anticipated abnormal plant...

ANTICIPATED AND ABNORMAL PLANT TRANSIENTS IN LIGHT WATER REACTORS Volume 1

ANTICIPATED AND ABNORMAL PLANT TRANSIENTS IN LIGHT WATER REACTORS Volume 1

Edited by

Pamela L. Lassahn Science Applications, Inc. Idaho Falls, Idaho

Debu Majumdar Department of Energy Idaho Falls, Idaho

and George F. Brockett Intermountain Technologies, Inc. Idaho Falls, Idaho

SPRINGER SCIENCE+BUSINESS MEDIA, LLC

Library of Congress Cataloging in Publication Data

American Nuclear Society Topical Meeting on Anticipated and Abnormal Plant Transients in Light Water Reactors (1983: Jackson, Wyo.) Anticipated and abnormal plant transients in light water reactors.

"Proceedings of an American Nuclear Society Topical Meeting on Anticipated and Abnormal Plant Transients in Light Water Reactors, held September 26-29, 1983, in Jackson, Wyoming"-T.p. verso.

Includes bibliographical references and index. 1. Atomic power-plants-Safety measures-Congresses. 2. Transients

(Dynamics)-Congresses. I. Lassahn, Pamela L. II. Majumdar, D. (Debu). Ill. Brockett, George F. IV. American Nuclear Society. V. Title. TK9152.A56 1983 621.48'35 84-13262

ISBN 978-1-4684-4801-6 ISBN 978-1-4684-4799-6 (eBook) DOI 10.1007/978-1-4684-4 799-6

Proceedings of an American Nuclear Society Topical Meeting on Anticipated and Abnormal Plant Transients in Light Water Reactors, held September 26-29, 1983, in Jackson, Wyoming

© Springer Science+Business Media New York 1984 Originally published by Plenum Press, New York in 1984 Softcover reprint of the hardcover 1st edition 1984

All rights reserved

No part of this book may be reproduced, stored in a retrieval system, or transmitted in any form or by any means, electronic, mechanical, photocopying, microfilming, recording, or otherwise, without written permission from the Publisher

To the nuclear power plant operators, who carry an important responsibility but

who often do not receive recognition for the magnitude of their burden.

This book is dedicated to the memory of George F. Brockett, who died March 17, 1984. He spent innumerable hours

compiling the program that resulted in these comprehensive proceedings on plant transients. George dedicated his life to technical excellence. He stood for what was right, not

what was popular. George believed in nuclear power, and the industry has lost a powerful advocate.

We will all miss him.

PREFACE

Over the last 30 years, reactor safety technology has evolved not so much from a need to recover from accidents or incidents, but primarily from many groups in the nuclear community asking hypothetical, searching (what if) ~uestions. This ~uestioning has indeed paid off in establishing preventive measures for many types of events and potential accidents. Conditions, such as reactivity excursions, large break, loss of coolant, core melt, and containment integrity loss, to name a few, were all at one time topics of protracted discussions on hypothesized events. Historically, many of these have become multiyear, large-scale research programs aimed at resolving the "what ifs."

For the topic of anticipated and abnormal plant transients, however, the searching ~uestions and the research were not so prolific until the mid-1970s. At that time, probabilistic risk methodologies began to tell us we should change our emphasis in reactor safety research and development and focus more on small pipe breaks and plant transients. Three Mile Island punctuated that message in 1979.

The plant transient topic area is a multidisciplinary subject involving not only the nuclear, fluid flow, and heat transfer technologies, but also the synergistics of these with the reactor control systems, the safety s;,"stems, operator actions, maintenance and even management and the economic considerations of a given plant. This need to integrate these several disciplines formed the basis for the special American Nuclear Society (ANS) topical conference held in Jackson, Wyoming, September 26-29, 1983 -- one that seemed long overdue. Appropriately, the organizing committee felt compelled to ma-.ke this first topical meeting cover as much as possible to provide a comprehensive treatment of plant transients.

This goal led to sessions on the ~xperience base, anatomy of significant events, deterministic and probabilistic methods and their applications, man-machine interface, and plant transient mangement. The hope was that an integration of these disciplines would teach the nuclear industry how to better prevent and cope with plant transients.

ix

One of the goals of this conference was to achieve high participation by people from the nuclear industry, particularly, the utilities. For this conference, the utilities and their research arms, the Electric Power Research Institute and the Institute of Nuclear Power Operations, made up nearly one-third of the program committee, one-third of the authors, and one-third of the session chairmen.

