ML20236V111
| ML20236V111 | |
| Person / Time | |
|---|---|
| Issue date: | 07/30/1998 |
| From: | Rossi C NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
| To: | NRC |
| References | |
| AL-98-04, AL-98-4, NUDOCS 9807310308 | |
| Download: ML20236V111 (3) | |
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July 30,1998
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To Senior Licensee Officials on the Attached List
SUBJECT:
COMMON CAUSE FAILURE DATABASE DISTRIBUTION A copy oi NRC Administrative Letter 98-04 is enclosed for your information. As indicated in this administrative letter, the Office for Analysis and Evaluation of Operational Data (AEOD) and the Idaho National Engineering and Environmental Laboratory (INEEL) have developed a common-cause failure (CCF) database and analysis software package to aid in system reliability ana!yses and related risk-informed applications. The database and supporting technical documentation contained on the enclosed CD-ROM are provided for your information and use.
Please note, INPO has given the NRC permission to distribute the CCF database to INPO members for their use with specific restrictions. A Conditions of Use statement from INPO is also enclosed. For this reason the database is password protected. After initialinstallation of i
the database, your organization will be responsible for complying with the INPO Conditions of l
Use.
We would appreciate any comments regarding the utility and accuracy of the database and associated computational tools. For technical information or other assistance, please contact Dr. Dale Rasmuson of my staff at 301-415-7571.
Sincerely, Original signed by:
Charles E. Rossi, Director Safety Programs Division Office for Analysis and Evaluation of Operational Data
Enclosures:
As stated cc w/ enclosures:
B. Keener, INPO kj Distribution: See attached list DR ng-is
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To Senior Licensee Officiels on the ' Attached List
SUBJECT:
COMMON CAUSE FAILURE DATABASE DISTRIBUTION The Offica for Analysis and Evaluation of Operationa! Data (AEOD) and the Idaho Nation Engineering and Environmental Laboratory (INEEL) have developed a common-cause ilure (CCF) database and analysis software package to aid in the analysis of system relia 'ity and related risk-informed applications. Common cause failures have been identified as significant contributors to system failure in many Probabilistic Risk Assessments, Common cause failure
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events are characterized by failure or degradation of multiple (typically redundant) components due to the same shared cause. The database contains CCF related events that have occurred in U.S. commercial nuclear power plants from 1980 through 1995. The events were identified from failure reports in the Nucioar Plant Reliability Data System (NPRDS), which is a proprietary database maintained by the Institute of Nuclear Power Operations, and Licensee Event Reports (LERs) obtained from the Sequence Coding and Search System (SCSS) database maintained by the U.S. Nuclear Regulatory Commission. Tha database and supporting technical documentation contained on the enclosed CD-ROM are provided for your information and use in system reliability analysis and similar risk-informed applications.
Please note, INPO has given the NRC permission to distrib' ute the CCF database to INPO members for their use with specific restrictions. A Conditions of Use statement from INPO is also enclosed. For this reason the database is passw' rd protected. After initial installation of o
the database, your organization will be responsible for complying with the INPO Conditions of Use.
We would appreciate any comments regarding the utility and accuracy of the database and associated computational tools. For technical information or other assistance, please contact Dr. Dale Rasmuson of my staff at 301-415-7571.
Sincerely, Thomas T. Martin, Director Office for Analysis and Evaluation of Operational Data
Enclosures:
As stated ccw/ enclosures:
T. McHenry, INPO j
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UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, DC 20555-0001 July 30, '.998 NRC ADMINISTRATIVE LETTER 98-04: AVAILABILITY OF COMMON-CAUSE FAILURE DATABASE Addressees All holders of operating licenses for nuclear power reactors, except those licensees who have permanently ceased operations and have certified that fuel has been permanently removed from the reactor vessel.
EuCDOS2 The U.S. Nuclear Regulatory Commission (NRC) is issuing this administrative letter to notify nuclear power reactorlicensees of the availability of a common-cause failure (CCF) database, CCF analysis software, and associated technical reports. This administrative letter does not transmit any new requirements or staff positions. No specific action or written response is required.
Backaround CCFs have been identified as significant contributors to system failure probability and accident sequence core damage frequency in most probabilistic risk assessments (PRAs) since the Reactor Safety Study (WASH-1400). They are also important contributors in the individual plant examinations (IPEs).
