ML19309A983

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Notification of NRC 800401 Meeting W/Westinghouse Owners Group in Bethesda,Md Re Encl Guidance on Analysis of Accidents & Transients & Preparation of Emergency Procedure Guidelines
ML19309A983
Person / Time
Issue date: 03/17/1980
From: Ross D
Office of Nuclear Reactor Regulation
To: Reed C
WESTINGHOUSE OPERATING PLANTS OWNERS GROUP
References
NUDOCS 8004020453
Download: ML19309A983 (7)


Text

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UNITED STATES

{ f)g(f,g NUCLEAR REGULATORY COMMISSION wassiwarou. o. c. 20sss n<g g/

p* *e MAR 17 GB0 Mr. Cordell Reed, Chairman Westinghouse Owners' Group Commonwealth Edison Company P. O. Box 767 Chicago, Illinois 60690

Dear Mr. Reed:

SUBJECT:

DISCUSSION OF ANALYSIS OF ACCIDENTS AND TRANSIENTS AND PREPARATION OF EMERGENCY PROCEDURE GUIDELINES We have developed additional guidance concerning the analysis of accidents and transients and the preparation of emergency procedure guidelines required by Darrell G. Eisenhut's letter dated September 13, 1979 to all licensees of operating nuclear power plants. A copy of that guidance is enclosed.

We plan to discuss the enclosed guidance with each of the operating plant owners groups.at separate meetings in Bethesda, and would like to meet with your group at a mutually convenient time. We have been advised by Mr. Dave Waters of your group that April 1,1980 would be an acceptable date for such a meeting. Consequently, we have arranged for a meeting in Bethesda, Maryland 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.

Sincerely, O

D. F. Ross, Jr., Acting Director l

Division of Project Management

Enclosure:

Guidance.for the Evaluation and Develcpment of Procedures for Transients and Accidents i

800.402.0453

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ENCLOSURE.

GUIDANCE FOR THE EVALUATION AND DEVELOPMENT OF PROCEDURES FOR TRANSIENTS AND ACCIDENTS 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), output 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.

i The types of failures to be considered are operator errors of omission and comission, 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 l

number of sequence branches considered must be clearly defined and the basis for omitt1nt 5 ranches must be documented to avoid redundant effort. The methodology used to develop the sequence of event diagrams should be described.

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Analyses should be performed to provide a basis for the symptoras and time available for operator actions, and observations.

In particular, analyses should be provided for those branches of the sequence diagram where the consequences cannot be judged' intuitively 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 I't is recognized r. hat 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 applicability 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.

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-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 rot,e? For a.

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

3-b.

Priorities What is the hierarch'y for the operator perfoming certain functions following a reactor scram, such as reactivity control, level control, etc.? Does the operator accomplish each function before proceeding to the next?

c.

Diagnosis What are the plant parameters that the operator monitors to diagnose the plant stability? Provide a time frame' for monitoring those parameters; for example, primary pressure and level may be monitored continuously while radiation monitors would not be scanned until 15 minutes after a reactor scram, d.

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 1

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 discussion of the use of various material generated in this study for i

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 accomplishing the various phases of this study should be submitted to the staff.

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1.2STEGHOUSE OWt:ERS GR0VP PRifiCIPAL CO:: TACT LIST

'r. Alan R. 6ct n Mr. George T. Berry, Executiva Director

-Scnicr Vicc-Fresidant Power Authority of the State of New York Alabama FO:ar Company 10 Columbus Circle P. O. Cox 2041 tiew York, N. Y.10019 Mr. J. A. 'ones MR. F. P. Librizzi, General Manager Senior Vice-President Electric Production, Production Dept.

Carolina Pc.:er & Light Company Public Service Electric & Gas Company 336 Fayetteville Street 80 Park Place, Room 7221 Ralcish, ::crth Carolina 27602

'tiewark, N. J.

07101

."r. Cordell Reed Mr. W. L. Proffitt

. ssistant Vice President Senior Vice-President - Power

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Corce.;onwealth Edison Company Virginia Electric & Poi.er Co.

aP. O. Box 767 P. O. Box 26666 Chicago Illinois 60690 Richmond, Virginia 23261 Mr. S 1 Burstein, Executive Vice-President Mr. William J. Cahill, Jr.

