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Event Notification Report for July 29, 2014

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
07/28/2014 - 07/29/2014

** EVENT NUMBERS **


50267 50284 50287 50294 50315 50316

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Agreement State Event Number: 50267
Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: LEHIGH VALLEY HOSPITAL - HAZLETON
Region: 1
City: HAZLETON State: PA
County:
License #: PA-0106
Agreement: Y
Docket:
NRC Notified By: DAVID ALLARD
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 07/10/2014
Notification Time: 14:35 [ET]
Event Date: 11/13/2013
Event Time: [EDT]
Last Update Date: 07/28/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
ANNE DeFRANCISCO (R1DO)
FSME EVENTS RESOURCE (FSME)

Event Text

AGREEMENT STATE REPORT - BRACHYTHERAPY UNDERDOSE

The following information was received via fax:

"This medical event (ME) was self-identified by the licensee during an audit. A patient who had undergone an iodine-125 (I-125) prostate brachytherapy procedure was reported to have a 'D90' dose of 43% of the written directive. The licensee radiation safety officer and physician are in contact regarding this ME. It is unknown at this time if the patient has been notified.

"The Department [Pennsylvania Department of Environmental Protection] is waiting for the required 15 day written report from the licensee. The Department will then conduct a reactive inspection."

PA Event Number: PA140017

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.


* * * RETRACTION FROM DAVID ALLARD TO DONALD NORWOOD AT 1641 EDT ON 7/28/2014 * * *

The following information was received via facsimile:

"Through an internal audit, it was initially thought that a patient who had undergone an iodine-125 (I-125) prostrate brachytherapy treatment in November, 2013 was believed to have had a 'D90' dose of only 43% of the written directive. However, based on a re-assessment by the licensee's Chief Medical Physicist, it appears that greater than 80% of the prostate volume received the prescribed dose.

"[The] reported medical event is to be retracted."

Notified R1DO (Dimitriadis) and FSME Events Resource via E-mail.

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Part 21 Event Number: 50284
Rep Org: VELAN INC.
Licensee: VELAN INC.
Region:
City: MONTREAL, CANADA State:
County:
License #:
Agreement: N
Docket:
NRC Notified By: VICTOR APOSTOLESCU
HQ OPS Officer: VINCE KLCO
Notification Date: 07/18/2014
Notification Time: 08:28 [ET]
Event Date: 07/17/2014
Event Time: [EDT]
Last Update Date: 07/28/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
THOMAS FARNHOLTZ (R4DO)
PART 21 GROUP (EMAI)

Event Text

PART 21 REPORT - NOTIFICATION OF DEFECTS ON 2 INCH BONNETS

The following information was received from Velan Inc by facsimile:

"SUBJECT NOTIFICATION: 2 INCH BONNETS, VELAN PART NUMBER 8943-014

"On May 16, 2014 [Velan] received notification from Westinghouse Electric Co. (WES) that 2 bonnets supplied by Velan to WES in early 2013 for installation at Comanche Peak exhibited the following issues:
- The bonnets were intended to be exact replacements for the bonnets built to drawing E73-020 Rev E (OEM is Velan) except for material change to SA-182 FXM-19. Bonnets were visually inspected when received at site. No issues were noted; both bonnets appeared to be identical.
- In April 2013, Unit 1 bonnet was installed in valve 1-8109. No issues were noted with the installation. The new bonnet was put into service.
-In April 2014, Unit 2 installation was scheduled to begin. After the disassembly of the valve, the old and new bonnets were compared. It was noted that the backseat dimensions are different between the 2 bonnets. The increase in backseat diameter on the new bonnet would cause the stem to not backseat. The decision was made to re-install the old bonnet and send the new bonnet back to the OEM, Velan.

"On June 10, 2014 the bonnet, identified in the last bullet above, arrived at Velan Plant 2.

"The review by the [Velan] Evaluation Committee was finalized on July 17 and concluded that:
-Four similar bonnets were delivered to WES on three different occasions in 1988 and early 90's
-The stem head diameter is 01.312 [inches] so, when opening, the stem may pass through the stem bore of the bonnet and not seat on the backseat.
-On opening, if the limit switches on the actuator do not function, the stem may enter the packing chamber. The packing may be deformed and a leak may develop. Stem travel is limited by the disc contacting the bonnet and/or the end of the stem thread stopping on the actuator drive nut.
-If the actuator and packing flange nuts are removed, there is the potential for the stem to blow out of the valve.
-The packing chamber depth will result in more packing being installed in the valve. This may result in a higher packing friction load on the actuator when operating and reduce the actuator margin.
-The smaller packing chamber will not affect safety. A different diameter packing may be required. The gland bushing diameter (01.744 inches) is less than the packing chamber diameter and will work correctly.

