ML20212D900
| ML20212D900 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee, Point Beach, Haddam Neck, 05000000 |
| Issue date: | 12/29/1986 |
| From: | Ellen Brown NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
| To: | Rubin S NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) |
| Shared Package | |
| ML20212D903 | List: |
| References | |
| AEOD-E613, NUDOCS 8701050118 | |
| Download: ML20212D900 (2) | |
Text
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..e AE0D/E613 MEMORANDUM FOR: Stuart D. Rubin, Chief Reactor Operations Analysis Branch Office for Analysis and Evaluation ifb. g l of Operational Data GQ
<2 l3 THRU:
Matthew Chiramal, Chief Engineering Section N ' 30 5 Reactor Operations Analysis Branch Office for Analysis and Evaluation of Operational Data FROM:
Earl J. Brown Engineering Section Reactor Operations Analysis Branch Office for Analysis and Evaluation of Operational Data
SUBJECT:
LOCALIZED R0D CLUSTER CONTROL ASSEMBLY (RCCA)
WEAR AT PWR PLANTS An engineering evaluation report on operational data involving degradation of rod cluster control assemblies is enclosed. The available event data was obtained for Westinghouse designed PWRs. There was no data to ascertain whether.imilar wear should be anticipated at PWRs designed by Babcock Wilcox or Combustion Engineering. The available information demonstrates that degradation is generic to this design and will occur on all RCCAs (shutdown and control banks). The degradation appears related to plant operating time (number of fuel cycles) and whether operation involved plant load following.
There are potential safety concerns related to rodlet clad integrity, rod insertion, or loss of absorber material.
It appears that the RCCA status and extent of degradation can only be determined by inspection of the RCCAs during a refueling outage.
Only three events were obtained from the database systems.
In reviewing these reports, it was found that these licensees had determined that RCCA wear was not reportable by either an LER requirement or to the NPRDS. Thus, general licensee awareness of the RCCA degradation and the need for inspections is not clear even though Westinghouse, on an informal basis, has provided information about the problem. Therefore, it is recommended that IE issue an information notice to alert licensees about the problem of RCCA wear and the need to plan and schedule inspections to determine the condition of all RCCAs. The report also suggests that NRR consider whether there is a need to establish periodic inspections k
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5 8701050118 861229 PDR ADOCK 05000213 (L,
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. (such as a 10-year interval) of RCCAs and assess the feasibility of reactor water chemistry monitoring procedures to detect severe, through-wall rodlet degradation.
s Earl J. Brown Engineering Section Reactor Operations Analysis Branch Office for Analysis and Evaluation of Operational Data
Enclosure:
As Stated cc w/ enclosure:
i T. Colburn, NRR F. Akstulewicz, NRR M. Fairtile, NRR D. Sullivan, RES J. Vora,-RES DISTRIBUTION j
PDR E. Brown ROAB CF M. Chiramal l
AE0D SF S. Rubin AE00 CF M. Williams D. Dilanni, NRR K. Black G. Requa, NRR W. Lanning M. Dunenfeld, NRR F. Hebdon D. Sellers, NRR C. Heltemes, Jr.
C. Berlinger, NRR P. Lam G. Lear, NRR S. Salah L. Rubenstein, NRR S. Varga, NRR J. Youngblood, NRR V. Noonan, NRR C. Grimes, NRR R. Ballard, NRR L. Marsh, NRR C. Thomas, NRR P. Lam, AE00 R. Baer, IE i
M. Chatterton, NRR T. Chan, NRR OFC
- ROAB
. BC:ROAB
.....: ____l[p:a[1._::_SC:ROAB[b4W:----____..,):____________:..--__
NAME : EBrown s
- MChiramal
- SRubin 12/}y/86 12/ \\$/86 DATE : 12/13/86 i
0FFICIAL RECORD COPY
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