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Event Notification Report for December 18, 2017

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/15/2017 - 12/18/2017

** EVENT NUMBERS **


53038 53109 53121 53122 53123 53124

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 53038
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: DAVID W. BURRUS
HQ OPS Officer: HOWIE CROUCH
Notification Date: 10/26/2017
Notification Time: 18:18 [ET]
Event Date: 10/26/2017
Event Time: 14:45 [CDT]
Last Update Date: 12/15/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
RAY AZUA (R4DO)

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

BOTH DIVISIONS OF DRYWELL VACUUM RELIEF DECLARED INOPERABLE

"At 1055 [CDT], drywell purge supply/initial vacuum relief 1E61F003B was declared INOPERABLE for Drywell Vacuum Relief System while performing a monthly surveillance. 1E61F003B is a Division II powered valve. Division 1 Emergency Diesel Generator is INOPERABLE due to a tagout. At 1455, under LCO 3.8.1.B.2 the station declared both divisions of Drywell Vacuum Relief INOPERABLE. GGNS [Grand Gulf Nuclear Station] identified that a loss of Safety Function occurred due to a loss of two 10-inch vacuum relief lines from the Drywell required by Technical Specification 3.6.5.6 and therefore could have prevented fulfillment of its safety function. That event is being reported under 10CFR50.72(b)(3)(v)(D), as 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 mitigate the consequences of an accident. "

Both divisions inoperable has placed the plant in a 72-hr. LCO shutdown action statement.

The licensee has notified the NRC Resident Inspector.

* * * RETRACTION FROM RALPH FLICKINGER TO HOWIE CROUCH AT 1643 EST ON 12/15/17 * * *

"At 1055 [CDT on 10/26/17], Drywell purge supply/initial vacuum relief 1E61F003B was declared INOPERABLE for Drywell Vacuum Relief System while performing a monthly surveillance. 1E61F003B is a Division II powered valve. Division 1 Emergency Diesel Generator was INOPERABLE due to a tagout. At 1455 [CDT on 12/26/17], under LCO 3.8.1.B.2, the station declared both divisions of Drywell Vacuum Relief INOPERABLE. GGNS identified that a loss of Safety Function occurred due to a loss of two 10-inch vacuum relief lines from the Drywell required by Technical Specification 3.6.5.6 and therefore could have prevented fulfillment of its safety function.

"This was initially reported under 10 CFR 50.72(b)(2)(v)(D). Div. 1 EDG was initially taken out of service at 1455 on 10/26 for preplanned maintenance (OP-EVAL). It was subsequently declared INOPERABLE-INOP due to a visible flaw indication in the exhaust manifold (1117 on 10/27). A subsequent Maintenance Functional Failure Evaluation and Past Operability Determination concluded the diesel was capable of performing its intended function for the required mission time, and therefore met the definition of OPERABLE.

"NUREG-1022 provides clarification for 10 CFR 50.72(b)(2)(v). NUREG Section 3.2.7, paragraph 4, states '...unless a condition is discovered that would have resulted in the system [otherwise] being declared inoperable, reports are not required when systems are declared inoperable solely as a result of Required Actions for which the bases is the assumption of an additional random single failure (i.e., . ..LCO 3.8.1, 'AC Sources Operating,' Required Actions .., B.2, or C.1). Per ACTION 3.8.1 .B.2, both trains of Drywell vacuum and Drywell Purge were inoperable for the purposes of Tech Specs. However, the normal power supply was available to Division 1 and there were no conditions which would have rendered the Division 1 diesel inoperable. Therefore, per Section 3.2.7 of NUREG-1022, this was not a Loss of Safety Function and was not reportable under 50.72(b)(2)(v)(D)."

The licensee has notified the NRC Resident Inspector.

Notified R4DO (Deese).

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Agreement State Event Number: 53109
Rep Org: KANSAS DEPT OF HEALTH & ENVIRONMENT
Licensee: INTEGRA TECHNOLOGIES
Region: 4
City: WICHITA State: KS
County:
License #: GL
Agreement: Y
Docket:
NRC Notified By: JAMES UHLEMEYER
HQ OPS Officer: VINCE KLCO
Notification Date: 12/08/2017
Notification Time: 17:26 [ET]
Event Date: 12/08/2017
Event Time: 15:20 [CST]
Last Update Date: 12/08/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
THOMAS HIPSCHMAN (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)
ILTAB (EMAI)

This material event contains a "Less than Cat 3 " level of radioactive material.

Event Text

AGREEMENT STATE REPORT - LOST POLONIUM SOURCE

The following information was excerpted from an email received from the State of Kansas:

The licensee is reporting that an ionizer containing a radioactive source (Model Number P-2063-1000) was lost. The licensee currently has 3 other ionizers of the same model. The device radioactive source was Polonium-210 (SN: A2KT674) with an activity of 31.5 mCi and was last leak tested on 9/20/2016. The device was checked out by the licensee and placed within the secure test floor while testing electrical devices at the Integra Technologies facility. The missing device use was last logged on 8/25/2017. The licensee believes that their maintenance department mistakenly threw the device away. Upon discovering that the device was missing, the licensee searched their facility several times over without finding the device. The prevention for further loss is that the remaining 3 units will be mounted in permanent locations using security screws so they cannot be removed by unauthorized personnel.

THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

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Part 21 Event Number: 53121
Rep Org: SOR MEASUREMENT AND CONTROL
Licensee: SOR MEASUREMENT AND CONTROL
Region: 4
City: LENEXA State: KS
County:
License #:
Agreement: Y
Docket:
NRC Notified By: MELANIE DIRKS
HQ OPS Officer: JEFF HERRERA
Notification Date: 12/15/2017
Notification Time: 18:02 [ET]
Event Date: 10/18/2017
Event Time: [CST]
Last Update Date: 12/15/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
Person (Organization):
RICK DEESE (R4DO)
PART 21/50.55 REACTO (EMAI)
ART BURRITT (R1DO)
BINOY DESAI (R2DO)
ANN MARIE STONE (R3DO)

Event Text

PART 21 - DEVIATION IN ORIGINAL QUALIFICATION TESTING OF SOR SAFETY RELATED SWITCHES

The following is a excerpt from a report received via email:

"On October 18, 2017 a deviation in the original qualification testing of SOR safety-related switches was discovered by a NRC vendor inspection conducted from October 16-20, 2017. SOR continues to evaluate those items cited by NON 99900824/2017-201-01 Items 1 through 3 and other effects on safety related components identified by SOR.

"The qualification test report was written in 1992. Due to the age of the report, SOR continues to retrieve records and consult contracted sources. The evaluation is expected to be completed as soon as possible or by February 27, 2018.

"If you have any questions regarding this matter, please contact:
Mike Bequette,
Vice President of Engineering
Email: mbequette@sorinc.com
Tel 913-956-3040"

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General Information Event Number: 53122
Rep Org: EXELON NUCLEAR CORPORATE
Licensee: EXELON NUCLEAR CORPORATE
Region: 3
City: WARRENVILLE State: IL
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DAVID GULLOTT
HQ OPS Officer: ANDREW WAUGH
Notification Date: 12/16/2017
Notification Time: 08:10 [ET]
Event Date: 12/15/2017
Event Time: 14:30 [CST]
Last Update Date: 12/16/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
ANN MARIE STONE (R3DO)
FFD GROUP (EMAI)

Event Text

CORPORATE INDIVIDUALS REMOVED FROM THE FITNESS FOR DUTY RANDOM POOL

"On 12/15/17 at 1430 [CST], it was discovered by corporate Fitness for Duty (FFD) personnel that two individuals in the Corporate Emergency Response Organization (ERO) and one Corporate FFD Authorization (FFDA) individual were removed from the random FFD testing pool by the security database, Illuminate. It was identified that a database coding error removed the FFD random pool flag when an additional clearance was requested for these individuals. The individuals involved did not have Unescorted Access (UA) or Unescorted Access Authorized (UAA).

"Review by corporate FFD personnel and the security database vendor (Endevor) found this coding error affected only those individuals not holding UA/UAA but who require additional clearances which require being in the FFD random pool (e.g., ERO, FFDA). Corporate security personnel found no other individuals to be affected by this issue. No individuals with UA/UAA are affected by this issue.

"Affected individuals have been added to the FFD random pool and pre-access testing will be performed for the three identified individuals prior to resuming duties requiring inclusion in the FFD random pool. A code modification for the security database has been created to prevent error recurrence, testing has begun with implementation targeted for Monday 12/18/17. Quarterly reviews will continue to take place for verification purposes.

"The issue does not affect any Exelon Sites or the process for granting UA/UAA.

"No other utilities are known to use the Illuminate security database."

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Power Reactor Event Number: 53123
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: ALAN SCHULTZ
HQ OPS Officer: ANDREW WAUGH
Notification Date: 12/17/2017
Notification Time: 05:48 [ET]
Event Date: 12/17/2017
Event Time: 03:16 [EST]
Last Update Date: 12/17/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
BINOY DESAI (R2DO)

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

HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM DECLARED INOPERABLE

"On December 17, 2017, at 0316 Eastern Standard Time (EST) the Unit 2 HPCI system was isolated and declared inoperable due to a packing failure of the HPCI Turbine Steam Supply Valve (i.e., 2-E41-F001). Isolation of the HPCI system due to the packing failure prevents the HPCI system from performing its design safety function. As such, this event is being reported in accordance with 10 CFR 50.72(b)(3)(v)(D) as a condition that at the time of discovery could have prevented the fulfillment of the safety function of a system that is needed to mitigate the consequences of an accident.

"Unit 2 HPCI system has been isolated and depressurized. The HPCI system will remain inoperable until the valve can be repaired.

"The safety significance of this condition is minimal. All other Emergency Core Cooling Systems (ECCS) and the Reactor Core Isolation Cooling (RCIC) system remain operable.

"This event did not result in any adverse impact to the health and safety of the public."

The NRC resident inspector has been notified.

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Power Reactor Event Number: 53124
Facility: GINNA
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: KIERAN REYNOLDS
HQ OPS Officer: BETHANY CECERE
Notification Date: 12/17/2017
Notification Time: 11:56 [ET]
Event Date: 12/17/2017
Event Time: 07:55 [EST]
Last Update Date: 12/17/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
ART BURRITT (R1DO)

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

OFFSITE NOTIFICATION FOLLOWING SULFRIC ACID SPILL

"Ginna notified New York State Department of Environmental Conservation of a sulfuric acid spill of approximately 270 gallons in the AVT, All Volatile Treatment, building. Ginna is currently contacting offsite support for hazardous chemical cleanup. The spilled sulfuric acid is currently contained within the secondary containment structure associated with the sulfuric acid tank. There is no release to the environment. There is no impact to habitability in the AVT building at this time."

The licensee notified the NRC Resident Inspector.

Page Last Reviewed/Updated Monday, December 18, 2017
Monday, December 18, 2017