A CCF event consists of component failures that meet four criteria: (1) two or more individual components fail or are degraded, including failures during demand, failures during inservice l
testing, or deficiencies that would have resulted in a failure if a demand signal had been received; (2) components fail or are degraded within a selected period, such that success of the PRA mission would be uncertain; (3) component failures result from a single shared cause and coupling mechanism; and (4) e component failure occurs within the established component boundary.
An approach to performing plant-specific CCF analyses was developed jointly by NRC and the Electric Power Research Institute in the late 1980s. The approach is documented in NUREGICR-4780, Procedures for Treating Common Cause Failures in Safety and Reliability Studies, Volumes 1 and 2. These documents gave relatively little guidance on the analysis of i
data. Furthermore, the cata required for application of the approach were not generally available in a readily accessible form. Each application involved significant rescreening of a large amount of data by each analyst using the approach.
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AL 98-04 July 30,1998 Page 2 of 3 in the past, the majority of CCF analyses performed in support of PRAs have used generic estimates for CCF parameters. Some have used the methods of NUREG/CR-4780 but produced widely varying results because of differences in the individual analysts' screening of industry data derived primarily from the licensee event reports (LERs).
DiscussiGD in response to these deficiencies related to CCF data, the NRC's Office for Analysis and Evaluation'of Operational Data (AEOD) and the Idaho National Engineering and Environmental Laboratory have developed a CCF database and analysis software package to aid in this aspect of system reliability analyses and related risk-informed applications. The CCF Catabase provides guidance on the screening and interpretation of data and contains relevant event data to provide a more uniform and cost-effective way of performing CCF analyses.
Documentation of the database is presented in four volumes: " Overview,"" Event Definition and Classification of Common-Cause Failure Events,"" Data Collection and Coding Common-Cause Failure Events," and " Common-Cause Failure Database and Analysis Software Reference Manual." These technical reports are published as NUREG/CR-6286," Common-Cause Failure Database and Analysis System."
The principal products of this CCF data collection and analysis system are the method and guidelines for identifying, classifying, and coding CCF events; the CCF database containing both CCF events and an estimate of independent failure counts; and the CCF parameter estimation software.
The CCF event identification process includes reviewing failure data to identify CCF events and ccunting independent failure events. The process allows the analyst to consistently screen failures and identify CCF events. The CCF event coding process provides guidance for the analyst to consistently code CCF events. Additionally, the CCF events are stored in a format that allows PRA analysts to review the events and develop an understanding of how they occurred.
The database contains CCF-related events that have occurred in U.S. commercial nuclear power plants from 1980 through 1995. The events were identified from failure reports in the Nuclear Plant Reliability Data System (NPRDS), which is a proprietary database maintained by the institute of Nuclear Power Operations (INPO), and LERs obtained from the Sequence Coding and Search System (SCSS) database maintained by the Oak Ridge National Laboratory for the NRC. The current data collection effort has separated the data by system as well as by component type.
The CCF analysis software uses the impact vector method demonstrated in NUREG/CR-4780.
The basic information needed for understanding and coding a CCF event is based on the physical characteristics of the event and is recorded in fields in the database. The database software allows an analyst to tailor the assessment of these parameters for plant-specific analyses.
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July 30,1998
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Page 3 of 3 1
The interpretation of the degree of impact of the CCF events on affected components is a somewhat subjective process impact interpretations contained in the database are clearly documented for each event. In addition, the analysis software provides the opportunity for analysts to review and modify these evaluations when performing plant-specific CCF analyses.
The CCF parameters estimated by the database software are conditional on these particular interpretations. Therefore, the NRC will continue to review CCF analyses r1d in regulatory applications on a case-by-case basis. The use of the CCF database should help to make the q
analyses easier to properly perform and more scrutable during the review process.
Because NPRDS data are proprietary, AEOD by a separate letter will be providing the CCF l
database and the CCF analysis software, along with supporting technical documentation, to l
only nuclear power plant licensees who are members of INPO. Copies of NUREG/CR-6286 J
may be obtained from the Public Document Rcom or from the Superintendent of Documer.t i
Any questions should be directed to the contact listed below.
y Jack W. Roe, Acting Director Division of Reactor Program Management Office of Nuclear Reactor Regulation
Contact:
Dale M. Rasmuson, AEOD 301-415-7571 Email: dmr@nrc. gov
Attachment:
List of Recently issued NRC Administrative Letters O
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e Attachment AL98-04 July 30,1998 Page 1 of 1 LIST OF RECENTLY ISSUED NRC ADMINISTRATIVE LETTERS Administrative Date of Lt.rter No.
