ML20106B433

Deficiency Rept (Rdc 111 (84)) Re Lack of Test Spec Requirements for Operational Testing of Fuel Pool Gates,As Required by Reg Guide 1.68,Rev 2.Technical Review Underway. Final Rept Anticipated by 850228

ML20106B433
Person / Time
Site:	Perry
Issue date:	01/31/1985
From:	Edelman M CLEVELAND ELECTRIC ILLUMINATING CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
(RDC-111-(84)), NUDOCS 8502110608
Download: ML20106B433 (2)

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i '< e P o. box 5000 - CLEVELAND. oHlo 44101 - TELEPHONE (216) 622-9800 - ILLUMINATING BLOG. - 55 PUBLIC SQUARE Serving The Best Location in the Nation MURRAY R. EDELMAN VICE M4ESIDENT January 31, 1985 Mr. James G. Keppler Regional Administrator, Region III Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 RE: Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Fuel Pool Gates 4 Preoperational Test Requirements (RDC 111 (84))

Dear Mr. Keppler:

This report is being transmitted pursuant to 10CFR50.55(e) and concerns the lack of test specification requirements for preoperational testing of the Fuel Pool Gates as required in Regulatory Guide 1.68, Revision 2, 1978. Mr.

J. McCormick-Barger of your office was notified on August 13,1984 by Mr.

B. D. Walrath of the Cleveland Electric Illuminating Company that this problem was being evaluated by Deviation Analysis Report No. 194. The results of the evaluation are provided as follows:

The safety significance of the lack of specifications for the operability and leak testing of the sectionalizing device (Fuel Pool Gates) in the refueling canal and fuel storage pool has been evaluated and determined to be not re-portable per the criteria delineated in 10CFR50.55(e).

If the fuel pool gate seals had not been tested and we assume that during normal operation the installed gates leaked at an unacceptable rate, thc flow would be from one spent fuel pool to the transfer pool or to the cask pit area.

Under no conditions will the leakage result in the uncovering of spent fuel.

In addition, level instrumentation would alarm a low level condition and indicate the need to provide makeup water. Therefore, the omission of the test speci-fication requirement to confirm the leakage rates would not lead to a significant safety hazard.

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Mr. James G. K;ppler January 31, 1985 Although no safety significanco was determined for the aforementioned deficiency, the technical review of the test specifications is in process.

Additional time will be required to complete the study. These efforts j are anti-ipated to result in the issuance of a final report by February 28, l 1985.

Please call if there are any questions.

Sincerely, tim 5/%

MRE/jml Murray Edelman Vice President Nuclear Group cc: Mr. J. A. Grobe USNRC, Site Office Mr. D. E. Keating USNRC, Site Office Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 U. S. Nuclear Regulatory Commission c/o Document Management Branch Washington, D. C. 20555 Records Center, SEE-IN Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339