ML20210C790
| ML20210C790 | |
| Person / Time | |
|---|---|
| Issue date: | 07/16/1999 |
| From: | King T NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Ralph Beedle, Bischoff G, Chexal V, Drake A, Joseph Kelly, Lochbaum D, Subalusky W, Townsend D ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY, ELECTRIC POWER RESEARCH INSTITUTE, FRAMATOME, GENERAL ELECTRIC CO., INSTITUTE OF NUCLEAR POWER OPERATIONS, NUCLEAR ENERGY INSTITUTE (FORMERLY NUCLEAR MGMT &, UNION OF CONCERNED SCIENTISTS, WESTINGHOUSE OPERATING PLANTS OWNERS GROUP |
| References | |
| NUDOCS 9907270035 | |
| Download: ML20210C790 (10) | |
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July 16,1999 L
l Mr. William T. Subalusky Vice President and Director Govemment Relations Division Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, GA 30339-5957
Dear Mr. Subalusky:
SUBJECT:
REQUEST FOR REVIEW OF REPORT-COMPONENT PERFORMANCE STUDY-TURBINE DRIVEN PUMP, 1987-1998 Attached for your information and review is the draft report on the turbine-driven pump (TDP) reliability at U.S. commercial pressurized water reacturs and boiling water reactors. This study is part of our ongoing evaluation of the unreliability of risk-significant safety systems and their associated components. Using data obtained from licensee event reports and the. Nuclear Plant Reliability Data System (NPRDS), the study provides an estimate of the turbine-driven pump unreliability based on Engineered Safety Features (ESF) actuations and test demands between 1987 and 1998 and identifies dominant contributors to component unreliability, in addition, the report includes a comparison with turbine-driven pump unreliability estimates published in probabilistic risk assessments (PRAs) and individual plant examinations (IPEs), and evaluations i
of most significant trends.
Major findings obtained from this study are summarized below:
The TDP probability of failure on demand estimates developed in this study for the auxiliary feedwater (AFW), reactor core isolation cooling (RCIC) and high pressure coolant injection (HPCI) systems are consistent with the generic values from NUREG/CR-4550 as indicated below:
Lower Bound Mean udder Bound
- AFW System 2.2E-2 4.0E-2 6.4E-2
- RCIC System 9.1 E-6 2.0E-2 8.7E-2
- HPCI System 1.6E-3 3.3E-2 9.7E-2
- NUREG/CR-4550 1.1E 3 3E-2 1.1 E-1 The TDP mean probabilities of failure on demand used in plant-specific IPE studies were compared with the results of this study. For BWR RCIC and HPCI systems, all of the IPE mean values for the TDP failure on demand probability were within the range of this study and NUREG/CR-4550. However, for the AFW system, approximately half of the IPE mean values were outside the probability of failure on demand range that was estimated in this study. The difference is believed to be due to the use of only ESF
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July 16, 1999 Mr. Andrew Drake, Project Manager Westinghouse Owners Group Westinghouse Electric Corporation Mail Stop ECE 5-16 P.O. Box 355 Pittsburgh, PA 15230-0355
Dear Mr. Drake:
SUBJECT:
REQUEST FOR REVIEW OF REPORT-COMPONENT PERFORMANCE STUDY-TURBINE DRIVEN PUMP, 1987-1998 f
' Attached for your information and review is the draft report on the turbine-driven pump (TDP) reliability at U.S. commercial pressurized water reactors and boiling water reactors. This study is part of our ongoing evaluation of the unreliability of risk-significant safety systems and their associated components. Using data obtained from licensee event reports and the Nuclear Plant Reliability Data System (NPRDS), the study provides an estimate of the turbine-driven pump unreliability based on Engineered Safety Features (ESF) actuations and test demands between 1987 and 1998 and identifies dominant contributors to component unreliability. In addition, the report includes a comparison with turbine-driven pump unreliability estimates published in probabilistic risk assessments (PRAs) and individual plant examinations (IPEs), and evaluations of most significant trends.