This is significant because ultimately the utility and its operators must cope with the problem of preventing and mitigating transients at a nuclear power plant. Also, the other segments of the nuclear community needed to hear their side of the story. Similarly, the participation of nuclear workers from foreign countries was important because many aspects of plant design for operation are treated differently abroad, and their record of transients is a~so different from that in the United States. Here, again, the response to stimulated and invited papers was rewarding.

Another goal of this conference was to compile as complete a reference document on this subject as possible. Therefore, considerable effort was expended to complile material beyond the invited and contributed papers. Several appendixes provide extensive information on computer codes, nuclear test facilities, and actual plant transients. In addition, each chapter is briefly introduced, and the question and answer discussions that followed the paper presentations are included with each chapter. These lively discussions candidly expound on the nuclear industry's current situation.

Three reviews of the conference have appeared in the literature: "Conferees in Jackson Hear Management Called Key to Accident Control" (Inside NRC, vol 5, pp 10-14, October 1983), "Anticipated and Abnormal Transients in LWRs" (Nuclear News, vol 26, pp 106-110, December 1983), and "Learning from Anticipated and Abnormal Plant Transients" (Nuclear Engineering International, vol 28, pp 25-28, December 1983). These articles provide other valuable perspectives on plant transients as seen through this conference.

Perhaps the most significant result of the conference was the recognition that the nuclear industry now has an evolving, worldwide, and reasonably well disseminated data base on plant transient experience. If "history is the best teacher," then we must heed this experience by improving analysis, design, procedure development, training, and management. This will not only improve the record of preventing and mitigating transients, but also improve plant availability -- a tangible benefit to all -- and add to the promise that nuclear power will be available to meet our future energy needs.

X

ACKNOWLEDGMENTS

This conference was possible because of the spontaneous support received from many people here and abroad. It is impossible to acknowledge them all in a small space, but some names stand out. First, many thanks to the Department of Energy, and particularly to Robert E. Tiller for his encouragement. Special appreciation is extended to Philip A. Anderson, the Idaho Section ANS Past-chairman, George Coulbourn and R. Jon Stouky of the National Program committee for their support and to the organizing committee members for their dedication and countless hours of work.

Recognition should be made of the financial help received from the Department of Energy and the Nuclear Regulatory Commission which enabled the committee to considerably reduce the registration fees. All the co-sponsoring organizations contributed key individuals who helped shape this meeting, and many members of the co-sponsoring ANS groups helped obtain the necessary approvals. Particularly, thanks are due to Joe Murphy, Fred Tory, and Roger Tilbrook (NRSD), Don Rowe and Chong Chiu (Thermal Hydraulics), Tony Kitz (ROD), Don Farr (Human Factors), and Dietrich Bunemann and w. Frisch (ENS). Several Idaho Falls organizations provided valuable support: Intermountain Technologies, Inc.; Energy Incorporated; EG&G Idaho, Inc.; Science Applications, Inc.; and Argonne National Laboratory.

Special thanks are due to Robert Breen (EPRI/NSAC), Roger Wyrick (INPO) and Ron Colombo (SMUD) for their valuable help in providing many missing links for the program. Several people have contributed to the preparation and review of the appendices. The following names, in addition to some technical program committee members, should be recognized: J. R. Buchanan (ORNL), R. B. Duffey and M. Divakaruni (EPRI), B. Fourest (CEA/France), F. Odar (NRC), G.E. Wilson, D. M. Ogden and V. N. Shah (EG&G Idaho), D. Slaughterbeck (ITI), and F. Winkler (KWU, W. Germany).

Special appreciation goes to the banquet speaker Joseph M. Hendrie, whoinspite of a bursitis attack, gave a delightful talk. Names of many people who have made this conference successful are listed below. They all deserve sincere thanks. Particularly the scientific secretaries and Helmut A. Worle as their coordinator did a marvelous job. Without their efforts there would have been no discussions recorded in the proceedings.

Three people have borne with us through the ordeal of typing and assembling the final proceedings. They are Patricia A. Hammond (EG&G, Idaho), Pat Dustin (SAI), and Helen Brown (IT!). Our sincere thanks go to them. Most of all, heartfelt thanks go to Pam Lassahn, the publications chairman, for her infinite patience ~n editing and integrating the many inputs of the proceedings.

