ML18079A014
| ML18079A014 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry, Cooper, Pilgrim, Brunswick  |
| Issue date: | 03/06/2018 |
| From: | Jeffrey Hamman Crane Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18079A014 (2) | |
Text
03-06-18;05:34PM;
[c~~N EJ NUCLEAR CRANE NUCLEAR, INC.
860 RE:MINGTON BOULEVARD March 6, 2018 Attn: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-001
- 12 FAX (6)0}226-4646 www.cro1\\anucfoar,i=
- om BOLINGBROOK, IL, 60440
Subject:
10 CFR Part 21 Notification of Defect on Crane Nuclear Figure Number 83 Y:i SPL I0"x8"x10" and 6"x4"x6" Bolted Bonnet Gate Valve This letter provides notification of a defect on Crane Nuclear Figure Number 83 ~ SPL 1 O"x8"xl O" and 6"x4"x6 valve components.
(i) Name and address of the individual or individuals informing the Commission.
Joyce Hamman Director, Safety and Quality Burt Anderson Site Leader Samson Kay Engineering Manager Crane Nuclear 860 Remington Blvd Bolingbrook, lL 60440
{ii) Identification of the basic component supplied for such facility or such activity Within the United States which may fail to comply or contains a potential defect, Crane Nuclear Figure Number 83 Yl SPL lO"xS"xlO" and 6"x4:x6" Bolted Bonnet Gate Valve (iii) Identification of the firm supplying the basic component which fails to comply or contains a
~ct Crane Nuclear, Inc.
860 Remington l3lvd Bolingbrook, IL 60440 (iv) Nature of the defect or failure to comply and the safety hazard which is created or could be created by.vuch defect or failure to comply A Crane Nuclear Figure Number 83 ~ SPL 10"x8"x10" Bolted Bonnet Gate Valve supplied to Duke Energy experienced a packing blowout on 12/17/17. Preliminary review of the packing design suggested that the packing clearances within the stuffing box were larger than standards specified by MSS-SP-120. Dimensions for parts such as the gland and stuffing box were based on drawings Crane Nuclear Figure Number 83 ~, which consolidates and tabulates dimensions needed to fabricate the parts based on stem dimensions. Review of the component drawings made for the Crane Nuclear Figure Number 83 !--S SPL l O"x8"xl O" and 6"x4"x6" Bolted Bonnet Gate Valve determined that the outside diameter of the gland for the 1 O"xS"xl O" and 6"x4"x6
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03-06-18;05:34PM; I CRAN EI NUCLEAR CRANE NUCLE:AR, INC.
860 REMINGTON 60ULEVARD
- 12 FMC. (6l0)226-4646 www.crn11cnuclcor.com I
BOLINGBROOK, IL 60440 I
I valves was incorrectly transcribed, resulting in an undersized condition :for the packaging gland and excess diametric clearance between the gland and stuffing box.
(v) The date on which the information of such defect or failure to compl/was obtained.
I Duke Energy's Brunswick facility notified Crane on 12/20/2017. Crane began research under Corrective Action Report 17-3 6 (Later Changed to 18-01) op. 12/22/18. *
(vi) In the case of a basic component which contains a defect or fails to comply, the number and location of these components in use at, supplied for, being supplied for. or may be supplied for, manufactured, or being manufactured for one or morefacilities or activities subject to the regulations in this part.
1 CNI Sales Order 33663 41030 41115 41619 43725 45441 4378 Valve Size 10x8xl0 10x8xl0 10x8x10 10x8x10 10x8x10 10x8x10 6x4x6 Licensee NPPD - Cooper Station (sold to Browns Ferry)
TV A-Browns Ferry TV A-Browns ferry NPPD - Cooper Station Duke Energy - Brunswick Duke Enerbry - Brunswick Entergy - Pilgrim (vii) The co"ective action which has been, is being, or will be taken: the name of the individual or organization responsible for the action; and the length of time that has been or will be taken to complete the action.
Drawings for Crane Nuclear Figure Number 83-1/2 SPL lO;'x8 11xlO and 6"x4"x6" valve components have been corrected. Additionally, notification is being made to each customer noted above.
(viii) Any advice related to the defect or failure ~o comply about the facility, activity, or basic component that has been, is being. or will be given to purchasers or licensees.
CNI Recommends that the gland be replaced to tighten clearances to meet MSS-SP-120 requirements.
(ix) In the case of an early site permit, the entities to whom an early site permit was tr,m~f(!.rred.
Not applicable.
Should you have any questions regarding this matter, please contact me, Joyce Hamman, Director, Safety & Quality at (678) 451-2280, Burt Anderson, Site Leader, at (630) 226-4990, or Samson Kay, Engineering Manager at (630) 226-4983.
- Regards, oyceHamman Director, Safety & Quality Crane Nuclear; lnc.
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