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Event Notification Report for May 4, 2004

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
05/03/2004 - 05/04/2004

** EVENT NUMBERS **


40710 40720 40721

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 40710
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: DARON ZAKARIAN
HQ OPS Officer: ARLON COSTA
Notification Date: 04/28/2004
Notification Time: 12:48 [ET]
Event Date: 04/27/2004
Event Time: 16:16 [EDT]
Last Update Date: 05/03/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
Person (Organization):
RICHARD BARKLEY (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 74 Power Operation 74 Power Operation

Event Text

PROCEDURAL ACCEPTANCE CRITERIA FOR DIESEL DRIVEN FIRE PUMP FUEL OIL VISCOSITY NOT MET

"In the process of performing an assessment of the Hope Creek diesel driven fire pump fuel oil supply, a review of the most recently performed fuel oil analysis was performed. This review identified that a fuel oil sample analysis performed on February 11, 2004, to satisfy the 92-day surveillance requirement specified in procedure NC.FP-AP.ZZ-0005, 'Fire Protection Surveillance and Periodic Test Program,' showed that the fuel oil did not meet the procedural acceptance criteria for viscosity (was low out of specification). The diesel driven fire pump was not declared inoperable at this time and no compensatory measures were put in place. Upon discovery of the out of specification fuel sample, the diesel driven fire pump was declared inoperable on April 27, 2004 at 1616 hours and compensatory measures were established. Although the diesel driven fire pump is inoperable due to failure to meet this acceptance criteria, engineering judgment based upon vendor recommended viscosity requirements and satisfactory surveillance pump performance indicates that the diesel driven fire pump would continue to operate and perform its necessary functions with the lower viscosity fuel oil.

"Failure to declare the diesel driven fire pump inoperable and establish appropriate compensatory measures is contrary to the provisions of Hope Creek Operating License Section 2.C.7, 'Fire Protection'. This event is being reported in accordance with Hope Creek Operating License Condition 2.F which requires a 24 hour notification for violation of the requirements of Section 2.C of the Operating License."

The licensee notified the NRC Resident Inspector.

* * * RETRACTION FROM BRADY TO RIPLEY ON 05/03/04 AT 1749 EDT * * *

"An investigation was performed regarding the out of specification fuel oil sample for the diesel driven fire pump that identified that the Chemistry procedure used to perform the fuel oil sample analysis contained testing criteria for viscosity that differed from the requirements of the testing criteria in procedure NC-FP-AP.22-0005, 'Fire Protection Surveillance and Periodic Test Program.' The Chemistry procedure required viscosity testing to be performed at 40 deg C and the Fire Protection surveillance procedure acceptance criteria requires testing for viscosity at 20 deg C. A fuel oil sample obtained on April 26, 2004 was re-analyzed using the required testing parameters of the Fire Protection surveillance procedure and was determined to be within acceptance criteria (satisfactory). A review of previous fuel oil sample analysis data back to August 2000 was performed and compared to the current testing results. The current test results were determined to bound the previous test data. Based on this information, the diesel driven fire pump fuel oil has been acceptable throughout this time period. The diesel driven fire pump was returned to an operable status and the impairment closed. Since the pump remained operable, there was no violation of the Fire Protection Program. The report for violation of License Condition 2.C.7 of the Operating License is being retracted."

The licensee will be notifying the NRC Resident Inspector.

Notified R1DO (A. Della Greca).

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Power Reactor Event Number: 40720
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: RON FRANTZ
HQ OPS Officer: JEFF ROTTON
Notification Date: 05/03/2004
Notification Time: 09:42 [ET]
Event Date: 05/03/2004
Event Time: 01:25 [CDT]
Last Update Date: 05/03/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
BRUCE BURGESS (R3)

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

NON-LICENSED EMPLOYEE TESTED POSITIVE FOR ALCOHOL

A non-licensed employee was identified as under the influence during for cause testing. The employee's access to the plant has been placed on hold. Contact the Headquarters Operations Officer for additional details.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 40721
Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [1] [ ] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: R.H.SCHNEIDER
HQ OPS Officer: JOSEPH TAYLOR
Notification Date: 05/03/2004
Notification Time: 15:29 [ET]
Event Date: 04/30/2004
Event Time: 14:38 [CDT]
Last Update Date: 05/03/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
TOM FARNHOLTZ (R4)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling 0 Refueling

Event Text

"On 4/30/2004, during Refueling Outage 1 R18, ultrasonic testing of the reactor vessel head identified two axial indications on Control Rod Drive Mechanism, nozzle 61. The indications were located on the outside diameter of the nozzle on the lower hillside. One of the flaws was at the toe of the fillet weld and extended below the fillet weld cap. The second flaw extended the full length of the weld and just below the toe of the fillet weld.

"There were no indications that either of the flaws was through-wall or through-weld and both were typical of Primary Water Stress Corrosion Cracking. No formal evaluation of these flaws has been completed; however, based on past analysis it is expected that they would not be found acceptable under ASME standards and, therefore, represent degradation of a principal safety barrier reportable under the referenced criterion. This condition was determined to be reportable at 0839 CDT on 5/3/2004.

"The nozzle will be repaired prior to startup from the current refueling outage.

"The reactor vessel head inspection was subsequently completed with no additional flaws identified."

The licensee notified the NRC Resident Inspector.

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