Subject issuance issued to 98-05, Rev.1 Compliance with the Rule 07/14/98 All material and fuel cycle
" Timeliness in Decommissioning licensees of Material Facilities
- 98-03 Operating Reactor Licensing 05/6/98 All power reactor licensees Action Estimates 98-02 Revision of Event Reporting 03/17/98 All holders of operating Guidelines for Power Reactors licenses for nuclear reactors 98-01 Maintenance Rule information 02/20/98 All holders of operating licenses Available on the NRC Home Page for nuclear reactors.
97-04 NRC Staff Approval for 09/30/97 All holders of operating Changes to 10 CFR, licenses for nuclear power Part 50, Appendix H, reactors except those who have Reactor Vessel Surveillance permanently ceased operations Specimen Withdrawal Schedules and have certified that fuel has been permanently removed from the reactor vessel 97-03 Plant Restart Discussions 03/28/97 All holders of OLs or cps Following Natural Disasters for nuclear power reactors 97-02 Elimination of National 03/06/97 All holders of OLs or cps Examination Schedule for for nuclear power reactors Operator Licensing 97-01 State Initiatives to 01/17/97 All holders of OLs or Legalize Schedule 1 for nuclear power reactors Drugs and alllicensees authorized to possess or transport Category i nuclear material 96-05 Compilance with the 11/05/96 All material and fuel Rule " Timeliness in cycle licensees Decommissioning of Material Facilities" OL = Operating License CP = Construction Permit I
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NPRDS Conditions of Use BY USING THE COMMON CAUSE FAILURE DATABASE, WHICH CONTAINS NPRDS DATA, YOU AGREE TO THE FOLLOWING CONDITIONS: The data contained in the Nuclear Plant Reliability Data System (NPRDS) are the exclusive property of the Institute of Nuclear Power Operations (iNPO) and the U.S. nuclear utility members of INPO. NPRDS may be used only to promote safety and reliability in the operation of commercial nuclear power plants.
INPO strictly prohibits any use of NPRDS, or data obtained through NPRDS, in marketing, advertising, solicitations, proposals, and similar activities.
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Data obtained through NPRDS are confidential. Disclosure is prohibited without the express, written, advance consent of INPO. In addition, disclosure of data that identify an individual nuclear power plant is prohibited without the express, written, advance consent of the Member of INPO that has primary authority for the i
operation of that plant. Any disclosure to the U.S. Nuclear Regulatory Commission is permitted, without any consent, provided that the disclosure is accompanied by a statement that NPRDS data are confidential, commercial information and the exclusive property of INPO.
Any individual or organization that obtains access to NPRDS by means of contract with an INPO Member shall retum to the Member all NPRDS data, user identification codes, passwords, documentation, and similar items at the conclusion of the contract.
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ys Distribution List for Senior Licens o Offici*ls M:ansas 1 & 2 Mr. C. Randy Hutchinson Vice President, Operations Entergy Operations Inc.
1448 S.R. 333 Russellville, AR 72801 Beaver Vallev 1 & 2 Mr. James E. Cross Senior Vice President and Chief Nuclear Officer Duquesne Light Co.
P.O. Box 4 Shippingport, PA 15077 Bia Rock Point and Palisades Mr. Robert A Fenech Senior Vice President, Nuclear, Fossil and Hydro Operations Consumers Power Company 212 West Michigan Avenue Jackson, MI 49201 Braidwood 1 & 2. Byron 1 & 2. Dresden 2 & 3. LaSalle 1 & 2. Quad Cities 1 & 2. and Zion 1 & 2 Mr. Oliver D. Kingsley, Jr.
President and Chief Nuclear Officer, Nuclear Generation Group Commonwealth Edison Co.
Executive Tower West 111 1400 Opus Place, Suite 900 Downers Grove, IL 60515 Browns Ferry 1. 2. & 3. Seouovah 1 & 2. and Watts Bar 1 Mr. O. J. Zeringue Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Brunswick 1 & 2. Harris. and Robinson 2 Mr. William G. Orser Executive Vice President - Energy Supply and Chief Nuclear Officer Carolina Power & Light Co.
