ML19312D336

Notification of 800403 Meeting W/Ce in Bethesda,Md to Discuss Encl Guidance for Evaluation & Development of Procedures for Transients & Accidents

ML19312D336
Person / Time
Issue date:	03/12/1980
From:	Ross D Office of Nuclear Reactor Regulation
To:	Liebler G ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
References
NUDOCS 8003240239
Download: ML19312D336 (7)

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WASHINGTON, D. C. 20S55 P*....#

MAR 12150

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6 Mr. George Liebler, Chaiman CE Designed Plant Owners' Group on Post TMI Efforts

-P. O. Box 529100

' Miami, Florida 33152

SUBJECT:

DISCUSSION OF ANALYSIS OF ACCIDENTS AND TRANSIENTS AND PREPARATION OF EhdRGENCY PROCEDURE GUIDELINES Your letter of February 27, 1980 to Mr. Harold Denton on this subject referred to a meeting held with members of the Bulletins & Orders Task Force on January 31, 1980, to discuss the planned contents of the CE Owners' Group submittal. Since that meeting, we have developed addi-tional guidance regarding our review effort on this matter. This guidance is enclosed.

We plan to discuss the enclosed guidance with each of the plant owner's groups at separate meetings in Bethesda, and would like to meet with your group at a mutually convenient time. You indicated to my staff that April 3, 1980 would probably be acceptable, and we have arranged for a meeting in Bethesda on that date, to be held in Room 114, Phillips Building, at 1:00 P.M.

Please let me know if these plans are suitable.

i Sincerely, 0..F. Ross, Jr., Acting Director Division of Project Management

Enclosure:

Guidance.for the Evaluation and Development of Procedures for. Transients and Accidents l

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ENCLOSURE GUIDANCE FOR THE EVALUATION AND DEVELOPMENT OF PROCEDURES FOR TRANSIENTS AND ACCIDENTS I NUREG-0578,- Section 2.1.9 position requires that procedures and operator training be developed for transients and accidents. The initiating events to be considered should include the events presented in the FSAR, loss of

~ instrumentation buses, and natural phenomena such as earthquakes, floods, and tornadoes.

For each event analyzed, control function diagrams and a sequence of event diagram should be provided. The control function diagrams identify the input functions (including power sources for the sensors and limitations on operating conditions), putput functions such as valves / pumps controlled, and auxiliary systems needed-(pneumatic, hyraulic, cooling) for each of the rele-vant control systems that could have an impact on the events whether or not the control system is safety-grade. The control function diagrams provide an effective means for evaluating the completeness of the sequence of event diagram and potential common mode failures. The control function diagrams should be applicable to~all scenarios.

The sequence of event diagrams should identify major functional requirements and how' they are accomplished and/or perturbed. The major functional require-ments include reactivity control, pressure and level control in the primary and secondary systems, electric power source, containment isolation, and so forth. The sequence of event diagram should contain single and multiple failures :(up to 3) in both normal control systems and mitigating systems.

The types of failures to be considered are operator errors of omission and commission, total system failure if you don't have diversity, consequential failures,; loss of offsite power, failure of instruments and instrument buses which could mislead the operator. It is recognized that consideration of all these-failures is an enormous effort, therefore, assumptions used to limit the

. number of sequence branches considered must be clearly defined and the basis for omitting branches must be documented to avoid redundant effort. The

- methodology used to develop the sequence of event diagrams should be described.

2-Analyses should be performea to provide a basis for the symptoms and time

-available fer Uperator actio'ns, and observations.

In particular, analyses should be provided for those branches of the sequence diagram where the consequences cannot be judged intuiti/ely or timing of the operator action may be important. The basis for the limited analyses associated with each event should be provided consistent with the above requirements.

A general description of the computer codes used for all of the analyses should be provided and code limitations and calculational uncertainties discussed. Reference to more detailed descriptions and verification data-should be provided.-

Selected analyses will be audited by the staff. We will require initial

. conditions and other input data sufficient to perform audit calculations for the following selected analyses:

(a) steam line break

.(b) steam generator tube rupture (c) loss of normal feedwater flow It is recognized that the analyses will be presented for a specific plant and that other plants may have different response characteristics because of variations in control systems. Therefore, the process of assessing the acplicability of those results to specific plants should be discussed to assure that the operator training and procedures that use these results will not be misleading.

l-The purpose of this effort is to develop guidelines for operator action

- following a reactor scram because of an operational occurrence or an accident.

A prerequisite for this activity is an understanding of the operator's disposi-l

-tion with regard to the guidelines and their use. To this end, the following information should be provided:

What is the operator supposed to know by rote? For a.

Knowledge example, does he know how to actuate ECCS or must control components be identified in the procedures? What pre-cautions does he carry around in his head?

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' Priorities' -' Wh'at'is the hierarchy for the operator performing certain functions following a reactor scram, such as reactivity control, level control, etc.? Does the operator-accomplish i-each function before proceeding to the.next?

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Diagnosis-

. What are the plant parameters that the operator monitors to diagnose the plant stabilit,y? Provide a time frame

- for monitoring-those parametars; for example, primary 1

~ pressure and. level may be monitored continuously while radiation monitors would not be scanned until 15 minutas after a reactor scram.

