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Event Notification Report for October 29, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/28/2013 - 10/29/2013

** EVENT NUMBERS **


49363 49450 49478 49480

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 49363
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: LT IHLENFELDT
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 09/19/2013
Notification Time: 23:56 [ET]
Event Date: 09/19/2013
Event Time: 17:50 [CDT]
Last Update Date: 10/28/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
KENNETH RIEMER (R3DO)

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

HIGH PRESSURE COOLANT INJECTION INOPERABLE DUE TO STEAM LEAK

"On 9/19/2013, during the performance of the High Pressure Coolant Injection (HPCI) quarterly pump and valve surveillance, a steam leak was discovered. HPCI had previously been declared inoperable due to planned maintenance. As a result of the steam leak, HPCI remains inoperable.

"Action taken: 14 days Required Action TS 3.5.1.J.2 remains in effect and corrective actions are in progress.

"The licensee has notified the NRC Resident Inspector."

* * * RETRACTION FROM RANDY SAND TO PETE SNYDER AT 1546 EDT ON 10/28/13 * * *

"The licensee performed an evaluation that determined the minor steam leak from the High Pressure Coolant Injection (HPCI) turbine reported on 9/20/2013 was not significant enough to prevent HPCI from mitigating the consequences of an accident or mitigating a Station Blackout (SBO) event.

"The licensee performed an engineering evaluation of the HPCI system, the HPCI pump/turbine and the HPCI room environmental conditions assuming conservative leakage conditions existed. The results of this evaluation confirmed that the HPCI system would have been able to perform its design function assuming conservative leakage conditions existed throughout limiting events. The HPCI pump/turbine would not have failed during any accident or SBO event, and sufficient motive (steam) force was available for the HPCI system to perform its design functions. There would have been no unacceptable impact on the HPCI pump/turbine oil system due to the steam leak. The HPCI room environment would not have exceeded allowable limits. For events where AC power is available, the analysis took advantage of the HPCI room cooler that is powered from an essential power source and supplied from a safety related service water system. This cooler was available during the period of the steam leak. The evaluation of room conditions for SBO conditions did not include use of the HPCI room cooler and also showed room conditions would have remained within acceptable values. There would not have been a buildup of fluid sufficient to cause a flood in the HPCI room.

"Therefore, based on the results of the formal engineering evaluation, the HPCI system was capable of performing its safety function and therefore, this event may be retracted."

The licensee will notify the NRC Resident Inspector. Notified R3DO (Daley).

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Agreement State Event Number: 49450
Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: ABINGTON MEMORIAL HOSPITAL
Region: 1
City: ABINGTON State: PA
County:
License #: PA-0055
Agreement: Y
Docket:
NRC Notified By: JOESEPH MELNIC
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 10/18/2013
Notification Time: 15:28 [ET]
Event Date: 05/07/2013
Event Time: [EDT]
Last Update Date: 10/18/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
PAUL KROHN (R1DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - MEDICAL EVENT INVOLVING THE ADMINISTRATION OF AN UNDER-DOSE TO A PATIENT

The following report was received via email:

"Event type: Medical Event involving the administration of yttrium-90 (Y-90) Sir-Spheres.

"Notifications: On October 17, 2013 the licensee informed the Department's Central Office of the Medical Event. The event is reportable within 24 hours per 10 CFR 35.3045(a)(1)(i). Appropriate reporting to the referring physician and the patient is currently underway.

"Event Description: The patient was scheduled to receive two split doses on May 7, 2013. The plan was to treat the left hepatic artery segment 2 and 3 with 11.9 mCi (0.44 GBq) and the left hepatic artery segment 4 with 11.9 mCi (0.44 GBq). The unit doses were assayed separately and were found to be within 10% of the prescribed doses. After the doses were assayed, the exposure rate around the jar was measured and documented. After the procedure was completed, the tubing, V-Vial, and the jar were collected and then measured to calculate the residual activity using the same procedure and geometry used during the pre-dose measurements as per procedure. The post treatment measurements and calculations revealed the following delivered doses. The left hepatic artery segment 2 and 3 branches received 9.2 mCi and the left hepatic artery segment 4 branch received 8.92 mCi. This resulted in under-dosing of 22.48% and 30.03% respectively.

"CAUSE OF THE EVENT: Occlusion of SirSpheres in the delivery system. The post treatment measurements were high which indicated that there were some spheres in the tubing or the V-Vial. When the jar was opened, it was found that the three-way stop cock contained some of the activity.

"ACTIONS: A new dose work sheet has been built in as a warning to remind the licensee to notify the regulatory agency should the dose variance exceed 20%.

"Media attention: None at this time."

Pennsylvania Event Report Number - PA130055

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: 49478
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: DAVID ORTIZ
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 10/28/2013
Notification Time: 18:02 [ET]
Event Date: 10/28/2013
Event Time: 12:30 [CDT]
Last Update Date: 10/28/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
JAMES DRAKE (R4DO)

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

POSTULATED EVENT COULD RESULT IN A HOT SHORT THAT COULD ADVERSELY IMPACT SAFE SHUTDOWN EQUIPMENT

"A review of industry operating experience regarding the impact of unfused direct current (DC) ammeter circuits in the control room has determined that the condition described below applies to Fort Calhoun Nuclear Station. This could result in an unanalyzed condition with respect to 10 CFR 50 Appendix R analysis requirements.

"The control room ampere indications for the Class 1E batteries and their chargers do not include over-current protection to limit fault current.

"In a postulated event, a fire in the control room could cause one of the ammeter wires to hot-short to the ground plane. Simultaneously, the event could cause another DC wire from the opposite polarity on the same battery to hot-short to the ground plane. This would cause a ground-loop through unprotected ammeter wiring.

"Since this circuit is not protected (not fused), this event could result in excessive current flow in the ammeter wiring to the point of causing a secondary fire in the associated raceway system. This could potentially cause the loss of the ability to conduct a safe shutdown as required by 10CFR50 Appendix R.

"This condition is being reported in accordance with 10 CFR 50.72(b)(3)(ii)(B) as an unanalyzed condition that significantly degrades plant safety. Compensatory measures (fire watches) have been implemented for affected areas of the plant.

"The NRC Resident Inspector has been notified."

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Power Reactor Event Number: 49480
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: CHRIS WEICHLER
HQ OPS Officer: DONG HWA PARK
Notification Date: 10/29/2013
Notification Time: 05:01 [ET]
Event Date: 10/29/2013
Event Time: 05:00 [EDT]
Last Update Date: 10/29/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
PAUL KROHN (R1DO)

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

Event Text

MAIN STACK RADIATION MONITORS REMOVED FROM SERVICE

"At 0500 [EDT] Tuesday, October 29, the Peach Bottom Atomic Power Station (PBAPS) main stack radiation monitors will be removed from service for planned preventative maintenance activities on the flow elements. This maintenance is scheduled to be worked continuously until completion to minimize out of service time. The planned main stack radiation monitor outage is scheduled to be completed within 13 hours. Periodic gas sampling will be performed in accordance with the offsite dose calculation manual while the monitors are out of service.

"The NRC Resident Inspector has been notified.

"There are no follow-up written reports required for this event."

Page Last Reviewed/Updated Tuesday, October 29, 2013
Tuesday, October 29, 2013