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Event Notification Report for April 30, 2004

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/29/2004 - 04/30/2004

** EVENT NUMBERS **


40605 40641 40706 40708 40714 40715 40716

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 40605
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GRANT FERNSLER
HQ OPS Officer: STEVE SANDIN
Notification Date: 03/23/2004
Notification Time: 11:00 [ET]
Event Date: 03/23/2004
Event Time: 07:46 [EST]
Last Update Date: 04/29/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
FRANK COSTELLO (R1)

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

Event Text

INDICATION OF CRACK FAILURE ON RCS PRESSURE BOUNDARY PENETRATION

"Unit 1 is currently in a refueling outage in Mode 5. During a routine inservice inspection of the reactor vessel, an indication was discovered on the N1B penetration. This is associated with the suction for B Loop of Reactor Recirculation. At 0746 on 3/23/2004, the Control Room was notified that the evaluation was completed and the indication was determined to be unacceptable under the ASME Section XI Code. Based on guidance provided in NUREG-1022, Rev. 2, this material defect in the primary coolant boundary constitutes a seriously degraded condition and is reportable under 10CFR50.72(b)(3)(ii)(A). A final evaluation of the flaw and a repair plan is being developed."

The licensee informed the NRC Resident Inspector.

*****RETRACTED ON 4/29/04 AT1018 FROM HUFFORD TO LAURA*****

"On March 23, 2004, PPL Susquehanna, LLC reported a material defect discovered on the N1B penetration associated with the suction for the B Loop of Reactor Recirculation. The defect was discovered during routine inservice inspection of the reactor vessel. At the time of the report, the indication was believed to exceed the acceptability standards of ASME Section XI, IWB-3640. Accordingly, an ENS call was made pursuant to the reporting requirements of 10CFR50.72(b)(3)(ii)(A). Engineering analysis subsequently determined that the dimensional characteristics of the flaw were within the acceptability requirements of ASME Section Xl. This analysis conclusion provides the basis for retraction of the ENS report of March 23.

"Although hypothetical flaw growth calculations demonstrated that the flaw size would remain within the allowable envelope of ASME Section Xl, IWB-3641-1 over the next operating cycle, and continued operation without repair of the observed flaw was justified, PPL Susquehanna, LLC performed a weld repair of the defect during the recently completed refueling outage."

Notified the R1DO (R. Barkley)

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Fuel Cycle Facility Event Number: 40641
Facility: PADUCAH GASEOUS DIFFUSION PLANT
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
                   6903 ROCKLEDGE DRIVE
                   BETHESDA, MD 20817 (301)564-3200
Region: 2
City: PADUCAH State: KY
County: McCRACKEN
License #: GDP-1
Agreement: Y
Docket: 0707001
NRC Notified By: KEVIN BEASLEY
HQ OPS Officer: MIKE RIPLEY
Notification Date: 04/05/2004
Notification Time: 01:40 [ET]
Event Date: 04/04/2004
Event Time: 14:30 [CDT]
Last Update Date: 04/29/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
RESPONSE-BULLETIN
Person (Organization):
JOEL MUNDAY (R2)
SCOTT MOORE (NMSS)

Event Text

24-HOUR NRC BULLETIN 91-01 LOSS OF CRITICALITY CONTROL NOTIFICATION

"At 1430, on 04-04-04 the Plant Shift Superintendent was notified of a violation of Nuclear Criticality Safety (NCS) control in the C-333 process building. While preparing for start up of the C-333 #1 High Speed Purge and Evacuation (P & E) pump, operations discovered that the delta pressure (DP) alarm instrument line to the RCW supply was unattached and the isolation valve was closed. With the RCW instrument line not attached, both DP alarms for this pump were not functional and therefore not able to perform their safety function, violating a safety related item (SRI) in NCSE 039. The SRI requires that both DP alarms be functional while the P & E is isolated from the cascade. The purpose of the SRI Is to alert the operator to take actions within a 28-hour timeframe to prevent wet R-114 from leaking into the process gas system. The DP alarms had been nonfunctional for more than 28 hours when discovered. Both DP alarms were put back in service and the R-114 sampled and found dry within 4 hours of discovery, therefore, re-establishing double contingency.

"The Senior NRC Resident Inspector has been notified of this event."

"PGDP Problem Report No, ATR-04-1342; PGDP Event Report No. PAD-2004-09; Event Worksheet #40641 Responsible Division: Operations

"SAFETY SIGNIFICANCE OF EVENTS: While the R-114 was demonstrated to be dry, both DP alarms relied on for double contingency were disabled without the knowledge of the operators.

