ML19256E279

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Requests Description of Acoustic Emission Leak Detection Sys Supporting Proposed Augmented Inservice Insp for Pipe Rupture Protection.Info Needed by 800201 in Order to Meet Scheduled Fuel Load Date of May 1980
ML19256E279
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 10/22/1979
From: Baer R
Office of Nuclear Reactor Regulation
To: Parker W
DUKE POWER CO.
References
REF-GTECI-A-42, REF-GTECI-PI, TASK-A-42, TASK-OR NUDOCS 7911020048
Download: ML19256E279 (4)


Text

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g UNITED s TATEs 8 'j ') y, g NUCLEAR REGULATORY COMMISSION 3 g /y g

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OCT 2 : 1979 Docket Nos. 50-369 and 50-370 Mr. William O. Parker, Jr.

Vice President, Steam Production Duke Power Company P. O. Box 2178 422 South Church Street Charlotte, North Carolina 28242

Dear Mr. Parker:

SUBJECT:

AUGMENTED ISI FOR PIPE RUPTURE PROTECTION - ACOUSTIC LEAK DETECTION SYSTEM (McGuire Nuclear Station, Units 1 and 2)

During our meeting with you on January 18, 1979 you agreed to provide an acoustic emission leak detection system as an adjunct to your proposed augmented inservice inspection for pipe rupture protection. As you know, we require that final design of the system including a description of the proposed acceptance standards and plant corrective action be submitted for our approval three months prior to ini-tial fuel loading and that the leak detection system be fully operational prior to exceeding if. power. The plant corrective action should clearly define the steps that will be taken upon receipt of an alarm from the acoustic leak detection system. Based on your current fuel load date of May 1980, we expect to receive this information no later than February 1,1980. Your letter of March 22, 1979, Position 3 Response, however indicated that this information would be provided by June 15, 1979. On August 31, 1979 as Attachment 6, some additional informa-tion was provided which we consider to be insufficient as a basis to accept this portion of your proposed augnented ISI.

We believe that the acoustic emission leak detection system should be able to detect very small leaks as early as possible to permit reactor shutdown and mini-mize the possibility of developing a critical crack length. We need to know the lower limits of acoustic leak detectability including the minimum leak crack size the system will detect, response time and how this crack size compares to the

- critical crack length for the piping. The instrumentation must be discussed more fully regarding acceptance standards and setpoints. Until this information is provided, we will be unable to complete our evaluation of the McGuire milestone Number 6.

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r. r.'i ll i ara 0. Pa rker, J r. riithin seven days of receipt of this letter, please nctify us when ycu plar. to respond to this natter.

Si ncerely, A:&&(.

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Robert L. Baer, Chief Light Water Reactcrs Branch No. 2 Division of Project Management ccs:

See r. ext pages 1257 231

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Mr. W. L. Porter Cui;e Power Ccapany F. O. Box 2178 422 South Church Street Charlotte, North Carolina 28242 Mr. R. S. Howarc

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' estinghouse Electric Corporation F. O. Ecx 355 Pittsburgh, Pennsylvania 15230 Mr. E. J. Keith EDS Nuclear Incorporated 220 Mcntgomery Street San Francisco, California 94104 Fr. J. E. Houghtaling NUS Corporation 2536 Countryside Boulevard Clearwater, Florida -33515 Mr. Jesse L. Riley, President The Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207 J. Michael McGarry, III, Esq.

Cebevoise & Liberman 1200 Jeventeenth Street, N. W.

..ashington, D. C.

20036 Rchert M. Lazo, Esq., Chairman Atcmic Safety and Licensing Board U. S. Nuclear Regulatory Ccanission

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7.ctural Fescurces Defense Council 917 - 15th Street, N. W.

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20555 F.ichard P. Wilscn, Esq.

A:sistant Attorney General State of South Carolina 2500 Bull Street Columbia, South Carolina 29201 O

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