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Team Plan

~ Describe how the guidelines are being-tailored to utilize

. 2 or 3 operators in the control room.

The general philosophy of the guidelines'should be discussed so that their application is understood..The discussion should include the basis for the

- procedures such as event oriented, symptom oriented, or function oriented,

-and a clear description of the diagnostic process that will lead the operator into the correct procedure:(or a conservative procedure). The purpose of caution statements and the time during which they are applicable should be discussed.. The use of multiple procedures and the basis for departing from a procedure should also be discussed.

~A flow chart should be presented with each. guideline to show the various

--branches and a successful completion of each branch.

A d' iscussion of the use of various material' generated in this study for

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operator training should be provided,. identifying plant-specific issues which must be resolved. A program for incorporating the results on a simulator. for-hands-on experience should also be provided.

A schedule for. accompl.ishing the various phases. of this study should be submitted to the staff.

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'Co;bustion Engin0ering Designed Operating Plants'0wners' Group Principle-Contacts List.

i r. David Bixel -

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- Nuclear Licensing Admiistrator Consumers Power Co'mpany 212 West Michigan Avenue.

' Jackson, Michigan -49201 o

Mr. William Cavanaugh, III Executive Director of Generation and Construction

, Arkansas Power & Light Company P. 0.* Box ~551 Little' Rock, Arkansas 72203 Mr.l A. E. Lundvall, Jr.

Vice-P~ resident - Supply

- Baltimire Gas & Electric Company P.. Box 1475~

Baltimore, Maryland 21203 Mr. Theodore E. Short Assistant General Manager Omaha Public Power District 1623 Harney Street -

Omaha', Nebraska 68102 Mr. Robert H. Groce Licensing Engineer Yankee-Atomic Electric Company 20 Turnpike Road Westboro, Massachusetts 01581

- Mr. W. G. Counsil, Vice-President Nuclear Engineering & Operations Northeast Nuclear Energy Company:

- P. O. Box 270

-Hart ord, Connect cut - 06101 f

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- Dr. Robert E. Uhrig, Vice-President-

- Advanced Systems.& Technology Florida Power & Light Company P. O. Box 529100 Miami, Florida 33152 l

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.1 List' for Combustien Engineering-dtsigned Op; rating Plants Gn:rs'. Group Contacts F. Wesley Hartley, Manager Mr. Robert T. Harris, Chairman Palo Verde Nuclear Generating Station Analysis Subgroup Arizona Public Service Company Northeast Utilities Service Company P. O. Box 49.

P. O. Box 270 Palo Verde, Arizona 85343 Hartford, Connecticut 06101 David C. Trimble, Manager Mr. John Garrity, Chairman Licensing

~

. Guidelines Subgroup

. Arkansas Peer & Light Company Maine Yankee Atomic Power Company Box 551

. 72203 Augusta, Maine 04336 Edison Drive Little Rock, Arkansas John Gore..

Roy W. Prados, Engineer Louisiana Power & Light Baltimore Gas & Electric Company 142 Delaronde Street P. O. Box 1475 New Orleans, Louisiana 70174 Baltimore, Maryland 21203 Rik Wells Northeast Utilities Service Company David A. Bryant P. O. Box 270 Nuclear Projects Department Hartford, Connecticut 06101 Boston Edison Company 800 Boylstone Street-Boston, Mass. 02199 Kenneth J. Morris Omaha Public Power District 1623 Harney Street Fred Buckman Omaha, Nebraska 68102 Consumers Power Company

-1945 W. Parnall Road Kenneth P. Baskin, Manager

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Jackson, Michigan 49201 Generation Engineering

-Southern California Edison Company P. O. Box 800 Warren H. Owen 2244 Walnut Grove Avenue Senior Vice-President Rosemead, California 91770 Engineering & Construction Duke Power Company Dwight R. Patterson, Chief rote,NorthC$rolina 28242 Mechanical Engineering Branch Division of Engineering Design Tennessee Valley Authority W10Cl26 George E. Liebler, Manager Power Resources Nuclear Services 400 Connerce Avenue 4

Florida Power & Light Company Knoxville, Tennessee 37902 P. O. Box 529100

' Miami, Florida.33152 e(a s

ey Authority Mr. Joseph-K. Gasper, Vice Chairman 400 Chestnut Street - Tower II Combustion Engineering Owners' Group Chattanooga, Tennessee -37401

-Omaha Public Power District Fourth & Jones Robert A. DeLorenzo, Chief Engineer Omaha, Nebraska 68108 Washington Public Power Su0 ply System 3000 George. Washington Way j

-Richland, Washington 99352 L

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Pg 2 - C-E-disigned Op: rating ~ Plants Own;rs' Group Contacts Robert P. Shone (Systems Engineering Manager

. Yankee Atomic Electric Company 20 Turnpike Road (Rte. 19) 1581 0

Westboro, Massachusetts

'Non-Participant, Information Only:

'M. J. Ray.

New York State Electric & Gas Canpany.

9500 Vestal Parkway Binghampton, New York )3902 Canbustion Engineering Representative:

Paul DeLozier C-E~ Power Systems Combustion Engineering.Inc.

1000 Prospect Hill Road Windsor, Connecticut 06095 William Lava 11ee NSAC P. O. Box 10412 Palo' Alto, California 94303-L a

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