"POTENTIAL CRITICALITY PATHWAYS INVOLVED: In order for a criticality to occur, an unsafe mass uranium deposit would have to be present in the process gas system, an R-114 leak to the process gas system would have to occur, the R-114 would have to contain an unacceptable amount of moisture ( i.e., greater than 10 kg of water) and moderate the deposit.

"CONTROLLED PARAMETERS (MASS, MODERATION, G5OMETRY, CONCENTRATION, ETC): Double contingency is maintained by implementing two controls on moderation.

"ESTIMATED AMOUNT, ENRICHMENT, FORM OF LICENSED MATERIAL: No known mass of licensed material exists in the #1 High Speed Purge and Evacuation pump.

"NUCLEAR CRITICALITY SAFETY CONTROL(S) OR CONTROL SYSTEM(S) AND DESCRIPTION OF THE FAILURES OR DEFICIENCIES: The first leg of double contingency is based on the DP switch alarming to alert the operator to take action to either verify the R-114 is dry or to isolate the RCW and remove the R-114 from the system in order to prevent water from leaking into the process gas system. This DP alarm was not maintained as functional. The DP alarm was put back in service and the R-114 was sampled and found to be dry. The SRI was not maintained and the control was violated but the process condition was maintained.

"The second leg of double contingency is based on the independent DP switch alarming to alert the operator to take action to either verify the R-114 is dry or to isolate the RCW and remove the R-114 from the system in order to prevent water from leaking into the process gas system. The independent DP alarm was not maintained as functional. The independent DP alarm was put back in service and the R-114 was sampled and found to be dry. The SRI was not maintained and the control was violated but the process condition was maintained. This re-established double contingency.

"CORRECTIVE ACTIONS TO RESTORE SAFETY SYSTEMS AND WHEN EACH WAS IMPLEMENTED: Both DP switches were returned to service and the R-114 was sampled and found to be dry on 04-04-04 at 1655."

* * * UPDATE 4/29/04 AT 1025 BEASLEY TO GOTT * * *

"Subsequent assay sample analysis of the Purge and Evacuation pump system indicates the system is non-fissile."

The PGDP notified the NRC Resident Inspector.

Notified NMSS (Torres) and R2DO (Ernstes)

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 40706
Facility: MCGUIRE
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN JENKINS
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/27/2004
Notification Time: 09:21 [ET]
Event Date: 04/26/2004
Event Time: 09:30 [EDT]
Last Update Date: 04/29/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
CAUDLE JULIAN (R2)

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

NON-LICENSED EMPLOYEE TESTED POSITIVE FOR CONTROLLED SUBSTANCE

A non-licensed employee was determined to be under the influence of an illegal drug during a random urinalysis. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details.

The licensee notified the NRC Resident Inspector.

* * * UPDATE ON 4/27/0 JENKINS TO GOULD * * *
Contact the Headquarters Operations Officer for details of update.

Notified the Reg 2DO (Ernstes) of update.

* * * RETRACTION ON 4/29/04 HEAFNER TO GOTT * * *

Event retracted. Contact the Headquarters Operations Officer for details.

The Licensee notified the NRC Resident Inspector.

Notified R2DO (Ernstes)

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General Information or Other Event Number: 40708
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: UCLA MEDICAL CENTER
Region: 4
City: TORRANCE State: CA
County:
License #: 0369-19
Agreement: Y
Docket:
NRC Notified By: KATHLEEN KAUFMAN
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 04/27/2004
Notification Time: 16:06 [ET]
Event Date: 03/19/2004
Event Time: 11:30 [PDT]
Last Update Date: 04/27/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CHARLES MARSCHALL (R4)
ROBERTO TORRES (NMSS)

Event Text

A STATE OF CALIFORNIA LICENSEE HAS LOST A CESIUM 137 SEED

The licensee reported that at approximately 1130 am the physicist was involved in removal of cesium 137 seeds from an implant The seeds were counted and accounted for in the patient's room after removal. They were then brought to the radiation oncology hot lab for placement into the safe. While removing them from the "Heyman Carrier" the physicist encountered some difficulty with one of the seeds which resulted in its being "flung" behind the counter in the hot lab and "lost." The Radiation Safety Office was notified and an initial search for the seed (activity 10 mg Ra equivalent - 25 millicuries) did not locate it.

