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Event Notification Report for October 6, 2011

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/05/2011 - 10/06/2011

** EVENT NUMBERS **


47318 47320 47321 47322 47323

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Agreement State Event Number: 47318
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: J. YANG AND ASSOCIATE
Region: 4
City: SAN RAMON State: CA
County:
License #: 3694-34
Agreement: Y
Docket:
NRC Notified By: KENT PRENDERGAST
HQ OPS Officer: JOE O'HARA
Notification Date: 10/03/2011
Notification Time: 18:48 [ET]
Event Date: 09/27/2011
Event Time: 09:00 [PDT]
Last Update Date: 10/03/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JACK WHITTEN (R4DO)
DUNCAN WHITE (FSME)

Event Text

AGREEMENT STATE REPORT - LICENSEE FAILED TO TURN IN THEIR NUCLEAR GAUGE AFTER LICENSE WAS TERMINATED

The following was received from the state via e-mail:

"On September 27, 2011, RHB [Radiologic Health Branch] was informed by Pacific Nuclear Technology (PNT) that they collected a moisture density gauge that was left on the adjacent office porch of the BSK & Associate office. The gauge was discovered by BSK & Associate's employee, and according to PNT service records, the gauge belonged to J. Yang and Associates. The gauge was delivered to CDPH-RHB on 09/27/11 by PNT. RHB will investigate to determine how the gauge was lost. Mr. Yang terminated his CA License in 2008, but apparently did not relinquish all of his licensed materials."

CA 5010 Number: 092711

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Power Reactor Event Number: 47320
Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: E. MICHAEL SOCHA
HQ OPS Officer: JOE O'HARA
Notification Date: 10/05/2011
Notification Time: 15:24 [ET]
Event Date: 10/05/2011
Event Time: 08:21 [EDT]
Last Update Date: 10/05/2011
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
2 N Y 100 Power Operation 100 Power Operation
3 N Y 98 Power Operation 98 Power Operation

Event Text

PAGING SYSTEM IS OUT OF SERVICE

"At 0812 EDT on October 5, 2011, Millstone Power Station determined that a condition exists affecting Emergency Preparedness Capabilities due to a major loss of offsite communications capability. Specifically, Millstone Power Station was notified by an offsite vendor that the system relied upon for offsite communications in accordance with the Millstone Emergency Plan using a pager system is not functioning reliably. The Millstone Emergency Plan will be implemented by the approved, pre-existing alternate notification method.

"Appropriate officials are being notified that the alternate method is being employed until the primary means is restored.

"This condition is being reported pursuant to 10 CFR 50.72(b)(3)(xiii)."

The paging system is being repaired and the utility has an alternate communication method in place.

The NRC Senior Resident Inspector has been notified as well as Waterford local government and the Connecticut Department of Environmental Protection.

IRF Number: 2011066

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Power Reactor Event Number: 47321
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [ ] [2] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: JACK KEMPKES
HQ OPS Officer: JOE O'HARA
Notification Date: 10/05/2011
Notification Time: 15:50 [ET]
Event Date: 10/05/2011
Event Time: 07:27 [CDT]
Last Update Date: 10/05/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
MONTE PHILLIPS (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Hot Shutdown 0 Hot Shutdown

Event Text

TWO LOOPS OF REACTOR COOLANT SYSTEM (RCS) WERE DECLARED INOPERABLE

"Unit 2 was shut down at 1048 CDT on October 4, 2011 due to 22 Reactor Coolant Pump (RCP) low seal leak off flow. At 0727 CDT on October 5, 2011 with Unit 2 in Mode 4 and 22 RCP secured, 21 RCP was also secured due to low seal leak off flow.

"It was determined that the station would not consider RHR [residual heat removal] available for decay heat removal per Technical Specification (TS) due to a procedural issue related to component cooling shutdown lineups. RCS temperature is being maintained stable in Mode 4 between 320 and 340 degrees Fahrenheit using natural circulation and the steam dump to the condenser. No operations were permitted that would have caused introduction into the RCS, coolant with boron concentration less than required to meet the Shutdown Margin.

