ML20027B378
| ML20027B378 | |
| Person / Time | |
|---|---|
| Site: | Perry, 05000000, 05000550, 05000551 |
| Issue date: | 09/09/1982 |
| From: | Davidson D CLEVELAND ELECTRIC ILLUMINATING CO., COMMONWEALTH EDISON CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19289B220 | List: |
| References | |
| NUDOCS 8209200385 | |
| Download: ML20027B378 (2) | |
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THE CLEVELAND ELECTRIC ILLUMIN ATING COMPANY P o Box 5000 m CLEVELAND. oHlo 44101 m TELEPHONE (216) 622-9800 e ILLUVINATING BLOG e 55 PUBLIC SOUARE Serving The Best Location in the Nation D;lwyn R. Davidson VICE PRESIDENT sysuu :noinumno ano CONSTRUCTION September 9,1982 Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 SER Outstanding Issues No. 3 Reactor Internals Vibration Prototype Test Program
Dear Mr. Schwencer:
This letter and its attachments are provided in response to the Perry SER outstanding issue number 3 regarding reactor internals vibration prototype test program (SER ref.3.9.2.3). Specific elements of Regulatory Guide 1.20 to be addressed in the pro-gram are: (1) analytical predictions of internals vibration levels; (2) instrumentation fo vibration monitoring; (3) testing procedures and extent of visual inspection; and (4) resolution of past BWR problems, such as degradation cf feedwater spargers, fuel channel box wear, and jet pump holddown beams.
The General Electric program for BWR/6 class plants, which addresses items (2) and (3), was described in a letter dated April 24, 1978, from Mr. Glenn Sherwood, GE to Mr. Edson Case, NRC (MFN/169/78) (Attachment 1). This program includes the vibration measurement and inspection program to be conducted during preoperational and initial startup testing for prototype and non-prototype plants in accordance with Regulatory Guide 1.20.
A draf t copy of the report NEDE-22203, " Reactor Internals Vibration Predictions,"
is provided as Attachment 2.
This report describes the GE reactor internals vibration program and provides peak amplitude predictions based on engineering analysis and prototype test results to address item (1). A finalized report will be submitted in October 1982. This report contains GE proprietary information and we request that it be handled as proprietary in accordance with 10CFR2.790.
The resolution of past BWR problems, item (4), such as degradation of feedwater spargers, fuel channel box wear, and jet pump holddown beams have been addressed in other CEI responses and are considered resolved in SER sections 3.9.3.1,4.2.3.1(5),
TBDI and 3.9.5 respectively.
820 9 20 0 MS ( E r
Mr. A. Schwencer September 9,1982 The feedwater spargers used at Perry are the improved interference fit triplesleeve design. Detailed information is provided in the GE Topical Report NEDE-21821, which satisfies the requirements in NUREG-0619, "BWR Feedwater Nozzel and Control Rod Drive Return Line Nozzle Cracking."
Fuel channel box wear is noted as a license condition for Perry. It was addressed as a Licensing Review Group (LRG-II) generic issue 3-CPB. A program for measuring channel box deflection through channel location monitoring and friction tests was presented in a letter dated May 17,1982 from D. Holtzscher, LRG-II, to H. J. Faulkner, NRC.
Finally, CEI has committed to reduce the preload on jet pump holddown beams and perform periodic inservice inspections to resolve this issue.
We believe that this letter and its attachments should resolve the outstanding issue of reactor internals vibration program in the next Perry Supplementary Safety Evaluation Report (SSER No. 2).
Very truly yours, Dalwy
. Davidson Vice P esident System Engineering and Construction DRD:kd cc: Jay Silberg, Esq.
John Stefano Max Gildner D. Terao D. Shen i
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