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Event Notification Report for March 27, 2018

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
03/26/2018 - 03/27/2018

** EVENT NUMBERS **


53273 53287 53288 53290 53291

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Non-Agreement State Event Number: 53273
Rep Org: RAPID CITY REGIONAL HOSPITAL
Licensee: RAPID CITY REGIONAL HOSPITAL
Region: 4
City: RAPID CITY State: SD
County:
License #: 40-00238-04
Agreement: N
Docket:
NRC Notified By: JAMES McKEE
HQ OPS Officer: DONG HWA PARK
Notification Date: 03/19/2018
Notification Time: 16:43 [ET]
Event Date: 03/08/2018
Event Time: [MDT]
Last Update Date: 03/19/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
Person (Organization):
JEREMY GROOM (R4DO)
NMSS EVENTS RESOURCE (EMAI)

Event Text

MEDICAL EVENT INVOLVING DELIVERED DOSE 50 PERCENT LESS THAN PRESCRIBED DOSE

A patient was prescribed 8 fractions of 500 cGy to the temple area. During the third fraction, the physician noticed the first two fractions were performed incorrectly. The first two fractions were performed with an incorrect setup, and the patient received less than 50 percent of the prescribed dose to the temple. The Radiation Safety Officer will provide a detailed written report after an investigation.

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: 53287
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: JOSEPH FRATTASIO
HQ OPS Officer: VINCE KLCO
Notification Date: 03/25/2018
Notification Time: 23:43 [ET]
Event Date: 03/25/2018
Event Time: 16:16 [EDT]
Last Update Date: 03/26/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
RAY MCKINLEY (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Cold Shutdown 0 Cold Shutdown

Event Text

CONTROL ROD DRIVE PIPING POTENTIALLY INOPERABLE

"On March 25, 2018 at 1616 hours [EDT], with the reactor in cold shutdown condition, two control rod drive piping lines were determined to be potentially inoperable in the event of a design basis earthquake due to support defects. The control rod drive piping forms a portion of the reactor coolant pressure boundary and primary containment boundary.

"The supports will be repaired prior to plant startup.

"This event had no impact on the health and/or safety of the public.

"The NRC Resident Inspector has been notified."

The licensee will notify the Commonwealth of Massachusetts.

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Power Reactor Event Number: 53288
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MATTHEW MILLER
HQ OPS Officer: DAVID AIRD
Notification Date: 03/26/2018
Notification Time: 11:51 [ET]
Event Date: 03/26/2018
Event Time: 10:58 [EDT]
Last Update Date: 03/26/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
STEVE ROSE (R2DO)

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

Event Text

TEMPORARY LOSS OF CONTROL ROOM ENVELOPE BOUNDARY

"At 1058 Eastern Daylight Time (EDT) on March 26, 2018, a Main Control Room (MCR) alarm was received for low control room positive pressure.

"At 1100 EDT, a Control Room Envelope (CRE) door was found ajar and immediately closed. Technical Specification 3.7.10, Control Room Emergency Ventilation System (CREVS), was declared not met for both trains and Condition B entered.

"At 1100 EDT on March 26, 2018, the alarm cleared, CREVS was declared operable and LCO [Limiting Condition for Operation] 3.7.10, Condition B was exited.

"The safety function of the CRE boundary is to ensure the in-leakage of unfiltered air into the CRE will not exceed the in-leakage assumed in the licensing basis analysis of Design Basis Accident (DBA) consequences to CRE occupants. From 1058 EDT to 1100 EDT, WBN [Watts Bar Nuclear] was unable to validate that CREVS could fulfill its required Safety Function.

"This event is being reported pursuant to 10 CFR 50.72(b)(3)(v)(D)."

The NRC Resident Inspector has been notified.

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Power Reactor Event Number: 53290
Facility: FARLEY
Region: 2 State: AL
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DOUGLAS HOBSON
HQ OPS Officer: DONALD NORWOOD
Notification Date: 03/26/2018
Notification Time: 18:19 [ET]
Event Date: 03/26/2018
Event Time: 13:38 [CDT]
Last Update Date: 03/26/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
STEVE ROSE (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Hot Standby 0 Hot Standby

Event Text

TECHNICAL SPECIFICATIONS REQUIRED SHUTDOWN DUE TO INOPERABLE MAIN STEAM ISOLATION VALVE

"On March 25, 2018 at 1833 CDT, while at 100 percent power, Farley Unit 1 (FNP-1) conservatively declared a single Main Steam Isolation Valve (MSIV) inoperable on the 1C Steam Generator line due to indication of Steam Generator pressure rise with a corresponding reduction in flow of that loop. FNP-1 began a reactor shutdown at 0400 CDT on March 26, 2018 to establish plant conditions to support testing the affected main steam line MSIVs while in the required action time of Technical Specification 3.7.2. At 1338 CDT on March 26, 2018, testing confirmed that the single MSIV was inoperable and that valve disassembly will be required. The duration of the valve repair would exceed the required action time of Technical Specification 3.7.2. This report is being made in accordance with 10 CFR 50.72(b)(2)(i), as a plant shutdown required by technical specifications.

"The licensee has notified the NRC Resident Inspector."

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Power Reactor Event Number: 53291
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CHARLES BROESCHE
HQ OPS Officer: DAVID AIRD
Notification Date: 03/26/2018
Notification Time: 20:07 [ET]
Event Date: 03/26/2018
Event Time: 18:39 [EDT]
Last Update Date: 03/26/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
STEVE ROSE (R2DO)

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

Event Text

TEMPORARY LOSS OF CONTROL ROOM ENVELOPE BOUNDARY

"At 1839 Eastern Daylight Time (EDT) on March 26, 2018, a Main Control Room (MCR) alarm was received for low control room positive pressure.

"At 1840 EDT, a Control Room Envelope (CRE) door was found ajar and immediately closed. Technical Specification 3.7.10, Control Room Emergency Ventilation System (CREVS), was declared not met for both trains and Condition B entered.

"At 1840 EDT on March 26, 2018, the alarm cleared, CREVS was declared operable and LCO [Limiting Condition for Operation] 3.7.10, Condition B was exited.

"The safety function of the CRE boundary is to ensure the in-leakage of unfiltered air into the CRE will not exceed the in-leakage assumed in the licensing basis analysis of Design Basis Accident (DBA) consequences to CRE occupants. From 1839 EDT to 1840 EDT, WBN [Watts Bar Nuclear] was unable to validate that CREVS could fulfill its required Safety Function.

"This event is being reported pursuant to 10 CFR 50.72(b)(3)(v)(D)."

A watch has been posted at the door to prevent recurrence.

The NRC Resident Inspector has been notified.

Page Last Reviewed/Updated Tuesday, March 27, 2018
Tuesday, March 27, 2018