Patricia M. Vann and Neil Kraner of the Plenum Publishing Corporation are cordially thanked for their guidance and role in publishing this book.

Finally, all the spouses of the organizing committee members deserve gratitude from us for their support and tolerance.

Debu Majumdar General Chairman

MEETING OFFICIALS

General Chairman Debu Majumdar Department of Energy

Program Chairman George F. Brockett Intermountain Technologies, Inc.

Asst. General Chairmen Richard E. Ireland

Secretary

Finance

Arrangements

Publicity

Publications

xii

Nuclear Regulatory Commission

Vincent G. AQuino Argonne National Laboratory - West

Earl E. Burdick and Joseph Henscheid EG&G Idaho, Inc.

Milton F. Adam and Vincent G. AQuino Argonne National Laboratory - West

Bernie F. Saffell, Carl F. Obenchain, and Rita Scott EG&G Idaho, Inc.

Pamela L. Lassahn Science Applications, Inc.

Registration V. P. (Hary) Charyulu Idaho State University

Tours Paul E. Litteneker Department of Energy

Recording Helmut A. Worle EG&G Idaho, Inc.

Poster Session

Foreign Liaisons

Spouses' Program

Registration Desk

Dan Denver Energy Incorporated

L. H. Sullivan Nuclear Regulatory Commission

Jan B. Van Erp Argonne National Laboratory

Kenneth V. Moore Thermal Hydraulics, Inc.

James McFadden Energy Incorporated

Catherine Majumdar

Betty Brockett Helen Brown Lois Dawson Kathy Jensen Patty Moore Betty Smith Mary Wenger

CO-SPONSORS

Idaho Section of the American Nuclear Society European Nuclear Society ANS Reactor Safety Division ANS Thermal Hydraulics Division ANS Reactor Operations Division ANS Human Factors Technical Group U.S. Department of Energy U.S. Nuclear Regulatory C,ommission Electric Power Research Institute Institute of Nuclear Power Operations

xiii

xiv

P. M Abraham Mario V. Bonaca Robert Breen

William E. Burchill Thomas J. Burns R. E. Collingham Ron Collins Ron Colombo Peter R. Davis Shyam Dua Donald E. Farr W. Frisch David Hetrick Ausaf Husain James F. Jackson Gary W. Johnsen Harry V. Julian R. Karam William Kerr Anton F. Kit z Jerry Koske Melvin M. Levine John H. Linebarger Larry R. Mathews James McFadden Andrew C. Millunzi Don Rowe Brian Sheron L. Harold Sullivan Jan B. Van Erp Nancy Willoughby David H. Worledge Roger Wyrick

PROGRAM COMMITTEE

Duke Power Northeast Utilities Nuclear Safety Analysis Center, Electric

Power Research Institute Texas A&M University Oak Ridge National Laboratory Exxon Nuclear Company, Inc. Babcock and Wilcox Sacrametao Municipal Utility District Intermountain Technologies, Inc. General Electric Corporation Consultant Gesellschaft fUr Reaktorsicherheit University of Arizona Yankee Atomic Electric Company Los Alamos National Laboratory EG&G Idaho, Inc. Westinghouse Georgia Institute of Technology University of Michigan QUAD REX Public Service of New Hampshire, Seabrook Brookhaven National Laboratory EG&G Idaho, Inc. Southern Company Services, Inc. Energy Incorporated Department of Energy Rowe & Associates Nuclear Regulatory Commission Los Alamos National Laboratory Argonne National Laboratory Bechtel Power Corporation Electric Power Research Institute Institute of Nuclear Power Operations

PAPER REVIEW MEETING ATTENDEES

Ron Colombo Jerry Koske Ausa:f Husain Roger Wyrick Robert Breen

Nancy Willoughby James McFadden Peter R. Davis Kenneth V. Moore Gary W. Johnsen Milan E. Stewart Orville Meyer R. E. Collingham V. P. (Hary) Charyulu Shyam Dua Manjit Sahota

Sacrameto Muncipal Utility District Public Service of' New Hampshire, Seabrook Yankee Atomic Electric Company Institute of' Nuclear Power Operations Nuclear Sa:fety Analysis Center, Electric