Major findings obtained from this study are summarized below:
The TDP probability of failure on demand estimates developed in this study for the auxiliary feedwater (AFW), reactor core isolation cooling (RCIC) and high pressure coolant injection (HPCI) systems are consistent with the generic values from NUREG/CR-4550 as indicated below:
Lower Bound Mean udder Bound
- AFW System 2.2E-2 4.0E-2 6.4E-2
- RCIC System 9.1 E-6 2.0E-2 8.7 E-2
- HPCI System 1.6E-3 3.3E-2 9.7E-2
- 1.1 E-3 3E-2 1.1 E-1 The TDP mean probabilities of failure on demand used in plant-specific IPE studies were compared with the results of this study. For BWR RCIC and HPCI systems, all of the IPE mean values for the TDP failure on demand probability were within the range of this study and NUREG/CR-4550. However, for the AFW system, approximately half of the IPE mean values were outside the probability of failure on demand range that was estimated in this study. The difference is believed to be due to the use of only ESF
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- 49,,..,o July 16, 1999 Mr. J. J. Kelly, Manager B&W Owners Group Services Framatome Technologies, Inc.
P.O. Box 10935 Lynchburg, VA 24506-0935
Dear Mr. Kelly:
Si)BJECT:
REQUEST FOR REVIEW OF REPORT - COMPONENT PERFORMANCE STUDY-TURBINE DRIVEN PUMP, 1987-1998 Attached for your information and review is the draft report on the turbine-driven pLmp (TDP) reliability at U.S. commercial pressurized water reactors and boiling water reactors. This study is part of our ongoing evaluation of the unreliability of risk-significant saf 3ty systems and their associated components. Using data obtained from licensee event reports and the Nuclear Plant Reliability Data System (NPRDS), the study provides an estimate of the turbine-drive;n pump unreliability based on Engineered Safety Features (ESF) actuations and test demands between 1987 and 1998 and identifies dominant contributors to component unreliability. In addition, the report includes a comparison with turbine-driven pump unreliability estimates published in probabilistic risk assessments (PRAs) and individual plant examinations (IPEs), and evaluations j
of most significant trends.
l Major findings obtained from this study are summarized below:
The TDP probability of failure on demand estimates developed in this study for the auxiliary feedwater (AFW), reactor core isolation cooling (RCIC) and high pressure
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Lower Bound Mean U_pp_er Bound
- AFW System 2.2E-2 4.0E-2 6.4E-2
- RCIC System 9.1 E-6 2.0E-2 8.7E-2
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- HPCI System 1.6E-3 3.3E-2 0.7E-2
- NUREG/CR-4550 1.1 E-3 3E-2 1.1 E-1 The TDP mean probabilities of failure on demand used in plant-specific IPE studies were compared with the results of this study. For BWR RCIC and HPCI systems, all of the IPE mean values for the TDP failure on demand probability were within the range of this study and NUREG/CR-4550. However, for the AFW system, approximately half of i
the IPE mean values were outside the probability of failure on demand range that was estimated in this study. The difference is believed to be due to the use of only ESF
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July 16, 1999 ABB Combustion Engineering Owners Group c/o Gordon Bischoff, CEOG Project Manager M.S. 9615-1932 2000 Day Hill Road Windsor, CT 06095
Dear Mr. Bischoff:
SUBJECT:
REQUEST FOR REVIEW OF REPORT - COMPONENT PERFORMANCE STUDY-TURBINE DRIVEN PUMP, 1987-1998 Attached for your information and review is the draft report on the turbine-driven pump (TQP) reliability at U.S. commercial pressurized water reactors and boiling water reactors. This study 4
is part of our ongoing evaluation of the unreliability of risk-significant safety systems and their j
associated components. Using data obtained from licensee event reports and the Nuclear Plant
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Reliability Data System (NPRDS), the study provides an estimate of the turbine-driven pump unreliability based on Engineered Safety Features (ESF) actuations and test demands between 1987 and 1998 and identifies dominant contributors to component unreliability. In addition, the report includes a comparison with turbine-driven pump unreliability estimates published in probabilistic risk assessments (PRAs) and individual plant examinations (IPEs), and evaluations of most significant trends.
