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Event Notification Report for August 05, 2019

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
8/2/2019 - 8/5/2019

** EVENT NUMBERS **


54184 54197 54198 54199

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Agreement State Event Number: 54184
Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: WEST PENN ALLEGHENY HEALTH SYSTEMS INC
Region: 1
City: PITTSBURGH   State: PA
County:
License #: PA-0031
Agreement: Y
Docket:
NRC Notified By: JOSHUA MYERS
HQ OPS Officer: JEFFREY WHITED
Notification Date: 07/26/2019
Notification Time: 14:34 [ET]
Event Date: 07/25/2019
Event Time: 00:00 [EDT]
Last Update Date: 07/26/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MEL GRAY (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - SOURCE FAILED TO RETRACT

The following was received via e-mail:

"On Thursday, July 25, 2019, the licensee called to report an equipment failure event where, during a cardiovascular brachytherapy treatment, the source failed to retract at the end of the treatment time due to a kink in the catheter line. The unit being used was a Best Vascular, Inc., A1000 Series using the Novoste Beta-Cath 3.5 Delivery System and a Sr-90 source with a source strength of 79.3 mCi. A service engineer for Best Vascular was present during the time of treatment and was able to unkink the catheter line allowing the source to fully retract into the unit. There was no harm to the patient and no overexposure occurred."

Event Report No.: PA190017

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: 54197
Facility: CLINTON
Region: 3     State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DAVID LIVINGSTON
HQ OPS Officer: HOWIE CROUCH
Notification Date: 08/03/2019
Notification Time: 06:47 [ET]
Event Date: 08/03/2019
Event Time: 02:26 [CDT]
Last Update Date: 08/04/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(A) - ECCS INJECTION
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
PATRICIA PELKE (R3DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 98 Power Operation 0 Hot Shutdown

Event Text

AUTOMATIC REACTOR SCRAM ON LOW REACTOR WATER LEVEL

"At 0226 [CDT], an automatic scram on low reactor water level occurred due to a trip of the 'B' Reactor Feed pump. All control rods fully inserted. Reactor water level 2 was reached and the High Pressure Core Spray system, Reactor Core Isolation Cooling system, Division 3 diesel generator, Standby Gas Treatment Systems 'A' and 'B' and all shutdown safety related service water pumps started as expected. Reactor Core Isolation Cooling and High Pressure Core Spray injected as expected. All level 2 containment isolation signals occurred as expected and all level 2 containment valves closed as expected. Reactor water level is currently being controlled in band by condensate. Reactor pressure is being maintained by main turbine Bypass Valves.

"This event is being reported under 10 CFR 50.72(b)(2)(iv)(A), for ECCS discharge to RCS; 10 CFR 50.72(b)(2)(iv)(B), for RPS actuation, and 10 CFR 50.72(b)(3)(iv)(A), for specified system actuation.

"The NRC Senior Resident Inspector has been notified."

No safety relief valves lifted during the transient. The plant is in a normal shutdown electrical lineup with all safety equipment available. The licensee notified the Illinois Emergency Management Agency per their communications protocol.

* * * UPDATE FROM DAVID LIVINGSTON TO HOWIE CROUCH AT 0321 EDT ON 8/4/19 * * *

"Following automatic initiation of the High Pressure Core Spray (HPCS) System as described above, the HPCS System was manually secured following station procedures after verification that additional RPV [reactor pressure vessel] injection was no longer required. Securing HPCS injection in this manner prevents automatic restart of the system in the event of a subsequent low RPV level condition, rendering it inoperable. As the HPCS system is considered a single train safety system, this meets the reportability requirements of 10 CFR 50.72(b)(3)(v)(D). This reportable condition was identified following review of post-scram actions. The HPCS system has been restored to a Standby lineup."

The licensee will be notifying the NRC Resident Inspector.

Notified R3DO (Pelke).

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Power Reactor Event Number: 54198
Facility: HOPE CREEK
Region: 1     State: NJ
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: STEVEN BIER
HQ OPS Officer: HOWIE CROUCH
Notification Date: 08/03/2019
Notification Time: 23:33 [ET]
Event Date: 08/03/2019
Event Time: 19:47 [EDT]
Last Update Date: 08/04/2019
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):
FRED BOWER (R1DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 37 Power Operation 0 Hot Shutdown

Event Text

MANUAL REACTOR TRIP AND MANUAL ACTUATION OF REACTOR CORE ISOLATION COOLING

"At 1947 [EDT] on 8/3/19, with Hope Creek in Mode 1 at 37 percent power, the reactor was manually scrammed due to loss of condenser vacuum. All control rods fully inserted into the core. All safety systems responded as designed and expected. Reactor level was stabilized using Reactor Core Isolation Cooling (RCIC) and Reactor Feedwater Pumps.

"Currently reactor water level is being maintained by the feedwater system and decay heat is being removed by the main condenser using the main turbine bypass valves. Due to the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B). Due to the manual actuation of RCIC, this event is also being reported as an eight-hour, non-emergency notification per 10 CFR 50. 72(b )(3)(iv)(A).

"There was no impact on the health and safety of the public or plant personnel.

"The NRC Resident Inspector has been notified."

The plant is in its normal shutdown electrical lineup with all safe shutdown equipment available. The licensee will be notifying the state of Delaware, state of New Jersey and the Lower Alloway Creek township.

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Power Reactor Event Number: 54199
Facility: NINE MILE POINT
Region: 1     State: NY
Unit: [1] [] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: JOE BLAKELEY
HQ OPS Officer: HOWIE CROUCH
Notification Date: 08/05/2019
Notification Time: 01:28 [ET]
Event Date: 08/04/2019
Event Time: 17:45 [EDT]
Last Update Date: 08/05/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
Person (Organization):
FRED BOWER (R1DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 89 Power Operation

Event Text

AVERAGE POWER RANGE MONITORS DECLARED INOPERABLE

"On August 4, 2019 at 1745 [EDT], Reactor Recirculation Pump (RRP) 11 tripped. The cause for the trip is under investigation.

"Following the RRP trip, the Average Power Range Monitors (APRMs) flow bias trips are inoperable due to reverse flow through RRP 11. The APRMs were restored to operable on August 4, 2019 at 1807, when the RRP 11 Discharge Blocking Valve was closed.

"This 8-hour non-emergency report is being made based upon requirements of 10CFR50.72(b)(3)(v)(A) which states: 'Licensee shall notify the NRC of any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to: (A) Shut down the reactor and maintain it in a safe shutdown condition.'"

The licensee has notified the NRC Resident Inspector.


Page Last Reviewed/Updated Monday, August 05, 2019
Monday, August 05, 2019