Power Research Institute Bechtel Power Corporation Energy Incorporated Intermountain Technologies, Inc. Thermal Hydraulics, Inc. EG&G Idaho, Inc. EG&G Idaho, Inc. EG&G Idaho, Inc. Exxon Nuclear Company, Inc. Idaho State University General Electric Corporation Los Alamos National Laboratory

SCIENTIFIC SECRETARIES

Stephen Nicolosi Melati Charyulu John Meir Wallis Cramond Tim Howe Bryce Johnson Faut Odar Charles Solbrig Michael Modro Henry Tobey James Milton John Linebarger Gary Johnsen R. Kingsley House

Battelle-Collumbus TRW - De:fense Systems Los Alamos National Laboratory Sandia Gulf' States Utilities Co. Science Applications, Inc. Nuclear Regulatory Commission Argonne National Laboratory - West EG&G Idaho, Inc. EG&G Idaho, Inc. EG&G Idaho, Inc. EG&G Idaho, Inc. EG&G Idaho, Inc. Intermountain Technologies, Inc.

XV

xvi

SESSION CHAIRMEN

J. Griffith- Department of Energy W. Cottrell - Oak Ridge National Laboratory R. Wyrick - Institute of Nuclear Power Operations M. Horne - Babcock and Wilcox R. Columbo - Sacramento Municipal Utility District M. Plesset - California Institute of Technology K. V. Moore - Thermal Hydraulics, Inc. L. H. Sullivan - Los Alamos National Laboratory V. Ransom- Idaho National Engineering Laboratory J. Turnage - Consultant J. M. Waage - S. M. Stoller Corporation D. Denver - Energy Incorporated J. Jeffries - Carolina Power and Light W. Frisch - Gesellschaft fUr Reaktorsicherheit L. Agee - Electric Power Research Institute S. Fischer - Middle South Utilities P. Hill - Pennsylvania Power and Light A. Villemeur - Electricite de France R. Breen - Nuclear Safety Analysis Center,

Electric Power Research Institute D. McPherson - Department of Energy J. G. Moore - United Kingdom SRD S. E. Jensen - Exxon H. Thompson - Nuclear Regulatory Commission R. M. Berryman - Virginia Electric and Power Co. W. Loewenstein - Electric Power Research Institute R. E. Ireland - Nuclear Regulatory Commission G. Dix - General Electric P. Saha - Brookhaven National Laboratory R. Mattson - Nuclear Regulatory Commission B. Monty - Westinghouse J. 1'T. Hickman - Sandia D. Hoffman - Consumers Power N. Willoughby- Bechtel Power Corporation S. Dua - General Electric

SPONSORS OF CONFERENCE EVENTS AND FUNCTIONS

Energy Incorporated Exxon Nuclear Company, Inc.

EG&G Idaho, Inc. Science Applications, Inc.

