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Event Notification Report for June 30, 2017

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
06/29/2017 - 06/30/2017

** EVENT NUMBERS **


52487 52816 52833

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Part 21 Event Number: 52487
Rep Org: CURTISS WRIGHT ELECTRO MECHANICAL C
Licensee: WESTINGHOUSE ELECTRIC CORPORATION
Region: 1
City: CHESWICK State: PA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JAY GARDINER
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 01/13/2017
Notification Time: 13:56 [ET]
Event Date: 01/12/2017
Event Time: [EST]
Last Update Date: 06/29/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
Person (Organization):
SCOTT SHAEFFER (R2DO)
PART 21/50.55 REACT (EMAI)

Event Text

PART 21 INTERIM REPORT - EXCESS MATERIAL CONDITION ON THE CASING FOR THE AP1000 REACTOR COOLANT PUMP

The following summary was excerpted from report #EMD-GM-17-02, provided by the Curtis-Wright Electro-Mechanical Corporation:

"Curtiss-Wright Electro-Mechanical Corporation (CW-EMD) has identified a condition which is currently being evaluated to determine if a significant safety hazard exists in the casing for the AP1000 Reactor Coolant Pump (RCP). The investigation is underway, but will not be completed within the required 60 days from discovery as required by paragraph 21.21(a)(1) of the regulation. This submission constitutes CW-EMD's interim report on the condition in accordance with paragraph 21.21(a)(2) of the regulation.

"Casings for the AP1000 Reactor Coolant Pump. The casings have an excess material condition in the transition region between the cast bowl and the suction nozzle. The condition is a discontinuous (non-tangential) axisymmetric feature between the cast bowl region and machined suction nozzle OD. The as-built transition feature on the casings has not been analyzed and is not included in CW-EMD Engineering Memorandum 7242, Revision 1, Volume 1, which is the applicable generic design report for the AP1000 RCP casing and main closure.

"At present, the following domestic deliveries have been made:
- 8 casings have been provided to V.C. Summer Units 2 and 3.
- 8 casings have been provided to Vogtle Units 3 and 4.

"Name and address of the individual or individuals informing the Commission:
Brian W. Eckels, General Manager
Curtiss-Wright Electro-Mechanical Corporation
1000 Wright Way Cheswick, Pa 15024"

* * * UPDATE AT 1238 EDT ON 06/29/17 FROM JAY GARDINER TO JEFF HERRERA * * *

The following update was received via email:

"Curtiss-Wright Electro-Mechanical Corporation (CW-EMD) submitted an interim report concerning a deviation in the AP1000 Reactor Coolant Pump casing via letter EMD-GM-17-02, dated January 12, 2017. This letter updates the status of the investigation.

"1. Extent of condition evaluation has been completed. CW-EMD has confirmed that the discontinuous (non-tangential) axisymmetric feature between the cast bowl region and machined suction nozzle OD is limited (domestically) to the 8 AP1000 RCP casings delivered to V.C. Summer units 2 & 3.

"2. AP1000 RCP casing stress and fatigue supplemental analyses have been performed to assess the excess material condition discovered on the suction nozzle OD. The deviation has been determined to still satisfactorily meet the pressure boundary stress requirements of the ASME Code and can therefore be accepted as-is.

"3. The analysis included generation of a 2D axisymmetric FEA [Finite Element Analysis] of the casing with a bounding representation of the as-built geometry, based on extraction of cross-sectional profiles from the V.C. Summer laser scan data of 2 casings. The 2D FEA was used to determine the stress concentration factor(s) associated with the as-built deviated feature, enabling a fatigue strength reduction factor to be estimated and applied to the existing 3D FEA casing fatigue (nominal design) analysis.

"4. The maximum fatigue usage at the location of the deviation on the casing suction nozzle was conservatively estimated to increase from 0.287 to 0.633. This condition still satisfies the 1.0 usage limit specified in the ASME Code.

"5. Therefore, this deviation does not constitute a substantial safety hazard, and the condition has been determined to be not reportable under the provisions of Title 10 Code of Federal Regulations, Part 21."

Notified the R2DO(Bartley) and Part 21 Group (via email).

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Agreement State Event Number: 52816
Rep Org: UTAH DIVISION OF RADIATION CONTROL
Licensee: UNIVERSITY OF UTAH, RADIOLOGICAL HEALTH DEPT
Region: 4
City: WEST JORDAN State: UT
County:
License #: UT 1800231
Agreement: Y
Docket:
NRC Notified By: SPENCER WICKHAM
HQ OPS Officer: BETHANY CECERE
Notification Date: 06/21/2017
Notification Time: 13:51 [ET]
Event Date: 06/19/2017
Event Time: [MDT]
Last Update Date: 06/21/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
VINCENT GADDY (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

AGREEMENT STATE REPORT - DOSE DELIVERED TO SITE ADJACENT TO INTENDED TARGET

The following State of Utah report was received by email:

"The licensee delivered a 500 cGy fraction of HDR [High Dose Rate] brachytherapy to a site adjacent to the intended target. This treatment was a supplemental boost to external beam radiotherapy, and the mistreated volume was included in the target volume of the external beam plan."

The State of Utah was notified of the event on June 21, 2017 by electronic mail opened at 1125 MDT.

Utah Event Report ID No: will be provided in follow up report.

A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.

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Power Reactor Event Number: 52833
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: BETH DALICK
HQ OPS Officer: JEFF HERRERA
Notification Date: 06/29/2017
Notification Time: 12:43 [ET]
Event Date: 06/29/2017
Event Time: 08:57 [EDT]
Last Update Date: 06/29/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
JONATHAN BARTLEY (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 100 Power Operation 0 Hot Standby

Event Text

AUTOMATIC TRIP DUE TO A LOSS OF NORMAL FEEDWATER FLOW TO B STEAM GENERATOR

"On 6/29/2017 at 0857 [EDT], VC Summer Nuclear Station automatically tripped due to a loss of normal feed water flow to the B Steam Generator.

"There were no complications with the trip. All control rods fully inserted. All emergency feedwater pumps automatically started and recovered steam generator levels.

"The plant is stable in Mode 3. Station personnel are investigating the cause of the loss of normal feedwater to the B Steam Generator. This is reportable per 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A).

"The NRC Resident Inspector has been notified."

The licensee notified the State of South Carolina as well as Fairfield, Lexington, Richland and Newberry Counties regarding the event.

Page Last Reviewed/Updated Friday, June 30, 2017
Friday, June 30, 2017