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Event Notification Report for November 3, 2016

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
11/02/2016 - 11/03/2016

** EVENT NUMBERS **


52222 52317 52318 52340 52342 52343

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 52222
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MIKE BRUMMITT
HQ OPS Officer: STEVEN VITTO
Notification Date: 09/03/2016
Notification Time: 12:47 [ET]
Event Date: 09/03/2016
Event Time: 09:02 [EDT]
Last Update Date: 11/02/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
RAY POWELL (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 60 Power Operation 60 Power Operation

Event Text

UNIDENTIFIED LEAKAGE GREATER THAN TECHNICAL SPECIFICATIONS

"At 0902 EDT, on September 3, 2016, a leak developed from 13 Charging Pump seals that resulted in an unidentified leak rate of 1.3 gpm. Salem Unit 1 entered Technical Specification 3.4.6.2.b for unidentified leakage greater than 1 gpm. The Technical Specification requires the leak rate to be restored to below 1 gpm in a 4 hour period or place the Unit in Hot Standby in the next 6 hours and Cold Shutdown within the following 30 hours. In addition there is an allowable total ECCS leakage outside of Containment value of 0.45 gpm associated with Control Room habitability to comply with GDC-19 [General Design Criteria] limits. 12 Charging Pump was placed in service and 13 Charging Pump was removed from service and isolated. The unidentified leak rate lowered to below the 0.45gpm requirement for the total ECCS leakage outside of containment and the Technical Specification value of 1 gpm.

"This event is being reported under the requirements of 10CFR50.72(b)(3)(ii)(B) as 'the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety' for exceeding the 0.45gpm total ECCS leakage allowable in accordance with GDC-19 limitations.

"The Licensee has notified the NRC Resident and the Lower Alloways Creek Township."


* * * RETRACTION FROM MATT MOG TO STEVEN VITTO ON 11/02/2016 AT 0916 EDT * * *

"The purpose of this notification is to retract event report number 52222 made on 09/03/2016 at 1247 (EDT). Previously PSEG reported that Salem Unit 1 was in an unanalyzed condition due to a leak from the 13 Charging Pump seals exceeding the 0.45 gpm limit for total ECCS leakage outside containment associated with the Control Room Habitability analysis.

"A subsequent engineering evaluation determined that the post-accident ECCS leak rate from the 13 Charging Pump seals that would have existed is 0.33 gpm. This is within the limits of the existing Control Room Habitability analysis and no unanalyzed condition existed.

"Therefore, PSEG is retracting the notification made under 10 CFR 50.72(b)(3)(ii)(B).

"The NRC Resident Inspector was notified of this retraction by the licensee."

Notified R1DO (Schroeder).

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Agreement State Event Number: 52317
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: ALBEMARLE CATALYSTS LP
Region: 4
City: PASADENA State: TX
County:
License #: 01743
Agreement: Y
Docket:
NRC Notified By: ARTHUR TUCKER
HQ OPS Officer: STEVEN VITTO
Notification Date: 10/25/2016
Notification Time: 15:53 [ET]
Event Date: 10/25/2016
Event Time: [CDT]
Last Update Date: 10/25/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

AGREEMENT STATE REPORT - NUCLEAR GAUGE STUCK SHUTTER

The following was received from the State of Texas via email:

"On October 25, 2016, the Agency [Texas Department of State Health Services] was notified by the licensee that while preparing to leak test a VEGA Americas, Inc. model SH-F1 nuclear gauge the shutter on the gauge could not be fully closed. Open is the normal operating position of this gauge. The gauge contains a 60 millicurie (original activity) cesium-137 source. The gauge is on the third floor of a vessel and does not present a exposure hazard to workers or members of the general public. The licensee has contacted a service provider to repair the gauge. Additional information will be provided as it is received in accordance with SA-300."