CONTENTS

BANQUET ADDRESS

Transients -- Abnormal and Otherwise J. M. Hendrie

SECTION 1: SIGNIFICANCE OF OPERATIONAL TRANSIENTS

1.1 Opportunities for Practical Improvements in the Management of Plant Transients (Opening Address)

E. L. Zebroski

1.2 Operational Transients, A Definition C. F. Sears

1.3 The Risk from Transients According to Probabilistic Risk Assessment(PRA)

B. J. Garrick and V. M. Bier

1.4 The Economic Impact of Reactor Transients A. D. Rossin and G. L. Vine

1.5 Questions and Answers

SECTION 2: PLANT TRANSIENT EXPERIENCE BASE

2.1 How Does the NRC Treat Operational Experience and What Is It Telling Us?

T. A. Ippolito

2.2 What is Our Experience in Plant Transients Telling Us?

S. L. Rosen

2.3 The NEA Incident Reporting System: Description, Experience, First Results

B. Fourest~ C. Giroux~ and Y. Otsuka

1

13

15

29

35

53

57

59

69

77

xvii

2.4 PWR - Experience in Operational Transients -French Program, 1981-82 Results

R. Cape"l

2.5 Experience with Transients in German NPPs E. Lindauer

2.6 Experience in Plant Transients - The Swedish RKS Program

J. P. Bento

2.7 Taipower Experience in Plant Transients P. C. Chen


SECTION 3: ANATOMY OF SELECTED OPERATIONAL TRANSIENTS

3.1 Ginna Steam Generator Tube Rupture R. C. Mecredy

3.2 Rancho Seco Light Bulb Incident R. Co"lombo

3.3 High Pressure Cooling System Malfunction B. Keck

3.4 Control Rod Trip Failures: Salem 1, the Cause, Response, and Potential Fixes

R. E. Ha"l"l~ J. L. Boccio~ and W. J. Luckas

3.5 Loss of Preferred Power Events in German BWRs and PWRs

W. Frisch and R. Gi"l"l

3.6 Analysis and Simulation of the DOEL-2 Steam Generator Tube Rupture Event

E. J. Stubbe~ J. M. Cha"lant, H. Michie"ls~ and H. Sab"lon


87

97

107

117

125

131

133

153

163

173

183

193

SECTION 4: SPECIFIC EXPERIENCE IN OPERATIONAL TRANSIENTS 203

4.1 Vital Auxiliaries - The Underrated Events D. J. Finnicum and S. A. Webster

xviii

205

4.2 Plant Transients - Licensing Requirements and Operating Experience Concerning the Plants Isar 1 and Grafenrheinfeld

D. Brosche

4.3 Plant and Operator Response to an Extraction Steam Line Rupture - Oconee Unit 2 - June 28, 1982

E. M. Kuhr~ S. T. Rose~ and K. S. Canady

4.4 Natural Circulation Response of PWRs W. D. Lanning and R. R. WunderZick


SECTION 5: CURRENT ISSUES IN OPERATIONAL TRANSIENTS

5.1 EPRI/NSAC's Approach for Tackling Current Safety Issues

B. Layman

219

229

239

249

255

257

5.2 Pressurized Thermal Shock -An Integrated Analysis 265 B. ChexaZ~ T. Marston~ T. Griesbach~ J. Chao~ and B. Layman

5.3 Pumps On vs. Pumps Off During Recovery 281 A. Husain~ L. Schor~ and J. Ghaus

5.4 Station Blackout Transients 295 P. W. Baranowsky

5.5 ATWS - An Update from NRC 305 R. J. Mattson

5.6 Application of Digital Technology to Nuclear Plant Control and Safety 315

A. B. Long~ S. M. Divakaruni~ and R. B. Duffey

5.7 Approach to Inadequate Core Cooling Detection 329 L. E. PhiZZips

5.8 Questions and Answers 339

SECTION 6: ANALYTICAL METHODS FOR TRANSIENT SIMULATION

6.1 A Perspective on Nuclear Power Plant Systems Analysis

s. M. Divakaruni and R. B. Duffey

6.2 Simulation of Transients with DRUFAN 367 W. Pointner, F. Steinhoff, and K. WoZfert

6.3 The TRAC-PFl/MODl Computer Code 381 D. R. LiZes and J. H. Mahaffy

6.4 An Overview of the Modular Modeling System (MMS) Code and Applications 387

L. P. Smith, R. S. May, S. Levy, S. M. Divakaruni, J. P. Sursook, and G. S. DeZuba

6.5 ALMOD4: Advanced PWR Transient Analysis Code A. Sohaefer, J. E. Mir6, G. Hoeppner, W. Frisoh, R. Meissner, and U. GaaZ

