IR 05000259/1986007

Discusses Items Noted in Insp Repts 50-259/86-07, 50-260/86-07 & 50-296/86-07.IE Info Notice 85-056 Also Pointed Out Need for Dry lay-up Processes to Prevent Stainless Steel Corrosion of RCPB

ML20203D569
Person / Time
Site:	Browns Ferry
Issue date:	04/15/1986
From:	Olshinski J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	White S TENNESSEE VALLEY AUTHORITY
References
IEIN-85-056, IEIN-85-56, NUDOCS 8604220196
Download: ML20203D569 (2)

Text

{{#Wiki_filter:.-- Q [L4.* gpg15 @ Tennessee Valley Authority ATTN: Mr. S. A. White Manager of Nuclear Power 6N 38A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 , Gentlemen:

l SUBJECT: DOCKET NOS. 50-259, 50-260, AND 50-296 NRC regulation 10 CFR 50.34(b)(6)(ii) requires licensees to maintain managerial and administrative controls to assure that 10 CFR 50, Appendix B, Criterion XIII is met. Crit 9rion XIII relates to preservation of material and equipment during storag All licensees were recently reminded of these requirements by IE Information Notice No. 85-56.

During a recent routine inspection of the Browns Ferry Plant, attention was ! focused on the vulnerability of the systems that constitute the reactor coolant l pressure boundary during the current extended outag It is difficult to ' establish quantitatively the extent to which degradation has occurred while the three units have been in wet lay-u However, it is known that corrosion of stainless steel and, especially, carbon steel is accelerated in the presence of oxygenated water or in humid environments.

l When this concern was discussed during the inspection, the inspector was informed i that a study of alternative techniques had just been completed and that the study concluded that- dry lay-up processes appeared to be advantageous. We are aware j that dry lay-up, through the use of desiccation and/or dehumidifiers, has already j been used at other nuclear power plants to prevent corrosion during extended i outages.

l Although this matter was brought to the attention of plant management and has been discussed in Inspection Report No. 86-07, I considered it advisable to use this letter to inform you also. Because of the significance of the potential deterioration of the reactor coolant pressure boundary, I urge that increased and expedited attention be given to evaluating and reviewing as appropriate the lay-up conditions that are now in effect at the Browns Ferry plan

Sincerely, ! John A. Olshinski Deputy Regional Administrator for TVA cc: (See page 2)

^
[[

G lO 31,c /

     .__ Tennessee Valley Authority  2 cc: W. C. Bibb, Browns Ferry Nuclear Plant Site Director (/ R. L. Lewis, Plant Manager f . W. Whitt, Director, Nuclear Managers Review Group VD. L. Williams, Jr. , Supervisor
 , Licensing Section vR. E. Rogers, Project Engineers bec:VJ. N. Grace v41. R. Denton, NRR vfi. L. Thompson, NRR v0. M. Taylor, IE d. B. Hayes, 01 vR. J. Clark, Licensing Project Manager, NRR
 /S.R.Connelly,OIA RC Resident Inspector ocument Control Desk ytateofAlabama
, '

l R RII RII RII, _

(d y ##eeertoceii4nsce 35 //86 sr o,e,reiiig&

3/7,/86 3/ff/86 p/ /86 t' /( /86 I l L-----_---------- }}