Texas Incident #: I 9434

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Non-Agreement State Event Number: 52318
Rep Org: HEMLOCK SEMICONDUCTOR CORPORATION
Licensee: HEMLOCK SEMICONDUCTOR CORPORATION
Region: 3
City: HEMLOCK State: MI
County:
License #: 21-32682-01
Agreement: N
Docket:
NRC Notified By: KELLY DEERING
HQ OPS Officer: STEVEN VITTO
Notification Date: 10/25/2016
Notification Time: 16:00 [ET]
Event Date: 10/25/2016
Event Time: 07:00 [EDT]
Last Update Date: 10/25/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
PATTY PELKE (R3DO)
NMSS_EVENTS_NOTIFIC (EMAI)

Event Text

SOURCE HOLDER STUCK SHUTTER

"At approximately 0700 EDT, October 25, 2016, the RSO [Radiation Safety Officer] and Assistant RSO attempted to open the shutter on source holder 10071961 (Hemlock identifier), while preforming routine maintenance. The shutter operation failed, the shutter is stuck in the closed position. There were no exposures as a result of the failed shutter operation. Operating the shutter was part of a routine preventative maintenance plan. The process is currently shut down, therefore this incident caused no loss of production. The source holder is located on site. Hemlock Semiconductor Operations is in contact with Vega Americas, the manufacturer."

Vega America Source Holder Model SHF 2-B
Radionuclide: Cesium 137 - 800mCi
Source holder serial number: 13544057

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Power Reactor Event Number: 52340
Facility: FARLEY
Region: 2 State: AL
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: PHIL MITCHELL
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 11/01/2016
Notification Time: 19:01 [ET]
Event Date: 11/01/2016
Event Time: 17:43 [CDT]
Last Update Date: 11/02/2016
Emergency Class: ALERT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
MIKE ERNSTES (R2DO)
CATHY HANEY (R2)
BRIAN MCDERMOTT (NRR)
BERN STAPLETON (IRD)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 2 Startup 2 Startup

Event Text

ALERT DECLARED AT FARLEY UNIT 1 DUE TO AMMONIA EXCEEDING IDLH LEVELS IN THE AUXILIARY BUILDING

"At 1743 CDT on 11/1/16, readings were obtained that indicated ammonia above IDLH [Immediately Dangerous to Life and Health] values in the Unit 1 Auxiliary Building and an Alert was declared by the Emergency Director. The plant is stable with Unit 1 at 2% power. Unit 2 is at 100% power [and stable]. The site is currently investigating to determine the source and ventilate the area."

The licensee has informed the NRC Resident Inspector.

Notified DHS SWO, FEMA Ops Center, USDA Ops Center, HHS Ops Center, DOE Ops Center, DHS NICC Watch Officer, EPA EOC, FEMA National Watch Center (email), FDA EOC (email), Nuclear SSA (email).


* * * UPDATE FROM BLAKE MITCHELL TO STEVEN VITTO ON 11/02/2016 AT 0443 EDT * * *

"The following is the Emergency Preparedness 8-hour report for the Plant Farley ALERT declaration. An ALERT was declared at 1743 CDT on November 1, 2016, based on Emergency Action Level (EAL) HA3 (Release of toxic, asphyxiant, or flammable gases within vital areas which jeopardizes operation of systems required to maintain safe operations or establish or maintain safe shutdown) due to an ammonia discharge into the Auxiliary Building. Farley Unit 1 was in Mode 2 at 2 percent power and Unit 2 was in Mode 1 at 100 percent power throughout the event.

"Actions completed during and leading up to termination from the event included walkdown of the area to locate the ammonia source, and isolating the ammonia source while atmospheric monitoring was performed in all affected and adjacent areas. Installation of additional ventilation fans was completed. This event has been entered into the Farley Corrective Action Program under Condition Report 10293519 (Ammonia levels in 100 Feet Radside).

"A review of the Alert classification has determined that the classification was timely and accurate. All required notifications were completed accurately and in a timely manner. The ERO [Emergency Response Organization] notification system functioned as expected and all emergency response facilities were activated in a timely manner. There were no missing or injured personnel during the event. There is no evidence of tampering or sabotage of plant equipment leading to this event."

