ML20116H292
| ML20116H292 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 04/18/1985 |
| From: | Edelman M CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| (RDC-124(85)), NUDOCS 8505020157 | |
| Download: ML20116H292 (2) | |
Text
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f THE CLEVELAND ELECTR P.O. BOX 5000 - CLEVELAND OHIO 44101 - TELEPHONE (216) 622-9800 - ILLUMINATING BLDG. - 55 PUBLIC SQUARE Serving The Best Location in the Nation MURRAY R. EDELMAN VICE PRESIDENT NUCUAR April 18, 198$
Mr. James G. Keppler Regional Administrator, Region III Office of Inspection and Enforcement 799 Roosevelt Road Glen Ellyn, Illinois 60137 RE:
Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Collection of Condensate in the RCIC Steam Supply Line
[RDC 124(85)]
Dear Mr. Keppler:
This letter serves as our second interim report pursuant to 10CFR50.55(e) on the potential significant deficiency associated with the collection of condensate in the Reactor Core Isolation Cooling (RCIC) steam supply line.
Mr. J. McCormick-Barger of your office was notified on January 23, 1985, by Mr. T. A. Boss of the Cleveland Electric Illuminating Company (CEI) that this problem was being evaluated per our Deviation Analysis Report 220.
Our first interim report was filed with your office on February 21, 1985.
This report contains a description of the deficiency, actions planned to complete our evaluation, and the planned date for our next report.
Description of Deficiency Two locations exist in the Reactor Core Isolation Cooling (RCIC) steam header where condensate can collect.
One location is up-stream of the RCIC inboard isolation valve, lE51F063, and the other is in the steam supply line to the RHR Heat Exchangers, upstream of valves lE12F052A&B.
Upon initiation of RCIC, the inboard isolation valve opens allowing the condensate to flow and possibly damage the system piping.
If the steam condensing mode of RHR was desired, the heat exchanger inlet valves would open, allowing condensate to be introduced to the RHR heat exchanger, possibly damaging the tubes.
8505020157 850418 R
ADOCK 05000 o
S PR 2 21985 1 0 ]~La/
Mr. James G. Kcppler April 18, 1985 Comoletion of Evaluation Gilbert / Commonwealth, Inc. our Architect Engineer has completed their analysis to determine the poterMial effects of the conden-sate slug flow on the operation of the RCIC system.
We are currently analyzing.the safety implications of these effects and determining what corrective actions may be necessary to alleviate them.
We anticipate the final report on this subject to be submitted by May 17, 1985.
Please call if there are any additional questions.
Sincerely, Murray R. Edelman Vice President Nuclear Group MRE:sab cc:
Mr. J. A Grobe USNRC, Site Office (SBB50)
Mr. D. E. Keating USNRC, Site Office (SBB50)
Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555 Records Center, SEE-IN
. Institute of Nuclear Power Operations 1100 circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339 l
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