P.O. Box 1551 Raleigh, NC 27602 Callaway l
Mr. Gary L. Randolph Vice President and Chief Nuclear Officer Union Electric Co.
P.O. Box 149 St. Louis, MO 63166 i
Calvert Cliffs 1 & 2 Mr. Charles E. Cruse Vice President-Nuclear Energy i
Baltimore Gas & Electric Co.
Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway l
Lusby, MD 20657 4702 Catawba 1 & 2. McGuire 1 & 2. and Oconee 1. 2. & 3 Mr. Michael S. Tuckman Senior Vice President - Nuclear Generation Duke Power Co.
P.O. Box 1006 Charlotte, NC 28201-1006 Clinton Mr. John G. Cook Senior Vice President-Clinton Power Station l
lilinois Power Co.
l P.O. Box 678 Clinton, IL 61727 1
Comanche Peak 1 & 2 Mr. C. Lance Terry i
Group Vice President, Nuclear Production Texas Utilities Electric Company Energy Plaza 1601 Bryan Street,12th Floor Dallas, TX 75201-3411 Cook 1 & 2 Mr. Eugene E. Fitzpatrick Senior Vice President of Nuclear Generation Indiana Michigan Power Co.
clo American Electric Power Service Corp.
1 Riverside Plaza Columbus, OH 43215 Cooper Mr. Philip D. Graham Vice President - Nuclear Nebraska Public Power District P.O. Box 499 Columbus, NE 68602-0499 Crystal River 3 l
Mr. Roy A. Anderson Senior Vice President - Nuclear Operations Florida Power Corp.
15760 West Power Line Street Crystal River, FL 34428-6708 l
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Davis-Besse j
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Mr. John K. Wood j
Vice President, Nuclear - Davis-Besse Toledo Edison Co.
j Davis-Besse NPS -
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' 5501 N. State Route 2 Oak Harbor, OH 43449 Diablo Canvon 1 & 2 Mr. Gregory M. Rueger L
- Senior Vice President & General Manager Nuclear Power Generation Pacific Gas and Electric Co.
77 Beale Street, Room 1451
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P.O. Box 770000, Mail Code B14A San Francisco, CA 94177' Duane Arnold l
Mr. Lee Liu l
Chairman of the Board and Chief Executive Officer
'lES Utilities Inc.
l P.O. Box 351
' Cedar Rapids, IA 52406 l
Farlev 1 & 2. Hatr+i 1 & 2. and Vaatia 1 & 2 Mr. Jack D. Woodard i
Executive Vice President - Nuclear Operations i
Southem Nuclear Operating Company l
P.O. Box 1295 I
Birmingham, AL 35201-1295 Fermi-2 i
Mr. Douglas R. Gipson Senior Vice President - Nuclear Generation Detroit Edison Co.
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- 6400 N. Dixie Hwy.
L Newport, MI 48166 i
l FitzPatrick and indian Point 3 l
Mr. James Knubel j
Chief Nuclear Officer Power Authority of the State of New York 123 Main Street White Plains, NY 10601 l
Fort Calhoun Mr. W. Gary Gates Vice President for Nuclear Operations Omaha Public Power District 444 South 16th Street Mall Omaha, NE 68102-2247 u_
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GiDDR Mr. Robert E. Smith Senior Vice President - Customer Operations Rochester Gas & Electric Corp.
89 East Avenue Rochester, NY 14649 r
Grand Gulf Mr. Joseph J. Hagan Vice President-Operations Entergy Operations, Inc.
P.O. Box 756 Port Gibson, MS 39150 Hone Creek and Salem 1 & 2 Mr. Leon R. Eliason Chief Nuclear Officer and Proskient, Nuclear Business Unit Public Service Electric & Gas Co.
P.O. Box 236 Hancocks Bridge, NJ 08038 Indian Point 2 Mr. Stephen E. Quinn Vice President - Nuclear Power Consolidated Edison Co. of NY, Inc.
Broadway and Bleakley Avenue l
Buchanan, NY 10511 Kewaunee Mr. Clark Steinhardt Senior Vice President - Nuclear Power Wisconsin Public Service Corp.
P.O. Box 19002 Green Bay, WI 54307-9002 I-Limerick 1 & 2 and Peach Bottom 2 & 3 Mr. Jerald R. Rainey Senior Vice President - Nuclear Operations PECO Energy Company Correspondence Control Desk i~
P.O. Box No.195 Wayne, PA 19087-0195 Maine Yankee Mr. Michael B. Sellman President and Chief Exocutive Officer Maine Yankee Atomic Power Co.