"At approximately 1329 CDT 21 RCP was restarted after the flow transmitters were vented and 21 RCP seal leak off flow was determined to be acceptable. The RHR procedural issue has been resolved.

"Per TS LCO 3.4.6, 'Two loops consisting of any combination of RCS loops and residual heat removal (RHR) loops shall be OPERABLE, and one loop shall be in operation.' This condition is reportable as an event or condition that could have prevented fulfillment of a safety function under 10CFR 50.72(b)3)(v)(B)."

During this event, RHR could not be credited because the utility was not able to valve in component cooling water to a SFP heat exchanger due to procedural issues. With the restart of 21 RCP and shutdown cooling water alignment, TS 3.6.4 A and B statements have been met and exited. 21 RCP loop in operation and 22 RHR is operable and can be aligned for shutdown cooling. Both Unit 2 EDG's are available and offsite power is normal electrical lineup. The licensee is no longer in any TS LCO statements.

The NRC Resident Inspector has been notified.

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Power Reactor Event Number: 47322
Facility: PALISADES
Region: 3 State: MI
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: OTTO GUSTAFSON
HQ OPS Officer: JOE O'HARA
Notification Date: 10/05/2011
Notification Time: 18:00 [ET]
Event Date: 09/26/2011
Event Time: 06:02 [EDT]
Last Update Date: 10/05/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
MONTE PHILLIPS (R3DO)

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

UNANALYZED CONDITION - APPENDIX R EQUIPMENT MAY NOT HAVE BEEN AVAILABLE

"An Appendix R non-compliance issue was identified. When the plant automatically tripped on September 25, 2011, an unexpected automatic trip was identified in DC shunt trip breakers 72-01 and 72-02. This automatic trip function was not considered in the Appendix R electrical coordination evaluation. Preliminary analysis has shown that if the shunt trip breaker would have automatically opened due to fire induced fault currents, then Appendix R credited equipment may have been lost unexpectedly. The operability evaluation performed, resulted in increasing the shunt trip settings to maximum, and implementing compensatory measures to isolate some non-safety related electrical loads, which restored compliance with 10 CFR 50 Appendix R.

"The licensee notified the NRC Senior Resident Inspector."

CR# PLP2011-04835

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Power Reactor Event Number: 47323
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: DAVID HALL
HQ OPS Officer: JOE O'HARA
Notification Date: 10/05/2011
Notification Time: 19:17 [ET]
Event Date: 10/05/2011
Event Time: 15:53 [EDT]
Last Update Date: 10/05/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
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

OFFSITE NOTIFICATION DUE TO POTENTIAL CHEMICAL SPILL IN THE DELAWARE RIVER

"At 0930 on 10/5/11, a fuse failure in a 1E to non - 1E interface failed causing a false run signal to the water treatment system for a standby station service water pump. The water treatment system responded by opening the injection valve for the out of service pump. With the associated pump out of service, the sodium hypochlorite can communicate with the Delaware river. This was discovered at 1553 and immediately terminated. This resulted in the discharge of approximately 195 gallons of 15% sodium hypochlorite to SSW intake which communicates with the Delaware river. The associated service water pump was started thus withdrawing residual product from the intake. A portion of the discharged sodium hypochlorite may have entered the Delaware river. A sample was obtained from the Delaware river just outside the intake structure and there was no detectable chlorine in the sample and there were no abnormal conditions noted on the river. Based on Environmental Licensing review, this was reportable to the state of NJ within 15 minutes. The report to the state was initiated at 1608 on 10/5/11.

"Subsequent calls were made to the Hope Creek Senior NRC Resident, the National Response Center and the US Coast Guard. Affected systems are limited to the Station Service Water (SSW) system and the sodium hypochlorite water treatment system. There was no impact on plant operations and these systems remain fully operable. Evaluation is underway to fully understand the impacts of the fuse failure to prevent reoccurrence. There was nothing unusual or not understood. All safety related equipment continues to function as required. There were no injuries or reported wildlife impact."

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Thursday, March 29, 2012