and interface devices for ease of operator use.

III. DESIGN VERIFICATION AND val.IDATION

1. Verification and Validation Program:

Evaluate scope and depth of program.

Compare program to NSAC 39.

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2. Design Verification:

Evaluate results from design verification activities.

Evaluate results from unit test of computer programs, Evaluate process used to resolve ider,tified discrepancies.

3. Design Validation:

Evaluate score of test plans and test procedures, Evaluate coordination of test of display system with other control room activities and with user-in-the loop tests, Evaluate acceptance criteria used for validation tests.

Evaluate test report, Evaluate scope, type, and resolution of discrepancies identified during design validation.

IV DATA VALIDATION

1. Data Validation Method:

Evaluate nethod used to validate data.

Audit scope and depth of the data validation method as a function of the number of sensors available.

Audit the criteria used to validate data

2. Displayed Results, Data Validation:

Evaluate method used to code quality of the data for operator use, the scope of application among display formats, and the ease of perception by a user.

V UNREVIEWED SAFETY QUESTION:

Evaluate results from the licensee's assessment of the SPDS system in accordance with licensee's technical specifications to determine whether the changes involve an unreviewed safety question or change of technical specification, a

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Y VI EXIT BRIEFING

1. NRC audit team caucus to discuss results and prepare exit briefing.

2. Conduct Exit Briefing with licensee, state preliminary audit findings and solicit coments.

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