329 Bath Road Brunswick, ME 04011 a
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Millstone 1. 2. & 3 Mr. Bruce D. Kenyon President and Chief Executive Officer Northeast Nuclear Energy Company P.O. Box 128 Waterford, CT 06385 l
Monticello and Prairie Island 1 & 2 Mr. Michael Wadley Vice President - Nuclear Generation Northem States Power Co.
414 Nicollet Mall Minneapolis, MN 55401 Nine Mile Point 1 & 2 Mr. B. Ralph Sylvie Executive Vice President - Nuclear Niagara Mohawk Power Corp.
Nine Mile Point Nuclear Station P.O. Box 63 Lycoming, NY 13093 North Anna 1 & 2 and Surry 1 & 2 Mr. James P. O'Hanlon Senior Vice President - Nuclear Virginia Electric and Power Company 5000 Dominion Boulevard Glen Allen, VA 23060 Qy ;1er Creek and Three Mile Island 1 Mr. T. Gary Broughton President and Chief Executive Officer GPU Nuclear Corp.
1 Upper Pond Road Parsippany, NJ 07054 Palo Verde 1. 2 f 3 t
Mr. James M. Levine Senior Vice President, Nuclear Arizona Public Service Co.
P.O. Box 53999 Phoenix, AZ 85072-3999 Pro' Mr. John P. Stetz Senior Vice President, Nuclear - Perry l
Centerior Energy Corporation l
Cleveland Electric illuminating Co.
P.O. Box 97, S270 Peny, OH 44081
8.
Pilgnm Mr. Leon J. Olivier Vice President - Nuclear Boston Edison Co.
Pilgrim Nuclear Power Station RFD #1 Rocky Hill Road Plymouth, MA 02360 Point Beach 1 &J Mr. Richard R. Grigg President end Chief Operating Officer
~ Wisconsin Electric Power Co.
231 West Michigan Street Milwaukee, WI 53201 River Bend Mr. John R. McGaha Vice President - Operations Group River Bend Station Entergy Operations, Inc.
P.O. Box 220 -
St. Francisville, LA 70775 San Onofre 2 & 3 Mr. Harold B. Ray l
Senior Vice President - Power Generation Southem California Edison Co.
San Onofre Nuclear Generating Station Post Office Box 128 San Clemente, CA 92674-0128 l
1 Seabrook Mr. Ted C. Feigenbaum l
Executive Vice President and Chief Nuclear Officer North Atlantic Energy Service Corp.
P.O. Box 270 l
Hartford, CT 06141-0270 South Texas 1 & 2 Mr. William T. Cottle l
Group Vice President, Nuclear l
Houston Lighting & Power Co.
l-South Texas Project Electric Generating Station P.O. Box 289
.Wadsworth, TX 77483 I-St. Lucie 1 & 2 and Turkov Point 3 & 4 Mr. Thomas F. Plunkett President-Nuclear Division Florida Power & Light Co.
P.O. Box 14000 Juno Beach, FL 33408-0420 f
a Summer Mr. Gary J. Taylor Vice President - Nuclear Operations South Carolina Electric & Gas Co.
V. C. Summer Station P.O. Box 88, Mail Code 601 Jenkinsville, SC 29065 Susauehanna 1 & 2 Mr. Robert G. Byram Senior Vice President - Generation and Chief Nuclear Officer Pennsylvania Power & Light Co.
Two North Ninth Street Allentown, PA 18101-1179 Vermont Yankqg Mr. J. Gary Weigand President and Chief Executive Officer Vermont Yankee Nuclear Power Corp.
R.D. 5, Box 169 Ferry Road Brattleboro, VT 05301 Washinaton Nuclear 2 Mr. P. R. Bemis Vice President, Nuclear Operations Washington Public Power Supply System P.O. Box 968 Richland, WA 99352 Waterford 3 Mr. Charles M. Dugger Vice President - Operations Entergy Operations, Inc.
P.O. Box B Killona, LA 70066 Wolf Creek Mr. Otto L. Maynard President and Chief Executive Officer Wolf Creek Nuclear Operating Corp.
P.O. Box 411 Burlington, KS 66839 I
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