ML20206B558

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Forwards Engineering Evaluation Rept Re RWCU Sys Automatic Isolation Events & Safety Significance of Operational Problems.Potential Improvements Include Hardware Changes & Procedural Mods
ML20206B558
Person / Time
Issue date: 03/31/1987
From: Heltemes C
NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
To: Lyon P
INSTITUTE OF NUCLEAR POWER OPERATIONS
Shared Package
ML20206B554 List:
References
AEOD-E705, NUDOCS 8704090229
Download: ML20206B558 (2)


Text

Mr. P:t:r Ly:n, Group Vics Presid::nt March 31, 1987 Institute of Nuclear Power Operations 1100 Circle 75 Parkway Suite 1500 Atlanta, Georgia 30339 AE0D/E705

Dear Mr. Lyon:

Subject:

Engineering Evaluation Report--RWCU System Automatic Isolation and Safety Considerations The Office for Analysis and Evaluation of Operational Data (AE00) has completed its engineering evaluation on the reactor water cleanup (RWCU) system automatic isolation events and the safety significance of RWCU system operational problems. The principal operational significance of these events is that operator attention and plant technical resources are diverted from other more important matters for investigating and reporting RWCU system spurious isolation events. Additionally, each time an isolation of the system occurs, plant personnel are exposed to additional radiation in order to investigate the isolation. P We have pulled together and summarized a number of operational improvements suggested by licensees of boiling water reactors that might be beneficial to other licensees in striving for excellence in plant operations as it relates to the RWCU system. These potential improvements include hardware changes as well as procedural modifications, and are summarized in Tables 3 and 4 of the attached report. We believe that the information in the report could be useful to INP0 in its ongoing efforts with licensees to improve plant operations and to maintain radiation exposures of personnel to "as low as reasonably achievable" levels.

If you or your staff have any questions regarding this report, please contact Dr. Neill Thomasson of my staff. Dr. Thomasson can be reached at (301) 492-4431.

Sincerely, onsmusapes my

c. J. % Jr.

C. J. Heltemes, Jr., Director Office for Analysis and Evaluation of Operational Data

Attachment:

As stated cc w/ enclosure: 8704090229 870327 V. Stello, ED0 PDR ORG NEXD J. Zerbe, DEDO PDR DISTRIBUTION:

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Mr. Peter Lyon well as procedural modifications, and are summarized in Tables 3 and 4 of the attached report. We believe that the information in the report could be useful to INP0 in its ongoing efforts with licensees to improve plant operations and.

to maintain radiation exposures of personnel to "as low as reasonab achievable" levels.

A copy of the final engineering evaluation report and this le er are being placed in the Public Document Room at 1717 H Street, N.W. W ington, D.C. 20555.

If you or your staff have any questions regarding this eport, please contact Dr. Neill Thomasson of my staff. Dr. Thomasson can reachedat(301) 492-4431.

Sincere ,

C. J. Heltemes, Jr., Director Office for Analysis and Evaluation of Operational Data

Attachment:

As stated cc w/ enclosure:

V. Stello, EDO J. Zerbe, DEDO DISTRIBUTION:

PDR AE0D SF AE0D CF ROAB SF ROAB CF NThomasson PBaranowsky SRubin WLanning KBlack j MWilliams FHebdon/

CHeltemes

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DATE:3/63/87.....:.........

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