ML20154M593

Responds to Generic Ltr 88-05 Re Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary (Rpb) Components. Initiating & Documenting Evaluation of Abnormal Leakage Affecting Rpb Will Be Proceduralized by 880901

ML20154M593
Person / Time
Site:	Yankee Rowe
Issue date:	05/25/1988
From:	Drawbridge B YANKEE ATOMIC ELECTRIC CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
FYR-88-74, GL-88-05, GL-88-5, NUDOCS 8806020016
Download: ML20154M593 (2)

Text

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s Telephons (617) 872-8100 TWX 710-380-7619 YANKEE ATOMIC ELECTRIC COMPANY 1671 kVorcestor Road, Framingham, Massachusetts 01701 Yka m May 25, 1988 FYR 88-74 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

References:

(a) License No. DPR-3 (Docket No. 50-29)

(b) Letter, USNRC to YAEC, dated March 17, 1988

Subject:

Response to Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants (Generic Letter 88-05)

Dear Sir:

In response to F.eference (b), a review has been conducted of our procedures and programs for the control of boric acid leakage which could potentially affect the integrity of the reactor coolant pressure boundary.

Procedures and programs are in place and are adequate to ensure boric acid corrosion will not lead to degradation of the reactor coolant pressure boundary.

Proceduralized inspections of the accessible primary pressure boundaries i

inside containment are conducted biweekly during routine power operation for l

location of abnormal leakage. Special inspections, instituted as a result of l management review of leak rate monitoring data, are also conducted. Detailed, component level inspections are conducted as required by plant management during nonpower operation periods. Abnormal leakage located by these inspections is evaluated through a management process involving plant support staff using engineering instructions provided by the Yankee Nuclear Services Division. The evaluation and any required repairs are conducted in accordance with ASME,Section XI.

As a result of this review two areas for improvement have been noted.

The plant process of initiating and documenting the evaluation of abnormal leakage which could af f ect the reactor coolant pressure boundary will be proceduralized. This process will include initiating further corporate engineering evaluation for recurring leakage. In addition, the engineering l instruction governing design changes will be modified to more clearly outline the effect of boric acid solutions on carbon steel components. Each of these items will be complete by September 1, 1988.

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l 8806020016 880525 l PDR ADOCK 05000029 I P DCD \

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,e United States Nucicar Regulatory Commission May 25, 1988 i Page 2 E FYR 88-74 We trust that you will find this information satisfactory; however, should you have any questions. please contact us. 'j Very truly yours, Y EE ATOMI ELECTRIC COMPANY-l AWiw &

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, i B. L. Drawbridge Vice President and Manager of Operation =

p-BIS /25.613 COMMONWEALTH OF MASSACHUSETTS)

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MIDDLESEX COUNTY )

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Then personally appeared before me, B. L. Drawbridge, who, being duly sworn, did state that he is Vice President and Manager of Operations of Yankee

. Atomic Electric Company, that he is duly authorized to execute and file the i foregoing document in the name and on the behalf of Yankee Atomic Electric  ;

Company and that the statements therein are true to the best of his knowledge t and belief.  !

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Robert H. Groce Notary Public i My Commission Expires August 29, 1991 cc: USNRC Region I I i USNRC Resident Inspector YNPS i l

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