Source: https://www.nrc.gov/reading-rm/doc-collections/event-status/event/2016/20160901en.html
Timestamp: 2020-03-28 14:38:25
Document Index: 429707419

Matched Legal Cases: ['art 21', 'ART 21', 'art 21', 'art 21', 'ART 21', 'art-21']

NRC: Event Notification Report for September 1, 2016
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Event Notification Report for September 1, 2016
52074 52197 52199 52210 52212 52213 52214
Part 21 Event Number: 52074
Rep Org: TEAM CORPORATE
Licensee: FURMANITE
NRC Notified By: EDWARD RICH
PART 21 REPORT - MATERIALS NOT PROPERLY DEDICATED
The following information was excerpted from the email received from Team Corporate:
"It was discovered during an internal audit that a Line Stop Fitting manufactured at the Furmanite Dixie Drive location and ordered from the Furmanite Charlotte location for nuclear work at Browns Ferry did not have material properly dedicated.
"Completion of the [engineering] evaluation [to determine if safety is compromised] to be complete by August 31, 2016.
A review of all safety related nuclear orders was performed and only the ones listed below are affected:
Browns Ferry - Part number SF-0615-STD for TVA Job 256-MH-131067 (Tee fitting, blank flange, gasket, studs and nuts)
Turkey Point - Part number CUS1301044-DWG-01, CUS1304019-DWG-01and CUS1304073-DWG-01(Leak Sealing cup, restraints, and enclosures) for FL&P job numbers 101-LS-104669, 101-LS-401085, and 101-LS-401142 respectively
Catawba - Part number CUS1505165-DWG-01for Duke Energy Job 101-LS-403182 (Gamma plug enclosure, studs and nuts)
POC: Edward Rich - Director of Quality
200 Herman Drive
(281) 388-5567
* * * UPDATE AT 0950 EDT ON 08/31/16 FROM EDWARD RICH TO JEFF HERRERA * * *
The following is an excerpt from an email received from Team Corporate:
Team Corporate determined that the affected orders where the materials were not dedicated as required only applied to the TVA orders. All other orders it was determined material was purchased from a supplier that operated an approved 10 CFR 50 App B Quality Program.
Notified the R2DO (Bartley) and Part 21/50.55 Reactors (via E-mail).
Power Reactor Event Number: 52210
HQ OPS Officer: MARK ABRAMOVITZ Notification Date: 08/30/2016
2 A/R Y 98 Power Operation 0 Hot Standby
A fault occurred on the unit 2 "B" main bank transformer resulting in an oil fire. The main turbine tripped resulting in a reactor trip. All control rods fully inserted and no safety or relief valves lifted. Decay heat is being removed via steam dumps to the main condenser and feeding steam generators with auxiliary feedwater. Electrical power is through the normal shutdown electrical lineup.
"On August 30, 2016, at 2110 EDT, Watts Bar Nuclear Plant Unit 2 reactor tripped due to an electrical fault affecting the 2B Main Bank Transformer, resulting in a fire in the transformer.
"Concurrent with the reactor trip, the Auxiliary Feedwater system actuated as designed.
"All Control and Shutdown rods fully inserted. All safety systems responded as designed. The unit is currently stable in Mode 3, with decay heat removal via Auxiliary Feedwater and main steam dump systems. Unit 2 is in a normal shutdown electrical alignment.
"The fire was out at 2230 EDT. The cause of the fire is currently under investigation.
"The fire was reported at 2149 EDT. Local Fire Departments responded to the site as requested.
"The reactor trip and system actuation is being reported under 10CFR50.72(b)(3)(iv)(A) and 10CFR50.72 (b)(2)(iv)(B).
"There was no effect on WBN Unit 1.
"The NOUE was exited at 2342.
Part 21 Event Number: 52212
NRC Notified By: WADE SHEPHARD
PART 21 NOTIFICATION - FLOWSERVE SWING CHECK VALVES
The following is an excerpt of the part-21 notification:
"Susquehanna Nuclear reported two size 3 class 900 Anchor Darling swing check valves were not passing LLRT [local leak rate tests]. After disassembly there appeared to be wear between the hinge arm and seat ring of the valve body apparent on the hinge. The interference was not severe enough to stop hinge arm motion of the disk, but did affect ability of the valve to seal during LLRT."
Affected Serial Numbers: BQ752, BQ753, and BO809
Affected Sites: Ginna, Diablo Canyon, Brunswick, Davis Besse, Kewaunee, Conn Yankee, Monticello, Susquehanna, Framatome, Chin Shan, and Kuosheng
Engineering Evaluation 10CFR21 No. 91
POC: Wade Shephard: 919-832-0525
Power Reactor Event Number: 52213
"This 4-hour and 8-hour notification is being made to report that Salem Unit 2 had an unplanned automatic reactor trip and automatic actuation of the auxiliary feedwater system. The trip occurred due to the loss of the 21 reactor coolant pump [RCP] resulting in a reactor trip on low reactor coolant flow. The 21 RCP remains unavailable. The cause of the loss of the 21 reactor coolant pump is unknown at this time.
"All control rods inserted on the reactor trip. All emergency core cooling systems and engineered safety feature systems functioned as expected. The auxiliary feed pumps started as expected.
"Salem Unit 2 is currently in Mode 3. Reactor coolant system pressure is at 2235 psig and temperature is 547 degrees Fahrenheit with decay heat removal via the main steam dumps and auxiliary feedwater systems. Unit 2 has no active technical specification action statements in effect requiring a lower mode of operation due to the transient.
"The 21 and 22 containment fan coil units (CFCU) were out of service for surveillance testing prior to the event. There was no major secondary equipment tagged for maintenance prior to the event. There were no personnel injuries as a result of this event.
"Normal offsite power is available to the site. There is no effect on Unit 1."