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Event Notification Report for December 6, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/03/2010 - 12/06/2010

** EVENT NUMBERS **


46354 46455 46456 46457

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 46354
Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [ ]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: PHILLIP PRATER
HQ OPS Officer: VINCE KLCO
Notification Date: 10/22/2010
Notification Time: 23:05 [ET]
Event Date: 10/22/2010
Event Time: 17:51 [CDT]
Last Update Date: 12/03/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
Person (Organization):
STEVE ORTH (R3DO)

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

POTENTIAL INOPERABILITY OF OSCILLATION POWER RANGE MONITORS

"At 1751 [CDT] on Oct 22, 2010, Dresden Nuclear Power Station (DNPS) determined that current Oscillation Power Range Monitors (OPRM's) setpoints, as outlined in the Core Operating Limits Report (COLR), for Dresden U2 are non-conservative. This renders the Technical Specification (TS) function of the OPRM's in the Reactor Protection System (RPS) inoperable.

"This event was initiated as a result of notification by Westinghouse Nuclear Fuels (NF-BEX-10-157) that an error exists in the McSLAP computer code which affects the Safely Limit Minimum Critical Power Ratios (SLMCPR) for Dresden. Currently the COLR and installed, amplitude setpoint (Sp) is 1.13 and the confirmation count setpoint (Np) is 15. This is required to be adjusted to 1.12 (Sp) and 14 (Np).

"Alternative methods to detect and suppress thermal hydraulic instabilities were initiated as required by Technical Specifications.

"This non-conservative computer code error could potentially have prevented fulfillment of the OPRM system's safety function and is therefore reportable per 10 CFR 50.72(b)(3)(v)(A), 'An event or condition that could have prevented the fulfillment of a safety function - shutdown the reactor and maintain it in a safe shutdown condition.'"

Corrective actions include the following:

"1. Revise U2 Core Operating Limit Report (COLR) to reflect correct values as determined by Westinghouse Nuclear Fuels Letter (NF-BEXl0-157).

"2. Adjust OPRM setpoints to comply with COLR values."

The licensee will notify the NRC Resident Inspector.

* * * RETRACTION FROM RILEY RUFFIN TO ERIC SIMPSON AT 1207 EST ON 12/3/10 * * *

"On October 22, 2010, Dresden Nuclear Power Station was notified by Westinghouse that an error in McSlap computer code resulted in a non-conservative MCPR safety limit. The preliminary results of the Westinghouse evaluation concluded that the setpoints for the Oscillation Power Range Monitors were also non-conservative. As a result of the notification, Dresden declared all channels of OPRM inoperable and took the required action of the plant's technical specifications. This was considered a loss of function.

"This condition was reported as a condition that could have potentially prevented the fulfillment of the OPRM system's safety function in accordance with 10 CFR 50.72(b)(3)(v)(A), an event or condition that could have prevented the fulfillment of a safety function - shutdown the reactor and maintain it in a safe shutdown condition.

"However, subsequent evaluation of the preliminary result determined that the original conclusions were overly conservative and the OPRM setpoints did not require revision. Based on the later evaluation, the function of the OPRMs was not adversely impacted by the installed setpoints. Thus, the system was always capable of performing its intended safety function.

"Therefore the notification associated with Event Number 46354 is being retracted."

The licensee notified the NRC Resident Inspector.

The R3DO (Ring) was notified.

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Power Reactor Event Number: 46455
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: CHRIS SMOLINSKI
HQ OPS Officer: BILL HUFFMAN
Notification Date: 12/04/2010
Notification Time: 14:13 [ET]
Event Date: 12/04/2010
Event Time: 11:28 [EST]
Last Update Date: 12/04/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
WAYNE SCHMIDT (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

TONE ALERT EMERGENCY NOTIFICATION SYSTEM INOPERABLE

"At 1142 (EST) on December 4, 2010, with the James A. FitzPatrick (JAF) Nuclear Power Plant operating at 100% reactor power, Oswego County Emergency Management notified JAF that the National Weather Service had notified them that the Tone Alert Radios had been out of service since 1028 (EST).