401

6.6 Sensitivity of SBLOCA Analysis to Model Nodalization 411 C. Lee, T. Ito, and P. B. Abramson

6.7 Mathematical Modeling of Plant Transients in the PWR for Simulator Purposes 425

K. HarteZ


SECTION 7: ANALYTICAL METHODS ASSESSMENT BY COMPARISON TO DATA 437

7.1 PWR and BWR Anticipated and Abnormal Plant Transient Research Sponsored by the U.S. NRC 439

W. D. Beokner, F. Odar, and L. H. SuZZivan

7.2 The EPRI Plant Transient Data Bank 449 P. G. BaiZey, G. A. Cordes, and R. K. House

7.3 FIST Small Break Accident Analysis with BWR TRACB02-Pretest Predictions 459

Md. AZamgir and W. A. SutherZand

7.4 A TRAC-PFl Analysis of LOFT Steam-Generator Feedwater Transient Test L9-1 467

J. K. Meier

7.5 Best-Estimate Analyses of LOFT Anticipated Transients with and without SCRAM Using DYNODE-P 477

R. C. Kern, D. A. Rautmann, and R. 0. Anderson

XX

7.6 Use of LOBI Test Facility for Plant Transients Simulation 487

W. L. RieboZd3 A. AmendoZa3 T. R. Fortesaue3 H. Stadtke3 A. Annunziato3 and B. Lisanti

7.7 ROSA-IV/LSTF Program at JAERI for PWR Small-Break LOCA and Operational Transient Experiments 499

M. Tanaka3 K. Tasaka3 Y. Koizumi3 C. P. Fineman3 and M. Shiba


SECTION 8: PRESSURIZED WATER REACTOR PLANT TRANSIENT ANALYSIS - PART I

8.1 RETRAN Analysis of SONGS 2 Reactor Coolant System Flow

513

Measurements 515 Y. P. Ting

8.2 TRAC Analysis of the Crystal River Unit 3 Plant Transient of Februrary 26, 1980 527

P. Coddington and G. J. E. WiZZautt3 Jr.

8.3 Calculation of the Limiting CESSAR Steam Line Break Transients

G. B. PeeZer3 D. L. Caraher3 and J. Guttmann

8.4 Station Blackout Accident for the Korea Nuclear

539

Unit 1 Using RELAP5/MOD1 555 B. D. Chung3 S. Y. Lee3 and J. S. Kim

8.5 Evaluation of RELAP5/MOD1 for Analysis of Steam Generator Tube Rupture Transients in OTSG Plants 565

J. R. White3 R. T. Jensen3 V. ChexaZ3 and J. Lang

8.6 Yankee Plant NRV Closure Analysis 575 G. E. Jarka3 J. M. KendaZZ3 and N. Fujita

8.7 TRAC Calculations of Overcooling Transients in PWRs for Pressurized Thermal Shock Analysis 587

J. R. Ireland and B. E. Boyack

8.8 RELAP5 Analyses of Overcooling Transients in a PRW 603 M. A. BoZander3 C. D. FZeataher3 D. M. Ogden3 B. D. Stitt3 and M. E. Waterman


xxi

SECTION 9: PRESSURIZED WATER REACTOR PLANT TRANSIENT ANALYSIS - PART II 627

9.1 Migation of PTS Transients by System Design in KWU PWR Plants 629

F. Winkler and G. Frei

9.2 Analysis of Safety Injection Fluid Mixing in the Downcomer and Cold Leg of PWRs 639

J. Chao, B. Chexal, B. Layman, R. McGriff, and D. Lunsford

9.3 OTSG Transient Modeling with ALMOD/GDE: Overview and Case Study 655

K. Hornyik, S. T. Luo, W. Frisch, and J. P. Weber

9.4 ATWS Parameter Studies for a Tight-Lattice PWR 667 H. Amm, G. Frei, M. D. Donne, J. M. Kallfelz, and H. KUsters

9.5 Small-Break LOCA Recovery in B&W Plants 679 R. J. Henninger, J. R. Ireland, and N. S. DeMuth

9.6 Boron Injection at Natural Circulation Conditions in PWRs 691

K. R. Perkins

9.7 RETRAN-02 Analysis of Ginna Nuclear Power Plant's Steam Generator Tube Rupture Accident

W. G. Choe, Y. Matsui, Y. Yabushita, and M. Fukuchi

9.8 Thermal-Hydraulic Analysis of the Ginna Steam Generator

701

Tube Rupture Event Using RETRAN-02 711 R. K. Wyrick, E. N. Winkler, and W. W. Brown