"These bonnets were fabricated against ASME Sec. Ill for installation in Class 2 systems. Not knowing exactly the nature of the application we cannot determine if the [above identified] potential issues may pose a significant safety hazard and therefore we have informed WES by way of a similar letter."

* * * UPDATE PROVIDED FROM VICTOR APOSTOLESCU TO JEFF ROTTON AT 1435 EDT ON 07/28/2014 * * *

Reporting Organization/Supplier who made the original event report on 07/18/2014 reported to the NRC Operations Center that the Event Notification posted has a typographical error regarding the Velan, Inc part number described in the report. The original documentation provided was concerning Velan Part Number 8943-014 which was mistakenly transcribed as 6943-014 in the original report. This error has been corrected in this updated report.

Notified R4DO (Okeefe) and Part 21 Group via email.

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Power Reactor Event Number: 50287
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: ROBERT PELL
HQ OPS Officer: DONALD NORWOOD
Notification Date: 07/20/2014
Notification Time: 20:02 [ET]
Event Date: 07/20/2014
Event Time: 14:54 [EDT]
Last Update Date: 07/28/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
GERALD MCCOY (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N Y 100 Power Operation 100 Power Operation
4 N Y 100 Power Operation 95 Power Operation

Event Text

ULTIMATE HEAT SINK TEMPERATURE EXCEEDED TECHNICAL SPECIFICATION LIMIT

"At 1454 EDT on 20 July 2014, Turkey Point Units 3 and 4 entered the Action for Technical Specification (TS) 3.7.4, Ultimate Heat Sink (UHS). The action was entered because UHS temperature exceeded the limit of 100 degrees F due to a natural event. This report is in accordance with 10CFR50.72(b)(3)(v)(B) because UHS capability to remove residual heat is impacted. At 1800 EDT the NRC verbally approved a natural event Notice of Enforcement Discretion (NOED) which allows the ultimate heat sink temperature to exceed 100 degrees F up to 103 degrees F. Unit power levels have been maintained at Unit 3 100% and Unit 4 95%.

"The NRC Resident Inspector has been notified."

* * * UPDATE FROM CHRIS TRENT TO DANIEL MILLS AT 2058 EDT ON 7/26/2014 * * *

"At 2046 on 7/20/14, Turkey Point Units 3 and 4 exited the Action for Technical Specification (TS) 3.7.4, Ultimate Heat Sink, when the ultimate heat sink (UHS) temperature decreased below the TS limit of 100 degrees F.

"At 1604 on 7/26/14, Turkey Point Units 3 and 4 entered the Action for TS 3.7.4, Ultimate Heat Sink. The action was entered because UHS temperature exceeded the limit of 100 degrees F. This report is in accordance with 10 CFR 50.72(b)(3)(v)(B) because UHS capability to remove residual heat is impacted. Turkey Point is currently complying with NOED No. 14-2-001, which allows a temporary maximum UHS temperature of 103 degrees F.

"The NRC Resident Inspector was notified."

At 2058 on 7/26/14 the UHS average temperature was 100.3 degrees F and the peak temperature was 100.5 degrees F. Unit 4 is currently operating at 75% power in anticipation of elevated intake temperature in the next several days.

Notified R2DO (Musser)

* * * UPDATE FROM JOSE VASQUEZ TO DANIEL MILLS AT 1913 EDT ON 7/27/2014 * * *

"At 2102 on 7/26/14, Turkey Point Units 3 and 4 exited the Action for Technical Specification (TS) 3.7.4, Ultimate Heat Sink, when the ultimate heat sink (UHS) temperature decreased below the TS limit of 100 degrees F.

"At 1602 on 7/27/14, Turkey Point Units 3 and 4 entered the Action for TS 3.7.4, Ultimate Heat Sink. The action was entered because UHS temperature exceeded the limit of 100 degrees F. This report is in accordance with 10 CFR 50.72(b)(3)(v)(B) because UHS capability to remove residual heat is impacted. Turkey Point is currently complying with NOED No. 14-2-001, which allows a temporary maximum UHS temperature of 103 degrees F.

"The NRC Resident Inspector was notified."

At 1913 on 7/27/14 the UHS average temperature was 101.1 degrees F and the peak temperature was 101.3 degrees F. Units 3 and 4 are currently operating at 75% power in anticipation of elevated intake temperature in the next several days.

Notified R2DO (Musser)

* * *UPDATE PROVIDED BY CHRISTOPHER TRENT TO JEFF ROTTON AT 2103 EDT ON 07/28/2014 * * *

"At 2212 on 7/27/14, Turkey Point Units 3 and 4 exited the Action for Technical Specification (TS) 3.7.4, Ultimate Heat Sink, which was entered at 1602 on 7/27/14, when the ultimate heat sink (UHS) temperature decreased below the TS limit of 100 degrees F.

