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Event Notification Report for September 8, 2016

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
09/07/2016 - 09/08/2016

** EVENT NUMBERS **


52211 52224 52225 52226

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Agreement State Event Number: 52211
Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: MEADWESTVACO
Region: 1
City: COVINGTON State: VA
County:
License #: 580-375-1
Agreement: Y
Docket:
NRC Notified By: CHARLES COLEMAN
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 08/31/2016
Notification Time: 13:33 [ET]
Event Date: 08/30/2016
Event Time: [EDT]
Last Update Date: 08/31/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY POWELL (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

AGREEMENT STATE REPORT - DAMAGED PROCESS NUCLEAR GAUGE

The following report was received via fax:

"On August 30, 2016, the licensee's Radiation Safety Officer reported that two cap screws used to secure the shutter handle on a fixed gauge (Ohmart Model SH-F2-C; serial number 70929; 1000 milliCuries cesium-137) had sheared off during a routine test of the on-off mechanism earlier in the day. The failure left the shutter in the on or open position. The gauge is used to provide density measurements of product traveling through a stainless steel pipe and is normally left in the on position. Personnel entry into the pipe is not possible, eliminating potential personnel exposure to radiation. The licensee has contacted a licensed service company to repair the gauge."

Virginia Report: VA-16-013

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Power Reactor Event Number: 52224
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: ERIK SILKO
HQ OPS Officer: DONALD NORWOOD
Notification Date: 09/07/2016
Notification Time: 16:47 [ET]
Event Date: 09/06/2016
Event Time: 13:47 [EDT]
Last Update Date: 09/07/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
MEL GRAY (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 100 Power Operation

Event Text

NON-ESSENTIAL SERVICE WATER HEADER DECLARED INOPERABLE

"At 1347 EDT on September 6, 2016, the non-essential service water header was declared inoperable due to what appeared to be a leak on a filet weld on a slip-on flange upstream of the 23 service water pump discharge valve SWN-2-2. [Operators] entered LCO 3.0.3 based on Engineering input with no code case to support an immediate determination of operability. The 23 service water pump was secured and the discharge valve SWN-2-2 was closed isolating the leak and restoring the non-essential SW header to operable status. With the discharge valve closed, LCO 3.0.3 was exited at 1417 EDT on September 6, 2016. The declaration of the inoperability of the non-essential service water header is considered a loss of safety function for purposes of reporting under 10 CFR 50.72(b)(3)(v). Further investigation of the leak revealed [that the leak had occurred at] a pipe flaw rather than at the weld location. An operability evaluation is ongoing. There was no reduction in power while in LCO 3.0.3 and no other issues arose."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 52225
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: SEAN DUNFEE
HQ OPS Officer: JEFF ROTTON
Notification Date: 09/08/2016
Notification Time: 04:27 [ET]
Event Date: 09/08/2016
Event Time: 03:00 [CDT]
Last Update Date: 09/08/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
THOMAS HIPSCHMAN (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 82 Power Operation

Event Text

TECHNICAL SPECIFICATION SHUTDOWN DUE TO LOSS OF RESIDUAL HEAT REMOVAL PUMP

"On September 4, 2016 at 0258 [CDT], Grand Gulf Nuclear Station entered three [Technical Specification] Limiting Conditions for Operations (LCOs) due to residual heat removal pump 'A' (RHR 'A') being declared inoperable.

"LCOs entered:
1) 3.5.1 for one low pressure ECCS injection/spray subsystem,
2) 3.6.1.7 for one RHR containment spray subsystem, and
3) 3.6.2.3 for one RHR suppression pool cooling subsystem.

"Station management has made the decision to shutdown the plant to repair the RHR 'A' pump prior to the end of the 7 day LCO completion time based on troubleshooting and testing performed on the RHR 'A' pump.

"Grand Gulf Nuclear Station initiated plant shutdown required by Tech Spec Actions 3.5.1, 3.6.1.7, and 3.6.2.3, at 0300 CDT on 09/08/2016 due to expected inability to restore RHR 'A' to operable status prior to exceeding the LCO time of 7 days."

The unit is currently at 82 percent power. There are no other systems out of service that would complicate the orderly shutdown to Mode 4.

The licensee will notify the NRC Resident Inspector.

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Power Reactor Event Number: 52226
Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: MIKE JONES
HQ OPS Officer: DANIEL MILLS
Notification Date: 09/08/2016
Notification Time: 04:27 [ET]
Event Date: 09/07/2016
Event Time: 21:31 [MST]
Last Update Date: 09/08/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
THOMAS HIPSCHMAN (R4DO)

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

Event Text

MANUAL REACTOR TRIP DUE TO STUCK OPEN PRESSURIZER MAIN SPRAY VALVE

"On September 7th, 2016 at approximately 2131 Mountain Standard Time (MST), Palo Verde Unit 1 was manually tripped due to a stuck open main spray valve. Unit 1 was operating at 100 percent power at normal operating temperature and pressure prior to the event. A 120 VAC non-class instrument distribution panel was being transferred to its alternate power supply to establish maintenance conditions. The distribution panel failed to transfer. The panel remained energized from its normal power supply; however, multiple components powered from the distribution panel began to exhibit uncharacteristic behavior. At this time, it was noted that a reactor coolant system main spray valve was open. The alarm response procedure was followed; however, the actions taken were unsuccessful at closing the main spray valve. The plant was then manually tripped due to pressurizer pressure continuing to lower. The reactor coolant pumps were turned off to terminate main pressurizer spray flow to control pressurizer pressure due to the inability to close the main spray valve. No ESF [Engineered Safety Features] actuations occurred and none were required. No emergency classification was required per the emergency plan. Safety related buses remained energized during and following the reactor trip. The emergency diesel generators did not start and were not required. The offsite power grid is stable. Limiting condition for operation 3.4.1 was entered due to low pressurizer pressure. No major equipment was inoperable prior to the event that contributed to the event.

"Unit 1 is stable at normal operating temperature and pressure in Mode 3. Reactor coolant pumps are secured and natural circulation has been verified. Primary pressure is being maintained at its normal operating pressure manually with pressurizer heaters and auxiliary spray, from the charging system. The event did not result in any challenges to fission product barriers and there were no adverse safety consequences as a result of this event. The minimum RCS pressure was approximately 2070 psia (normal 2250). The event did not adversely affect the safe operation of the plant or the health and safety of the public."

All rods inserted and the trip was uncomplicated. Units 2 and 3 were not affected and continue to run at full power.

The NRC Resident Inspector has been notified.

Page Last Reviewed/Updated Thursday, September 08, 2016
Thursday, September 08, 2016