Wisconsin Electric Power Company 7fce-President 231 West Michigan Street Consolidated Edison Company Milwauker, Wisconsin 53201 of t:ew Ycek, Inc.

  • !cw York, t;. Y.10003 Mr. Eugene R. Mathews, Vice-President "r. C. N. Cdnn, Vice-President Power Supply &, Engineering Wisconsin Public Service Corporation

perations Division G

consin 54305 h

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?ittsburgh, PA.

15219 Mr. Robert H. Groce, Licensing Engineer Yankee Atomic Electric Company Jr. Rcbert E. L'hrig. Vice-Presidsnt 20 n k d

.jdvancedSystecsandTechnology clorida Po::ar & Light Co.

. Ia li, Mr. W. G. Counsil, Vice-President or 152 fluclear Engineering & Operations Connecticut Yankee Atomic Power Co.

"r. Jchn Dolin, Vice-Presidcnt

'ndiana and "ichigan Electric Cc piny Har o necticut 06101

.ndiana and Michigan Power Co. piny h.c;.11tngGreenStation Mr. Leon D. White, Jr., Vice-President Electric & Steam Production

,a.1 York,..ew York 10004 Rochester Gas & Electric Corporation 89 East Avenue R chester, N. Y. 14649 Mr. L. O. l*2ysr, Manager

'7clearSupportServices Mr. James H. Drake, Vice-President boo Southern California Edison Company N4l 1e. 31 t

2244 Walnut Grove Avenue-P.0. Sox 800

fr.r.easpolis, "irnesota 55401 Rosemead, Calirornia 91770 Mr. Charles C:cdwin, Jr.

i 3ssistant Vice-President l

. ortland Ger.eral Electric Cocpany 121 S.W. Sal.:n Street

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W yL J brtland, Gregon 97204 ee 4,-

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. Husain Alabama Power Company inkee Atomic Electric Company 600 North 18th Str:et

.; Turnpike Rond P. O. Box 2641 estboro, Massachusetts 01581 Birmingham, Alabama 35291

ik W. Wells George Liebler

.ortheast Utilities Florida Power & Light Co.

..' Box 270 P. O. Box 529100

-artford, Connecticut 06101 Miami, Florida 33152

obert.W. Jurgensen
nerican Electric Power Service Corp, Mark Marchi 2 Broad.way Wisconsin Public Service Corp.

Ncw York, New-York 10004 P. O. Box 1200 Green Bay, Wisconsin 54305

<;. Ji Cahill

ensolidated Edison F. Pat Tierney, Jr.
  • Irving Place Northern States Power Co.

New. York,.N. Y.

10003 Route 2 Welch, Minnesota 55089

? ster W. Lyon Power Authority of the State of New York Roger Newton Wisconsin Electric Power Co.

10 Colub. bus Circle "ew York, New York 10019 231 West Michigan Milwaukee, Wisconsin 53201 1

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John A. Ahladas Cordell Reed Viroinia Electric & Power Company Comonwealth Edison Co.

One' James. River Plaza P. O. Box 767

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P. 0.. Box 26666 One First National Plaza Richmond, Virginia 23261 Chicago, Illinois 60690 Frank P. Librizzi Pb S vice Electric & Gas Co.

0r nd G n ra Electric Company 121 West Salmon Street flewark, New Jersey 07101 Portland, Oregon 97204 SJerry G. Haynes Southern California Edison Co.

roi n wer & Light 2244 Walnut Grove Avenue l

P. O. Box 1551 Rosemead, California 91770 Raleigh, North Carolina 27602 l

Jim Gormly 1

J. J. Carey Pacific Gas & Electric Co.

Duquesne Light 77 Beale Street P. O. Box 1551 San Francisco, California 94106 Shippingport, PA.

15077 Robert Mecredy Bill Layman l

Rochester Gas & Electric Electric Power Research Institute, 3412 Hillview Avenue 39 East Avenue Rochester, H. Y.

14649 Palo Alto, California 94303,

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usungn: usa uwners broup xepresentatives

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B:b Szalay Atomic Industrial Forum 7101 Wisconsin Avenue Bethesda, Md. 20014 Thomas D. Keenan Vermont Yankee Nuclear Power Corp.

77 Grove Street Rutland, Vermont 05701 9

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