Major findings obtained from this study are summarized below:
The TDP probability of failure on demand estimates developed in this study for the j
auxiliary feedwater (AFW), reactor core isolation cooling (RCIC) and high pressure coolant injection (HPCI) systems are consistent with the generic values from NUREG/CR-4550 as indicated below:
Lower Bound Mean Upper Bound
- AFW System 2.2E-2 4.0E-2 6.4E-2
- RCIC System 9.1E-6 2.0E-2 8.7E-2
- HPCI System 1.6E-3 3.3E-2 9.7E-2
- NUREG/CR-4550 1.1 E-3 3E-2 1.1 E-1 The TDP mean probabilities of failure on demand used in plant-specific IPE studies were compared with the results of this study. For BWR RCIC and HPCI systems, all of j
the IPE mean values for the TDP failure on demand probability were within the range of this study and NUREG/CR-4550. However, for the AFW system, approximately half of i
the IPE mean values were outside the probability of failure on demand. range that was estimated in this study. The difference is believed to be due to the use of only ESF l
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' s WASHINGTON, D.C. 20$5fM)o01 July 16, 1999 Mr. Dennis Townsend General Electric Nuclear Energy Owners Group G.E. Nuclear Energy 175 Curtner Avenue M/C 187 San Jose, CA 95125
Dear 11r. Townsend:
SUBJECT:
REQUEST FOR REVIEW OF REPORT - COMPONENT PERFORMANCE STUDY-TURBINE DRIVEN PUMP, 1987-1998 i
Attached for your information and review is the draft report on the turbine-driven pump (TDP) reliability at U.S. commercial pressurized water reactors and boiling water reactors. This study is part of our ongoing evaluation of the unreliability of risk-significant safety systems and their associated components. Using data obtained from licensee event reports and the Nuclear Plant Reliability Data System (NPRDS), the study provides an estimate of the turbine-driven pump unreliability based on Engineered Safety Features (ESF) actuations and test demands between 1987 and 1998 and identifies dominant contributors to component unreliability. In addition, the report includes a comparison with turbine-driven pump unreliability estimates published in probabilistic risk assessments (PRAs) and individual plant examinations (IPEs), and evaluations of most significant trends.
Major findings obtained from this study are summarized below:
The TDP probability of failure on demand estimates developed in this study for the auxiliary feedwater (AFW), reactor core isolation cooling (RCIC) and high pressure coolant injection (HPCI) systems are consistent with the generic values from NUREG/CR-4550 as indicated below:
Lower Bound Mean Upper Bound
- AFW System 2.2E-2 4.0E-2 6.4E-2
- RCIC System 9.1 E-6 2.0E-2 8.7E-2
- HPCI System 1.6E-3 3.3E-2 9.7E-2
- NUREG/CR-4550 1.1 E-3 3E-2 1.1 E-1 The TDP mean probabilities of failure on demand used in plant-specific IPE studies were compared with the results of this study. For BWR RCIC and HPCI systems, all of the IPE mean values for the TDP failure on demand probability were within the range of this study and NUREG/CR-4550. However, for the AFW system, approximately half of the IPE mean values were outside the probability of failure on demand range that was estimated in this study. The difference is believed to be due to the use of only ESF l
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WASHINGTON, D.C. 20565-0001
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j July 16, 1999 L
l I
Mr. V. K. Chexal, Director l
Nuclear Safety Analysis Center Electric Power Research Institute P.O. Box 10412 l
Palo Alto, CA 94303 l
Dear Mr. Chexal:
SUBJECT:
REQUEST FOR REVIEW OF REPORT-COMPONENT PERFORMANCE STUDY-TURBINE DRIVEN PUMP, 1987-1998 Attached for your information and review is the draft report on the turbine-driven pump (TDP) reliability at U.S. commercial pressurized water reactors and boiling water reactors. This study is part of our ongoing evaluation of the unreliability of risk-significant safety systems and their associated components. Using data obtained from licensee event reports and the Nuclear Plant Reliability Data System (NPRDS), the study provides an estimate of the turbine-driven pump unreliability based on Engineered Safety Features (ESF) actuations and test demands between 1987 and 1998 and identifies dominant contributors to component unreliability. In addition, the report includes a comparison with turbine-driven pump unreliability estimates published in probabilistic risk assessments (PRAs) and individual plant examinations (IPEs), and evaluations of most significant trends.