The same afternoon the RSO presumably located the seed lodged in the crack of the counter. Because of its location the counter was required to be taken apart. The State was informed by RSO on April 26, 2004 that final retrieval will be made in approximately two weeks when they receive their new counter table and safe so that the remaining seeds can be removed and present counter cut to retrieve the lost seed.

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Power Reactor Event Number: 40714
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: KEN HILL
HQ OPS Officer: RICH LAURA
Notification Date: 04/29/2004
Notification Time: 01:40 [ET]
Event Date: 04/28/2004
Event Time: 22:30 [EDT]
Last Update Date: 04/29/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
MIKE ERNSTES (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 96 Power Operation 96 Power Operation

Event Text

HPCI SYSTEM INOPERABLE FOLLOWING PLANNED MAINTENANCE

"During post maintenance testing following a High Pressure Coolant Injection (HPCI) System outage, the HPCI System was not declared operable due to unstable operation - oscillations of turbine speed (300-400 RPM), pump flow (600 GPM) and discharge pressure (300-550 psig) were seen in both automatic and manual flow control during the System Operability Periodic Test. HPCI had been declared inoperable at 0410 on 4/28/04 and placed under clearance to support planned maintenance on the Flow Controller, Flow Transmitter, system valves and condensate pump. The cause of the unstable operation is currently being investigated."

The licensee notified the NRC Resident Inspector.

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Other Nuclear Material Event Number: 40715
Rep Org: COGEMA MINING INC
Licensee: COGEMA MINING INC
Region: 4
City: MILLS State: WY
County:
License #: SUA-1341
Agreement: N
Docket:
NRC Notified By: TOM NICHOLSON
HQ OPS Officer: RICH LAURA
Notification Date: 04/29/2004
Notification Time: 11:03 [ET]
Event Date: 04/28/2004
Event Time: 15:00 [MDT]
Last Update Date: 04/29/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
Person (Organization):
CHARLES MARSCHALL (R4)
JOHN HICKEY (NMSS)

Event Text

MINOR WASTE POND LEAKAGE AT COGEMA MINING

The licensee reported the discovery of minor leaks detected in two of four surface evaporator waste ponds used as a portion of an uranium milling process. Each pond has a leak detection system which is checked once per week. The minor leaks were detected on 4/28/04 indicating some minor leakage through the pool liner. The licensee stated there was no release of liquid to the environment. Corrective actions planned are to pump down the two ponds and inspect and repair the liner as needed. This report was made pursuant to License Condition 11.4 which specifies to notify the NRC of any spills or leaks. The licensee also notified the Wyoming Department of Environmental Quality.

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Power Reactor Event Number: 40716
Facility: COOK
Region: 3 State: MI
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Bud Hinckley
HQ OPS Officer: MIKE RIPLEY
Notification Date: 04/29/2004
Notification Time: 18:09 [ET]
Event Date: 04/29/2004
Event Time: 15:57 [EDT]
Last Update Date: 04/29/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
Person (Organization):
BRUCE BURGESS (R3)
TAD MARSH (NRR)
SUSAN FRANT (DIRO)

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

IDENTIFIED LEAKAGE LIMIT EXCEEDED FOR 5 MINUTE PERIOD DUE TO LIFTED LETDOWN LINE SAFETY VALVE

"D.C. Cook Unit 2 was performing post-maintenance testing on a solenoid valve associated with a letdown orifice valve and realigning letdown flowpath when safety valve 2-SV-51 (Regenerative Heat Exchanger Letdown Outlet Safety Valve) lifted on 4/29/04 at 15:57 EDT, relieving 323 gallons of water to the Pressurizer Relief Tank over a five (5) minute period before letdown was isolated. Average leak rate was approximately 65 gallons per minute, greater than the 25 gallon per minute identified leak rate limit for an Unusual Event [10CFR50.72(a)(1)(i)]. This was a rapidly concluded event of a five (5) minute duration. Time of discovery for leakage quantity and reportability was 17:10 on 4/29/04.

"Therefore, for a five (5) minute period, D.C. Cook Unit 2 met the conditions for an Unusual Event. However, this fact was discovered after leakage was stopped. Unit 2 is stable at approximately 100% reactor thermal power with the excess letdown system in service.

"An Unusual Event was NOT declared, but the conditions for an Unusual Event were met between 15:57 and 16:02 on 4/29/04. This ENS notification is being made within one hour of the discovery of the undeclared event."

The licensee notified the NRC Resident Inspector.

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