"This impacts the ability to readily notify a portion of the Emergency Planning Zone (EPZ) Population for the Nine Mile Point and JAF Nuclear Power Plants. This failure meets NRC 8 hour reporting criterion 10 CFR 50.72(b)(3)(xiii).

"The County Alert Sirens which also function as part of the Public Prompt Notification System remain operable.

"The loss of the Tone Alert Radios constitutes a significant loss of emergency off-site communications ability. Compensatory measures have been verified to be available should the Prompt Notification System be needed. This consists of utilizing the hyper reach system which is a reverse 911 feature available from the county 911 center. Local Law Enforcement Personnel are also available for 'Route Alerting' of the affected areas of the EPZ.

"The event has been entered into the corrective action program and the resident inspector has been briefed .

"At 1258 (EST) on December 4, 2010, Oswego County Emergency Management notified JAF that the Tone Alert Radio System has been restored effective at 1255 (EST) ."

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Power Reactor Event Number: 46456
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: JIM VAUGHN
HQ OPS Officer: VINCE KLCO
Notification Date: 12/04/2010
Notification Time: 14:37 [ET]
Event Date: 12/04/2010
Event Time: 11:42 [EST]
Last Update Date: 12/04/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
WAYNE SCHMIDT (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

TONE ALERT EMERGENCY NOTIFICATION SYSTEM INOPERABLE

"On Saturday, December 04, 2010 at 1142 [EST], the NYS Warning Point informed NMP [Nine Mile Point] via the RECS [Radiological Emergency Communications System] line that the EAS/Tone system was out of service for greater than one hour as of 1128 [EST].

"10CFR 50.72(b)(3)(xiii) requires reporting within 8 hours when a significant portion of the emergency communications system has been lost. Site Emergency Procedures define a loss of EAS/Tone for greater than 1 hour as a significant loss of emergency communications.

"The EAS/Tone Alert system was returned to service on December 4, 2010 at 1255 [EST].

"The event has been entered into the corrective action program,"

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 46457
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: PRESTON LAWSON
HQ OPS Officer: HOWIE CROUCH
Notification Date: 12/06/2010
Notification Time: 05:42 [ET]
Event Date: 12/06/2010
Event Time: 04:18 [CST]
Last Update Date: 12/06/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
DALE POWERS (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 85 Power Operation

Event Text

TECH SPEC REQUIRED SHUTDOWN DUE TO EXCEEDING ALLOWED OUTAGE TIME ON THE 'A' EMERGENCY DIESEL GENERATOR

"(KKJ01A) 'A' Emergency Diesel Generator (EDG) was removed from service and declared inoperable [on] 11/29/2010 at 0500 (CST) for a scheduled 7 day Technical Specification equipment outage to perform various scheduled maintenance items. Technical Specification 3.8.1 Condition B was entered for one Diesel Generator inoperable, utilizing Action B.4.2.2, 'Restore the Diesel Generator to OPERABLE within 7 days AND 10 days from discovery of failure to meet LCO'.

"On 12/06/2010, it was discovered during the Operability Run Surveillance, STS KJ-015A, utilized to restore the EDG to service, the Engine Analyzer Data Acquisition [software] indicated the No. 12 cylinder is 'out of balance' and will require a clearance order and maintenance repair. On 12/06/2010 [at] 0350 hrs., it was determined that the work required to restore the EDG to service would cause the Tech Spec 3.8.1 Action B.4.2.2 Completion Time requirement of 7 days to be exceeded, requiring a Plant Shutdown per TS 3.8.1 Condition H, with Action H.1, 'Be in Mode 3 within 6 hours', and Action H.2, 'Be in Mode 5 within 36 hours'.

"Plant Shutdown to Mode 3 was commenced [on] 12/06/2010 at 0418 (CST).

"The [NRC] Resident Inspector has been contacted."

The licensee indicated that required repairs should be completed within 8 hours and expects restart to occur on 12/06/2010.

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Tuesday, August 11, 2015