Major findings obtained from this study are summarized below:
The TDP probability of failure on demand estimates developed in this study for the auxiliary feedwater (AFW), reactor core isolation cooling (RCIC) and high pressure coolant injection (HPCI) systems are consistent with the generic values from NUREG/CR-4550 as indicated below:
Lower Bound Mean Upper Bound
- AFW System 2.2E-2 4.0E-2 6.4E-2
- RCIC System 9.1 E-6 2.0E-2 8.7E-2
- HPCI System 1.6E-3 3.3E-2 9.7E-2
- NUREG/CR-4550 1.1 E-3 3E-2 1.1 E-1 The TDP mean probabilities of failure on demand used in plant-specific IPE studies were compared with the results of this study. For BWR RCIC and HPCI systems, all of the IPE mean values for the TDP failure on demand probability were within the range of this study and NUREG/CR-4550. However, for the AFW! system, approximately half of the IPE mean values were outside the probability of failure on demand range that was l
estimated in this study. The difference is believed to be due to the use of only ESF l
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WASHINGTON, D.C. 20555 0001 July 16, 1999 4
Mr. Ralph E. Beedle Nuclear Energy Institute 1776 i Street N.W.
Suite 400 Washington, D.C. 20006-3708
Dear Mr. Beedle:
SUBJECT:
REQUEST FOR REVIEW OF REPORT - COMPONENT PERFORMANCE STUDY-TURBINE DRIVEN PUMP, 1987-1998 Attached for your information and review is the draft report on the turbine-driven pump (TpP) reliability at U.S. commercial pressurized water reactors and boiling water reactors. This study is part of our ongoing evaluation of the unreliability of risk-significant safety systems and their associated components. Using data obtained from licensee event reports and the Nuclear Piant Reliability Data System (NPRDS), the study provides an estimate of the turbine-driven pump unreliability based on Engineered Safety Features (ESF) actuations and test demands between 1987 and 1998 and identifies dominant contributors to component unreliability. In addition, the report includes a comparison with turbine-driven pump unreliability estimates published in probabilistic risk assessments (PRAs) and individual plant examinations (IPEs), and evaluations of most significant trends.
Major findings obtained from this study are summarized below:
The TDP probability of failure on demand estimates developed in this study for the auxiliary feedwater (AFW), reactor core isolation cooling (RCIC) and high pressure coolant injection (HPCI) systems are consistent with the generic values from NUREG/CR-4550 as indicated below:
Lower Bound Mean Upper Bound
- AFW System 2.2E-2 4.0E-2 6.4E-2
- RCIC System 9.1 E-6 2.0E-2 8.7E-2
- HPCI System 1.6E-3 3.3E-2 9.7E-2
- NUREG/CR-4550 1.1 E-3 3E-2 1.1 E-1 The TDP mean probabilities of failure on demand used in plant-specific IPE studies were compared with the results of this study. For BWR RCIC and HPCI systems, all of the IPE mean values for the TDP failure on demand probability were within the range of this study and NUREG/CR-4550. However, for the AFW system, approximately half of the IPE mean values were outside the probability of failure on demand range that was estimated in this study. The difference is believed to be due to the use of only ESF
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.....,o July 16, 1999 Mr. David A. Lochbaum
)
Union of Concerned Scientists 1616 P Street, N.W.
Suite 310 Washington, D.C. 20035-1495
Dear Mr. Lochbaum:
SUBJECT:
REQUEST FOR REVIEW OF REPORT - C iPONENT PERFORMANCE STUDY-TURBINE DRIVEN PUMP,1987-r Attached for your information and review is the draft re
.,o the turbine-driven pump (TDP) reliability at U.S. commercial pressurized water reactors ond boiling water reactors. This study is part of our ongoing evaluation of the unreliability of risk-significant safety systems and their associated components. Using data obtained from licensee event reports and the Nuclear Plant Reliability Data System (NPRDS), the study provides an estimate of the turbine-driven pump unreliability based on Engineered Safety Features (ESF) actuations and test demands between 1987 and 1998 and identifies dominant contributors to component unreliability. In addition, the report includes a comparisor, with turbine-driven pump unreliability estimates published in probabilistic risk assessments (PRAs) and individual plant examinations (IPEs), and evaluations of most significant trends.
