05000373/LER-1983-146, Updated LER 83-146/03X-1:on 831109,local Leak Rate for Inboard Feedwater Check Valves 1B21-F010A/B Exceeded Tech Spec.Caused by Gaps on Perimeter of Disc Seal Matl. Manufacturer Supplying One Piece seals.W/840313 Ltr

Updated LER 83-146/03X-1:on 831109,local Leak Rate for Inboard Feedwater Check Valves 1B21-F010A/B Exceeded Tech Spec.Caused by Gaps on Perimeter of Disc Seal Matl. Manufacturer Supplying One Piece seals.W/840313 Ltr

ML20087N078
Person / Time
Site:	LaSalle
Issue date:	02/21/1984
From:	Diederich G, Dus R COMMONWEALTH EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
LER-83-146-03X, LER-83-146-3X, NUDOCS 8404030083
Download: ML20087N078 (4)

LER-2083-146, Updated LER 83-146/03X-1:on 831109,local Leak Rate for Inboard Feedwater Check Valves 1B21-F010A/B Exceeded Tech Spec.Caused by Gaps on Perimeter of Disc Seal Matl. Manufacturer Supplying One Piece seals.W/840313 Ltr

Event date:
Report date:
3732083146R00 - NRC Website

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sysNT OasCn PTtON AND PROSASLE CONSEQUENCES h I g l On Nov. 9,1983, with Unit-1 shutdown for a planned outaae. Local Leak Rate Tests were It was determined thatt g , performed on the inboard feedwater check valves (1821-F010A/B).

the Tech. Spec. 3.6.1.2. limit of .6 La (231.4 SCFH) was exceeded. The Feedwater lines]

the requirements of Aopendix J [

g g still have two isolation valves in each'line which meet _

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l were identified that would have prevented the discs from closing squarely against the g

Th,e Mfr. is supplying LSU with "one piece" seals, & the alignment problems are J

[ seal. Other corrective action outlined in confi rmatory letter f rom J. Keppler I being resolved.

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.a .o I. LER NUMBER: 83-146/03X-1

11. LASALLE COUNTY STATION: Unit 1 Ill. DOCKET NUMBER: 050-373 IV. EVENT DESCRIPTION:

On November 9, 1983, with Unit One shutdown for a planned outage, Local Leak Rate Tests were performed on the inboard feedwater check valves (1821-F010A/B).

It was determined that the Technical Specification 3.6.1.2 Limit of .6 La (231.4 SCFH) was exceeded.

V. PROBABLE CONSEQUENCES OF THE OCCURRENCE:

The feedwater lines still have two isolation valves in each line which meet the requirements of Appendix J to 10CFR50 criteria as containment isolation valves. .

The feedwater lines between the inboard and outboard check valves as well as the valves themselves are specially designed and constructed in accordance with Standard Review Plan 3.6.2-10 and ASME Section 3, so as to preclude the possibility of a credible line break between the check valves. Therefore, it is believed that the check valves would serve their original procured function of preventing a significant loss of vessel inventory in the event of a feed-water line break.

It is, therefore, believed that no immediate safety hazards existed, and that the plant was maintained in a safe condition at all times.

VI. CAUSE:

The subject valves are tilting disc check valves manufactured by the Anchor Darling Company. It was determined that the excessive leakage was a result of gaps found on the perimeter of the disc seal material, one aboutTheseone-half gaps inch long and the other about one and one half inches in length.

It was also noticed appeared at the seam, or " vulcanized", points of the seal.

that one of the seal's material appeared to be hardened slightly with multiple minute cracks, in addition, alignment problems were identified that would have prevented the discs from closing squarely against the seal.

Vll. CORRECTIVE ACTION:

Immediate action was taken to repai r the valves. The valve manufacturer (Anchor-Darling) is now supplying LSCS with new molded (one piece) seals as was used in the original design. Also, a representative of the Anchor-Darling Co.

has been on-site to resolve the alignment problems. ,

As of 11-3 CF83, an acceptable Local Leak Rate Test had been performed on 1821-F010B after a molded (one piece) seal was installed and the disc to hinge pin horizontal clearance was adjusted to within Anchor-Darling speci-

' fications. . Work is progressing on 1B21-F010A to install a molded seal and

• *

• LER NUMBER: 83-146/03X-1 Vll. CORRECTIVE ACTION (Cont'd):

and to make more critical adjustments of the vertical positioning of the disc assembly with Anchor Darling Specifications. 1821-F010A will be Local Leak Rate Tested when the above vnrk is completed prior to startup.

Additional corrective actions to assure that the seal failures Aincourse theseofvalves have been identified and the problems corrected are underway.

action to procure and install qualified seals in accordance with the require-

' ments of Appendix B of'10CFR Part 50 are outlined in a Confirmatory Action Letter dated 11/28/83 from J. Keppler (NRC) to C. Reed (Ceco).

Prepared by: Randy S. Dus 9

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f^N Commonw;cith Edison

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) RuralRoute #1 Box 220LaSalle County Nuclear Station (t ___

-s 7 Marseilles,il!inois 61341

( / Telephone 815/357-6761 March 13, 1984 James G. Keppler Regional Administrator Region lil U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137

Dear Sir:

Reportable Occurrence Report #83-146/03X-1 Docket #050-373 is being submitted to your office to supersede previously submitted Reportable Occurrence Report

1. 83-146/03L-0, in accordance with NUREG-0161, " Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File"; General Instruction No. 3 f-G. J. Diederich Superintendent LaSalle County Station l

GJD/GW/sjc Enclosure cc: Di rector of Inspection & Enforcement Director of Management Information & Program Control U.S. NRC Document Management Branch INP0-Records Cen ter l File /NRC l

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