ML100610346

Part 21 Potential Defective Stud Attachment to Embedded Plates

ML100610346
Person / Time
Site:	Oconee
Issue date:	02/24/2010
From:	Severance S Dubose National Energy Services
To:	Brian Bonser, Dong Park Office of Nuclear Reactor Regulation, NRC/NSIR/DPR/DDIR/OB, NRC/RGN-II
References
45722
Download: ML100610346 (4)

Text

02/24/2010 U.S. Nuclear Regulatory Commission Operations Center Event Report General Information or Other (PAR)

PaEne I Event#

45722 Rep Org: OCONEE NUCLEAR STATION Notification Date / Time: 02/24/2010 14:44 (EST)

Supplier: DUBOSE NATIONAL ENERGY SERVICES, INC.

Event Date / Time: 02/17/2010 06:32 (EST)

Last Modification: 02/24/2010 Region:

1 Docket #:

City: SENECA Agreement State:

Yes County:

License #:

State:

SC NRC Notified by: SANDRA SEVERANCE Notifications: BRIAN BONSER R2DO HQ Ops Officer: DONG HWA PARK PART 21 GROUP EMAIL Emergency Class: NON EMERGENCY 10 CFR Section:

21.21 UNSPECIFIED PARAGRAPH POTENTIALLY DEFECTIVE STUD ATTACHMENT TO EMBEDED PLATES "On February 17, 2010, Duke Energy (Duke) completed a reportability determination which concluded that a defect associated with Nelson Stud attachment to embed plates is reportable under Part 21. The embed plates with Nelson studs were procured safety-related from DuBose National Energy Services, Inc. (DuBose) on December 18, 2008. Receipt of the material began as early as August 1, 2009. When delivered to the on-site storage location, it was identified that a Nelson Stud was missing from one of the plates. Follow-up investigation and evaluation identified that automatically timed stud welding procedures/process control weaknesses in the areas of cleanliness and operator/equipment performance have resulted in cold weld joints and weld failures. Duke will provide follow up written notification within 30 days pursuant to Part 21.21 (d)(3)(ii).

"Initial Safety Significance: None. The potentially defective embedded plates installed in the Protected Service Water (PSW) Building prior to this discovery have not been placed into service. These plates will be removed, abandoned, or re-engineered prior to placing the system in service. However, the embed plates described were to be used for a variety of QA Condition 1 functions, including reaction points for PSW Building structural steel framing and support/restraint of PSW electrical equipment. Depending upon the installation location of these embedded plates and the number and location of ineffectively attached Nelson studs, this deviation could have created a substantial safety hazard were it to remain uncorrected.

"Corrective Action(s):

"1. Notified vendor (DuBose).

"2. Re-work all embeds by installing a fillet weld on each stud.

"3. Determine whether the installed embeds will be removed, abandoned, re-engineered.

The licensee notified the NRC Resident Inspector.

02/24/2010 U.S. Nuclear Regulatory Commission Operations Center Event Report Page 2 General Information or Other (PAR)

Event #

45722

"-4,

.002

.02/24/10 14:43 FAX 2869 UNIT 1 & 2 CONTROL ROOM

-4 NRC Attachment B NRC Event Notification Worksheet OMP 1-14 Page 2 of 2 Event Description (Include systems affected, actuations and their initiating signals, causes, effect of event on plant, actions taken or planned, etc.)

Event: On February 17, 2010, Duke Energy (Duke) completed a reportability determination which concluded that a defect associated with Nelson Stud attachment to embed plates is reportable under Part 21. The embed plates with Nelson studs were procured safety-related from DuBose National Energy Services, Inc. (DuBose) on December 18, 2008. Receipt of the material began as early as August 1, 2009. When delivered to the on-site storage location, it was identified that a Nelson Stud was missing from one of the plates. Follow-up investigation and evaluation identified that automatically timed stud welding procedures/process control weaknesses in the areas of cleanliness and operator/equipment performance have resulted in cold weld joints and weld failures. Duke will provide follow up written notification within 30 days pursuant to Part 21.21(d)(3)(ii).

Initial Safety Significance: None. The potentially defective embedded plates installed in the Protected Service Water (PSW) Building prior to this discovery have not been placed into service. These plates will be removed, abandoned, or re-engineered prior to placing the system in service. However, the embed plates described were to be used for a variety of QA Condition I functions, including reaction points for PSW Building structural steel framing and support/restraint of PSW electrical equipment. Depending upon the installation location of these embedded plates and the number and location of ineffectively attached Nelson studs, this deviation could have created a substantial safety hazard were it to remain uncorrected.

Corrective Action(s):

1. Notified vendor (DuBose).

2. Re-work all embeds by installing a fillet weld on each stud.

3. Determine whether the installed embeds will be removed, abandoned. or re-enineered Anything unusual or not understood?

D Yes (Explain above) 0 No Did all systems function as required?

[

Yes IE No (Explain above)

Mode of operations until corrected: N/A JEstimated restart date: N/A eDoes event result in a radiological release, RCS leak, or steam generator tube Eli Yes (complete page 3)

No

ýleak?

Does the event result in any of the units experiencing a L

Yes (complete Oconee Plant Status sheet) _FM

ýtransient?

N Notifications NRC Resident:/trl~w r (S

! N/will be lant Manager:

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Notified By:-

Time: 't Y5 State(s):

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Date/Time:

NRC Notification Complete by Caller/NRC Communicator:

Date/Time:

Received at: 02/24/2010 14:42 02/24/1.0.

14:42 FAX 2869 UNIT 1 & 2 CONTROL ROOM 4 NRC Z001 I

Attachment B NRC Event Notification Worksheet OMP 1-14 Page 1 of 2 NRC Event Notification Worksheet Notification Timc Facility or Organization Unit Caller's Name Call Back #

Oconee Nuclear Station 1, 2, 3 Sandra Severance ENS 256-9931 (864) 873-3466 I

NRC Operations Officer Contacted:

NRC Event Number:

I Event Time/Zone

.Event Date I

Power/Mode Before P ower/Mode Aftr 0632 EST 2/17/2010 N1 N/A Event Classifications Li General Emergency L1 Site Area Emergency ni Alert 0i El EL1 Unusual Event 50.72 Non-emergency (see other columns) 72.75 Spent Fuel (ISFSI) 73.71 Physical Security Transportation 20.2202 Material/Exposure 26.73 Fitness for Duty Other: Part 21.21(d)(3)(i) 8-Hour Non-Emergency 10 CFR 50.72 (b) (3)

[E (ii) (A) Degraded Condition

[I (ii) (B) Unanalyzed Condition L] (xiii) Loss of emergency assessment capability/offlsite communications Li (iv) (A) System Actuation Li RPS Li Containment isolation E] ECCS Li EFW EL Containment spray/coolers E] Emergency AC (Keowee Hydro)

Li (v) (A) Safe Shutdown Capability Li (v) (B) Residual Heat Removal Capability EL (v) (C) Control of radiological material Li (v) (D) Accident Mitigation Li (xii) Transport contaminated person to offsite medical facility J-Hour Non-emergency 10 CFR 50.72 (b)(1)

Li Deviation from TS per 50.54(x) 4-Hour Non-Emergency 10 CFR 50.72 (b)(2)

Li (i) TS Required Shutdown Li (iv) (A) ECCS Discharge into RCS EL (iv) (B) RPS Actuation (while critical)

Li (xi) News release/notification to other government agencies