SECTION 10: BOILING WATER REACTOR PLANT TRANSIENT ANALYSIS 725

10.1 Verification Study of Transient Analysis Code BWRDYN Using Startup Test Data of Tokai Unit 2 BWR Plant

M. Yokobayashi and Y. Takahashi

xxii

727

10.2 Application o~ the RELAP5 Code ~or Simulation o~ Three Turbine Trip Transients at the Peach Bottom Unit 2 BWR

R. K. House, G. A. Cordes, C. S. MiZZer, and P. G. BaiZey

739

10.3 Peach Bottom Transient Analysis with BWR TRACB02 755 Md. AZamgir and W. A. SutherZand

10.4 Analysis o~ Incomplete Control Rod Insertion by Three Dimensional Kinetic Code Developed ~or BWR Simulation 765

K. Kitayama, S. Tsunoyama, and S. Ebata

10.5 Balance o~ Plant Modeling in TRAC-BDl/MODl 773 W. L. Weaver, M. M. GiZes, and C. M. Mohr

10.6 Balance o~ Plant Modeling with RETRAN and MMS 781 C. R. Arndt, E. M. Page, and T. L. Tederington

10.7 Sa~ety Margin o~ BWRs Operating with High Power/ Flow Ratios 793

K. Hornyik and J. Naser


SECTION 11: MODELING METHODS AND ANALYSIS 807

11.1 BWR/4 Loss o~ Feedwater Transient Analysis 809 M. s. Lu, M. M. Levine, and W. G. Shier

11.2 An Algorithm Suitable ~or Numerical Analyses o~ Space-Time Reactor Transients Using Microprocessors 821

B. Stevenson

11.3 TRAC-PFl Posttest Predictions ~or the Semiscale Natural-Circulation Tests S-NC-2 and S-NC-6 831

C. P. Booker

11.4 Thermal-Hydraulic Analysis o~ Main Steam Line Breaks with Continuous Feedwater Addition 843

M. A. FeUus

11.5 Modeling o~ PWR Steam Generators: An Application o~ Code SICLE

P. KasteZanski 857

xxiii

ll.G LOFT Transient Analysis with Real-Time, Minicomputer- 867 Based Simulation

F. K. Hyer and J. L. JYZee

11.7 Analysis of Anticipated Plant Transients As an Aid 875 for PWR Plant Verification

T. Busi~ R. Cori~ and F. PretoZani

11.8 Evaluation of Primary Feed and Bleed Cooling Capability 885 of PWR Systems

L. C. Pwu

11.9 TRAC-PFl--Pressurized Thermal Shock Calculations for Several Small-Break Loss-of-Coolant Transients in the Oconee-1 Nuclear Power Plant

M. W. Burkett and B. Bassett

SECTION 12: PROBABILISTIC RISK ASSESSMENT OF TRANSIENT ACCIDENT RISKS

12.1 The Risk Significance of PWR Transient Accidents

895

909

from PRA Studies 911 P. R. Davis~ J. M. Broughton~ and P. E. MacDonald

12.2 Dominant Accident Sequences Derived from Review of Five PRA Studies 921

V. Joksimovich~ M. V. Frank~ and D. R. WorZedge

12.3 A Review and Analysis of Insights from Plant Transients Gained from the Interim Reliability Evaluation Program 933

G. J. KoZb and A. C~ Payne~ Jr.

12.4 Risk Impact Analysis of Abnormal Transients Using Sensitivity Analysis 943

A. K. Bhattacharyya and S. Ahmed

12.5 Some Insights Obtained During a Study of Candidate Methods for Achieving a Reduction in Core Damage Frequency 953

M. G. K. Evans and P. D. O'ReiZZy

12.6 Mitigation of BWR ATWS Risk: A Probabilistic Assessment 963

M. J. Hazzan and W. P. Hennessy


xxiv

SECTION 13: PROBABILISTIC RISK ASSESSMENT METHODS AND APPLICATIONS IN OPERATIONAL TRANSIENTS

13.1 A Method to Assess Nuclear Power Plant Risk Due to Fire-Induced Transients

J. M. Siegel and M. A. Stutzke

13.2 Use of RETRAN for Determination of some BWR Success Criteria

E. V. Moore3 J. C. Wells3 S. F. Deng3 G. R. Sawtelle3 D. C. Rees3 and B. B. Chu

13.3 The Inclusion of External Initiating Events in the Limerick Generating Station PRA

G. Daebeler and G. W. Parry

13.4 Sequence Risk Analysis: A Method for the Evaluation of Event Significance Based on Potential Core Damage Frequency

G. B. Fader3 E. L. Zebroski3 and M. A.

13.5 Operator-Action Trees, A Method for Modeling Cognitive Errors in Risk Analysis

J. WreathaU


SECTION 14: TRANSIENT MANAGEMENT STRATEGIES

14.1 Elements of Effective Control Room Response to Emergencies

C. D. Wilkinson

Jones

14.2 Transient Management Using the Safety Function Approach

W. R. Corcoran3 V. M. Callaghan3 G. C. Bischoff3 R. T. Pearce3 and J. M. Barrow

14.3 BWR Emergency Procedure Guidelines J. S. Post3 E. F. Karner3 and R. A. Stratman

14.4 Guidance for Control Room Emergency Operations R. C. Surman3 B. S. Monty3 M. E. Stella3 H. V. Julian3 and R. A. Newton