At 2202 CDT on 11/1/2016, the ammonia source was identified as Valve N1P20V913. At 2228 CDT, the ammonia source was isolated. Final assessment of the Auxiliary Building showed that the ammonia levels were less than 5 ppm. It was determined that a deficiency in the valve component was the cause of the ammonia leak.

The Alert was terminated on 11/1/2016 at 2340 CDT.

The Licensee has notified the NRC Resident Inspector.

Notified R2DO(Ernstes), IRD (Stapleton), NRR EO (Miller).

Notified DHS SWO, FEMA Ops Center, USDA Ops Center, HHS Ops Center, DOE Ops Center, DHS NICC Watch Officer, EPA EOC, FEMA National Watch Center (email), FDA EOC (email), Nuclear SSA (email).

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Power Reactor Event Number: 52342
Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: GREG MILLER
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 11/02/2016
Notification Time: 15:05 [ET]
Event Date: 11/02/2016
Event Time: 10:34 [EDT]
Last Update Date: 11/02/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
ROBERT DALEY (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 97 Power Operation 97 Power Operation

Event Text

UNANALYZED CONDITION FOR CONTROL ROD DROP ACCIDENT AT LOW POWER

"On November 2, 2016, while performing a re-evaluation of the radiological consequences of the Fermi 2 control rod drop accident (CRDA), DTE Electric Company (DTE) identified a non-conservatism in the current Fermi 2 design and licensing basis of the CRDA. As described in the Updated Final Safety Analysis Report (UFSAR) Section 15.4.9, the current design and licensing basis assumes that the post-CRDA release pathway consists of carryover with steam to the turbine condenser. The re-evaluation has identified that a forced release from the gland seal exhausters (GSEs) could also occur which could result in post-CRDA radiological consequences that exceed the current 10 CFR 100.11 offsite dose limits and Standard Review Plan 6.4 (General Design Criterion 19) main control room dose limits when operating at low power conditions.

"The unanalyzed condition described above only applies to low power operating conditions (i.e. less than 10% power) since the fuel damage postulated as a result of a CRDA is only credible under low power operating conditions when an individual control rod worth is high. Fermi 2 is currently at 97% power and, therefore, the plant condition is currently bounded by the design and licensing basis such that the condition currently does not exist and no immediate actions are required.

"However, Fermi 2 has operated at low power levels several times in the past three years. Those periods of operation at low power represent unanalyzed conditions that significantly degraded plant safety since the occurrence of a CRDA during those periods could have resulted in offsite and main control room doses exceeding regulatory limits. Therefore, this 8-hour notification is being reported in accordance with 10 CFR 50.72(b)(3)(ii)(B). There was no adverse impact to public health and safety or to plant employees.

"The licensee has notified the NRC Resident Inspector."

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Power Reactor Event Number: 52343
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: THOMAS YURKON
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 11/02/2016
Notification Time: 15:35 [ET]
Event Date: 11/02/2016
Event Time: 08:45 [EDT]
Last Update Date: 11/02/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
DAN SCHROEDER (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 70 Power Operation 70 Power Operation

Event Text

RESIDUAL HEAT REMOVAL VALVE INOPERABLE FOR CONTAINMENT ISOLATION

"During panel walkdown, it was discovered that a tag out for the 'C' Residual Heat Removal pump suction valve was active and the valve was open with its breaker open. This rendered the valve inoperable and Technical Specification 3.6.1.3 Action C for penetration with one inoperable PCIVs was entered. The action was to isolate the penetration by closing the valve within (4) hours or restore power. The event was discovered at 0845 [EDT] and the breaker was closed at 0925 [EDT]. Technical Specification 3.6.1.3 Action C (Isolate penetration within 4 hrs.) was entered at 0130 [EDT] (time breaker was opened per tagout) and exited at 0925 [EDT]. This condition of non-compliance existed from 0530 [EDT] on 11/02/16 until 0925 [EDT] on 11/02/16. This event is being reported under 10CFR50.72 (b)(3)(v)(C).

"NRC Resident has been notified."

Page Last Reviewed/Updated Thursday, November 03, 2016
Thursday, November 03, 2016