"At 1445 on 7/28/14, Turkey Point Units 3 and 4 entered the Action for TS 3.7.4, Ultimate Heat Sink. The action was entered because UHS temperature exceeded the limit of 100 degrees F. This report is in accordance with 10 CFR 50.72(b)(3)(v)(B) because UHS capability to remove residual heat is impacted. Turkey Point is currently complying with NOED No. 14-2-001, which allows a temporary maximum UHS temperature of 103 degrees F.

"At 1946 on 7/28/14, UHS temperature decreased below the TS limit of 100 degrees F and Turkey Point Units 3 and 4 exited the Action for Technical Specification (TS) 3.7.4, Ultimate Heat Sink.

'The NRC Resident Inspector was notified."

Peak UHS temperature reached on 7/28/2014 was 101.1 degrees F. Units 3 and 4 are currently operating at 75 percent power in anticipation of continued elevated intake temperatures.

Notified R2DO (Musser)

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Power Reactor Event Number: 50294
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: NICHOLAS E. RULLMAN
HQ OPS Officer: STEVE SANDIN
Notification Date: 07/22/2014
Notification Time: 16:57 [ET]
Event Date: 07/22/2014
Event Time: 06:35 [PDT]
Last Update Date: 07/28/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
GEOFFREY MILLER (R4DO)

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

RADIATION MONITORING SAMPLE RACK DECLARED NON-FUNCTIONAL

"At 0635 hours PDT on July 22, 2014, Turbine Building Exhaust Air Radiation Indicating Switch (TEA-RIS-13) and the Turbine Building Process Radiation Monitoring Sample Rack (TEA-SR-26) were declared non-functional. The cause of the malfunction is under investigation. Compensatory measures have been implemented to obtain radiation readings from the associated effluent release pathway. Field team assessment function was unaffected and remains available.

"This event is being reported as a major loss of assessment capability in accordance with 10 CFR 50.72(b)(3)(xiii).

"The licensee has notified the NRC Resident Inspector."


* * * UPDATE FROM DUANE SALSBURY TO DONALD NORWOOD AT 2018 EDT ON 7/28/2014 * * *

"At 1351 PDT on 7/28/2014, Turbine Building Exhaust Air Radiation Indicating Switch (TES-RIS-13) and Turbine Building Process Radiation Monitoring Sample Rack (TES-SR-26) were declared functional.

"The NRC Resident Inspector has been notified."

Notified R4DO (O'Keefe).

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Power Reactor Event Number: 50315
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: MICHAEL MOORE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 07/28/2014
Notification Time: 05:06 [ET]
Event Date: 07/28/2014
Event Time: 01:18 [EDT]
Last Update Date: 07/28/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MEL GRAY (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

LOSS OF METEOROLOGICAL DATA TO THE SITE

"At 0118 [EDT] on 7/28/2014, meteorological data was lost to both Salem and Hope Creek. At the time, there were storms in the vicinity which [were] the apparent cause of the temporary loss of data. Both Salem and Hope Creek lost wind direction information. This event is being reported under 10CFR50.72(b)(3)(xiii), major loss of emergency assessment capabilities.

"At 0130, meteorological data was restored to the control rooms. Plant operations at Hope Creek and both Salem Units 1 and 2 were not affected. All three units remain at full power.

"The licensees notified the NRC Resident Inspectors."

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Power Reactor Event Number: 50316
Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: STEVEN ANDREWS
HQ OPS Officer: STEVE SANDIN
Notification Date: 07/29/2014
Notification Time: 05:05 [ET]
Event Date: 07/29/2014
Event Time: 05:00 [EDT]
Last Update Date: 07/29/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
RANDY MUSSER (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

TECHNICAL SUPPORT CENTER HVAC REMOVED FROM SERVICE FOR PLANNED MAINTENANCE

"This is a non-emergency eight hour notification for a loss of emergency assessment capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the work activity affects the functionality of an emergency response facility. Planned maintenance activities are being performed on 07/29/2014 to the Technical Support Center (TSC) HVAC.

"The work includes performance of breaker inspections and corrective/preventative AHU [Air Handling Unit] maintenance. The planned work activity duration is approximately 48 hours.

"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures unless the TSC becomes uninhabitable due to ambient temperature, radiological, or other conditions. If relocation of the TSC becomes necessary, the Emergency Director will relocate the TSC staff to an alternate location in accordance with applicable site procedures.

"The Emergency Response Organization team has been notified of the maintenance and the possible need to relocate during an emergency.

"The NRC Resident Inspector has been notified.

"This condition does not affect the health and safety of the public or station employees."

The licensee will be notifying state and local authorities.

Page Last Reviewed/Updated Tuesday, July 29, 2014
Tuesday, July 29, 2014