Major findings obtained.an this study are summarized below:
The TDP probability of feiture on demand estimates developed in this study for the auxiliary feedwater (AFW), reactor core isolation cooling (RCIC) and high pressure coolant injection (HPCI) systems are consistent with the generic values from NUREG/CR-4550 as indicated below:
. Lower Bound Mean Upper Bound
- AFW System 2.2E-2 4.0E-2 6.4E-2
- RCIC System 9.1 E-6 2.0E-2 8.7E-2
- HPCI System 1.6E-3 3.3E-2 9.7E-2
- NUREG/CR 4550 1.1 E-3 3E-2 1.1 E-1 The TDP mean probabilities of failure on demand used in plant-specific IPE studies were compared with the results of this study. For BWR RCIC and HPCI systems, all of the IPE mean values for the TDP failure on demand probability were within the range of
+
this study and NUREG/CR-4550. However, for the AFW system, approximately half of the IPE mean values were outside the probability of failure on demand range that was estimated in this study. The difference is believed to be due to the use of only ESF
+
Multiple Addressees 2
"3ilure and demand data in this study. We found that surveillance test failure and demand data were not statistically in the same population as the unplanned ESF demand and failure data. Moreover, we are aware that the surveillance tests for AFW TDPs were usually preconditioned (i.e., warmed-up), while TDP ESF demands experienced the more stringent " cold quick starts." The AFW TDP values used in IPEs were consistent with the probability of failure on demand values estimated from the surveillance test data. RCIC and HPCI TDP surveillance tests generally prohibited the use of preconditioning.
Failure rates, as a function of component-years, were compared among the PWR and BWR, plant age groups (3 groups of approximately equal size, from older to newer plants by commercial operations date). For both PWRs and BWRs, the review of plant age groups did not show clear evidence of component aging or plant age effects on TDPs.
The evaluation of TDP sub-component (e.g., governor, turbine, pump) failure patterns demonstrated that failures of governor sub-components were significant contributors to the TDP unreliability in the BWR RCIC system (70%). For the BWR HPCI system, turbine and govemor failures were both dominant contributors to the TDP unreliability (53% and 47%, respectively). For PWRs, the evaluation of AFW system sub-component failure patterns determined that ynvemor (50%) and turbine (42%) failures were significant contributors to the overall TDP unreliability.
TDP failure causes for the PWR AFW system were mainly due to age / wear (26%) and maintenance / procedural deficiencies (24%). For the BWR RCIC system, the main causes were also due to age / wear (30%) and maintenance / procedural deficiencies (27%), while the cause of TDP failures for the HPCI system was predominantly maintenance / procedural deficiencies (45%).
In accordance with our peer review process prior to the distribution of the final report, we want to provide you with the opportunity to review and comment on the draft report. We are specifically interested in your comments regarding the technical adequacy of the data analysis and the appropriateness of the major findings from this study. In order to meet our planned publication schedule, we would appreciate receiving your comments within 30 days from receipt of this letter.
A copy of this draft report and letter are being placed in the Public Document Room at 2120 L Street NW, Washington, DC 20555
i Mulflpb Addr:ssees 3
If you have any quec.tions related to this report, please contact Mr. Hossein Hamzehee at 301-415-6228 or e-mail: bgh@nrc. gov of my staff.
Sincerely,
/s/
Thomas L. King, Director Division of Risk Analysis and Applications Office of Nuclear Regulatory Research
Attachment:
As stated cc w/att.:
A. Thadani, RES M. Federline, RES S. Collins, NRR R. Zimmerman, NRR B. Sheron, NRR W. Kane, NRR INDENTICAL LETTERS pistribution w/att.:
OERAB RF ARubin, RES MReinhart, NRR PBernard, Ril DRAA RF MCunningham, RES JCalvo, NRR MParker, Rlli File Center NSiu, RES RBarrett, NRR SBurgess, Rill Public MDrouin, RES PWilson, NRR JShackelford, RIV JRosenthal JVora, RES DCoe, NRR WJones, RIV JFlack LLancaster, RES WDean, NRR HOmstein GParry, NRR MJohnson, NRR MKnapp, DEDE SMalik, NRR AMadison, NRR JMitchell, OEDO FTalbot, NRR JTrapp, RI JLarkins, ACRS LMarsh, NRR TShediosky, Rl MMarkley, ACRS MRubin, NRR WRogers, Ril DOCUMENT NAME: S:\\DRAA.OERAB\\HGH\\TDPCLTR2.WPD To receive a copy of this document indicate in the box: "C" = Copy wolenci "E" = Copy wienci "N" = No cop' r OFFICE OERAB C,
OERAB
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OERAB C
OERAB
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NAME HHamzeheefff SMays M PBaranowhg TKing/ jQ DATE
'I/ '? /99 7 / 5/99 y//5/99 7/ /L, /99 OFFICIAL RECORD COPY
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