ML20035E847
| ML20035E847 | |
| Person / Time | |
|---|---|
| Issue date: | 04/09/1993 |
| From: | Ross D NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
| To: | Grimes B, Hodges M, Shao L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I), Office of Nuclear Reactor Regulation, NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| Shared Package | |
| ML20035E848 | List: |
| References | |
| AEOD-S93-02, AEOD-S93-2, NUDOCS 9304190318 | |
| Download: ML20035E847 (3) | |
Text
_ _ _ _ _ _ _
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NUCLEAR REGULATORY COMMISSION n
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April 9,1993 MEMORANDUM FOR:
Brian K. Grimes, Director Division of Operating Reactor Support, NRR Lawrence C. Shao, Director Division of Engineering, RES M. Wayne Hcdges, Director Division of Reactor Safety, RI Albert F. Gibson, Director Division of Reactor Safety, RII Hubert J. Miller, Director Division of Reactor Safety, RIII A. Bili Beach, Director Division of 'leactor Safety, RIV Ker.neth E. Psrkins, Director Division of Reactor Safety & Projects, RV FROM:
Denwood F. Ross, Acting Director Division of Safety Programs, AE00
SUBJECT:
REQUEST FOR PEER REVIEW COMMENTS - PRELIMINARY SPECIAL STUDY REPORT ON STANDBY TURBINE-DRIVEN PUMP PROBLEMS AT U.S. LIGHT WATER REACTORS A preliminary AE0D special study report," Operating Experience feedback -
Reliability of Safety-Related Steam Turbine-Driven Pumps," is enclosed.
The study analyzes and evaluates operational experience and safety implications associated with failures and degradations of turbine-driven standby pumps at U.S.
light water reactors (LWRs).
The intent of the study was to: (1) gather and review all available information and data on failures of standby turbine-driven pumps in order to identify failure mechanisms and corrective actions, (2) update the reliability of these turbine-driven pumps, and (3) establish a data base for use in risk based analyses. The report was structured to encourage its use by individual licensees in enhancing the reliability of their standby turbire-driven pumps as appropriate. The report addresses the operating experience of these pumps through 1990, including licensee event reports (LERS), Nuclear Plant Reliability Data System (NPRDS) failure reports, NRC and industry generic documents, and vendor technical infor.ntion (VTI) relating to the turbines and their control systems. LERs from January 1987 through December 1990 were analyzed for demand failures.
Failure mechanisms not previously addressed in generic communications were identified, as well as corrective actions to prevent such failures.
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Multiple Addressees In accordance with our " peer review" process, prior to the finalization and distribution of our sp9cial reports, we are providing you, INPO, NUMARC, NSAC, and vendors who provided input to the study, with a copy of the preliminary report for review and comment. We request that you focus your review primarily on the accuracy and completeness of the technical details (i.e., comments are being solicited on the technical accuracy of the report).
The findings and conclusions are provided for your information i. order that you may understand the significance that we place on them and, therefore, obtain a more complete picture of the total report. Changes to the findings and conclusions will be considered only if the underlying information concerning the details of plant design or system operation is in error.
We ask that comments be provided by memorandum.
Since we wish to finalize and issue the report shortly, we ask that any comments be received by us within 30 days from receipt of this preliminary report. Should your office require additional time beyond that point, please let us know; otherwise, it will be assumed that you have no comments.
If you or your staff have any questions regarding this study, please feel free to contact me or John Boardman at (301) 492-9861.
Orig!r al Eirrec : / :
Dr. Denwood F. Ross, Acting Director Division of Safety Programs, AE00
Enclosure:
As stated cc w/ enclosures Distribution:
T. Murley, NRR PDR EJordan E. Beckjord, RES Central File Dross T. Martin, RI TPAB R/F S. Ebneter, RII JBoardman A. Davis, RIII P0'Reilly J. Milhoan, RIV PBaranowksy J. Martin, RV MTaylor, EDO RSavio, ACRS s
f TPAB:DSP*h TPAB:D50*
AC:TPAQtyg/
AD:05P:AEOD JBoardman
- P0'Reilly JJohnsoP DfRoss 4/8/93 4/8/93 4/q/93 4/ /93
- See previous concurren-'
Multiple Add,essees In accordance with our " peer review" process, prior to the finalization and distribution of our special reports, we are providing you, INPO, NUMARC, NSAC, and vendors who provided input to the study, with a copy of the preliminary report for review and comment. We request that you focus your review primarily on the accuracy and completeness of the technical details (i.e., comments are being solicited on the technical accuracy of the report).
The findings and conclusions are provided for your information in order that you may understand the significance that we place on them and, therefore, obtain a more complete picture of the total report. Changes to the findings and conclusions will be considered only if the underlying information concerning the details of plant design or system operation is in error.
We ask that comments be provided by memorandum.
Since we wish to finalize and issue the report shortly, we ask that any comments be received by us within 30 days from receipt of this preliminary report. Should your office require additional time beyond that point, please let us know; otherwise, it will be assumed that you have no comments.
If you or your staff have any questions regarding this study, [please feel free to contact me or John Boardman at (301) 492-9861.
Dr. Denwood F. Ross, Acting Director Division of Safety Programs, AE0D
Enclosure:
As stated cc w/ enclosures Distribution:
T. Murley, NRR PDR EJordam E. Beckjord, RES Central File Dross T. Martin, RI TPAB R/F S. Ebneter, RII JBoardman A. Davis, RIII P0'Reilly J. Milhoan, RIV PBaranowksy J. Martin, RV MTaylor, EDO RSavio, ACRS TPAB:DSPh'}
TPAB:DSP AC:TPAB:DSP AD:DSP:AE0D JBoardman -
P0'Reilly JJohnson DFRoss 4/5/93 4/]/93 4/ /93 4/ /93