14.5 Emergency Operating Procedures Guidelines for PWRsA Progress Report

W. C. Lyon and D. Langford

995

1005

1017

1029

1041

1047

1049

1059

1073

1083

1099

XXV

ll+. 6 Advanced Process Management Aids for Nuclear Plant Operation

D. G. Cain


SECTION 15: TRANSIENT MANAGEMENT IMPLEMENTATION

15.1 A Functional Approach to Transient Management A. C. Kadak and J. D. Candon

15.2 On-Line Prediction of BWR Transients in Support of

1109

1121

1125

1127

Plant Operation and Safety Analysis 1141 W. Wulff~ H. S. Cheng~ S. V. Lekaoh~ and A. N. Mallen

15.3 Classroom Training of Nuclear Power Plant Personnel for Transients 1157

W. Marquino

15.4 Operator Actions Following Abnormal Transients: Tests on Simulators 1169

M. Legaud~ A. Villemeur~ and A. Oliot

15.5 Abnormal Transient Operating Procedures 1177 D. H. Williams

I 15.6 Advances in Modeling Techniques for Plant Simulators 1187 S. Fabio and P. S. Andersen


SECTION 16: HUMAN FACTORS CONSIDERATIONS IN OPERATIONAL TRANSIENTS

16.1 Issues in the Relationship of Human Reliability

1205

Analysis to Probabilistic Risk Assessment 1207 B. J. Bell

16.2 Analysis of Operator Response to Anticipated Transients and Multiple Failure Accident Sequences 1215

A. S. McClymont and J. L. vonHerrmann

16.3 Systematic Approach to Integration of a Human Reliability Analysis into a NPP PRA 1221

J. R. Fragola

xxvi

16.4 Task Analysis: How Far Are We from Usable PRA Input?

D. I. Gertman3 M. F. Hinton 3 and H. S. BZackman

16.5 Safety Parameter Display Systems Effect on Operator Performance

F. Cerven3 R. E. Ford3 and H. S. BZackman

16.6 Issues in Cognitive Reliability D. D. Woods 3 J. A. Rumancik3 and M. J. HitchZer


1235

1243

1253

1263

SECTION 17: WHERE FROM HERE WITH OPERATIONAL TRANSIENTS? 1269

17.1 Successful Plant Operations: An Engineering Function 1273 W. J. Ford

17.2 Where from Here with Operational Transients: A Designer's Point of View

W. R. Corcoran and R. T. Pearce

17.3 Nuclear Plant Transients: Utility Viewpoint R. A. Newton

1281

1289

17.4 Transients: The Regulator's View 1293 B. W. Sheron and T. P. Speis

17.5 Operational Transients -A Regional Administrator's View 1303

J. T. CoZZins and E. H. Johnson


SECTION 18: WHERE ARE WE WITH OPERATIONAL TRANSIENTS?

18.1 Summary of Operational Transients/Current Issues, and Specific Experience

N. B. WiZZoughby

18.2 Summary of Plant Transient Experience Base and Anatomy of Selected Operational Transients

W. R. Corcoran

1309

1321

1323

1329

)(X Vii

18.3 Summary of Analytical Methods for Transient Simulation, Analytical Methods Assessment by Comparison to Data, Modeling Methods and Analysis, and PWR Transient Analysis 1332

S. Fabia

18.4 Summary of Transient Analysis 1339 P. Saha

18.5 Summary of PRA Assessment of Transient Accident Risks, Human Factors Considerations, and PRA Methods and Applications 1343

A. Camino

18.6 Summary of Transient Management 1347 B. W. Sheron


APPENDIX A: FREQUENTLY DISCUSSED NUCLEAR POWER PLANT TRANSIENTS

APPENDIX B: MAJOR EXPERIMENTAL FACILITIES IN THE WORLD

APPENDIX C: GLOSSARY OF COMPUTER CODES USED IN PLANT TRANSIENTS ANALYSIS

APPENDIX D: INTERNATIONAL AND U. S. THERMAL-HYDRAULIC CODE VALIDATION STANDARD PROBLEMS

APPENDIX E: ACRONYMS

APPENDIX F: LIST OF ATTENDEES

INDEX

xxviii

1357

1371

1379

1397

1415

1427

anticipated abnormal plant...

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