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Event Notification Report for March 16, 2004

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
03/15/2004 - 03/16/2004

** EVENT NUMBERS **


40519 40581 40582 40584 40588 40589 40590 40591

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 40519
Facility: WATERFORD
Region: 4 State: LA
Unit: [3] [ ] [ ]
RX Type: [3] CE
NRC Notified By: GREG SCOTT
HQ OPS Officer: ERIC THOMAS
Notification Date: 02/13/2004
Notification Time: 20:32 [ET]
Event Date: 02/13/2004
Event Time: 05:25 [CST]
Last Update Date: 03/15/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
Person (Organization):
CHUCK CAIN (R4)

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

Event Text

24 HOUR NOTIFICATION PER LICENSEE CONDITION 2.F

"On February 13, 2004, Waterford 3 reactor power reached an estimated maximum reactor power level of 101.9% due to Atmospheric Dump Valve #2 (ADV#2) failing full open. ADV#2 failed open due to the control system setpoint failing low. Operations personnel promptly responded to the condition by reducing turbine load (5 megawatts per minute ) and manually closing ADV#2, to restore plant power. ADV#2 was open for less than a minute. Per the FSAR, this transient is an analyzed event and is bounded by the safety analyses. This event is being reported in accordance with Waterford 3 event notification and reporting procedure, UNT-006-010, which is more conservative than the guidance provided in NRC Inspection Procedure 61706. This event is being reported pursuant to Waterford 3 License Condition 2.F as a 24 hour notification."

The licensee notified the NRC Resident Inspector.

* * * RETRACTION FROM R. MURILLO TO M. RIPLEY 2100 ET ON 03/15/04 * * *

"On February 13, 2004, Waterford 3 provided a 24 hour notification to the NRC (reference EN# 40519) stating that due to a failed open atmospheric dump valve, plant reactor power level momentarily reached a value of 101.9%. The event was reported conservatively based on the guidance provided in the plant's event notification and reporting procedure. The procedure has been revised to incorporate the guidance provided by NRC inspection Procedure 61706, 'Core Thermal Power Evaluation.' Based on this guidance, reporting of events such as stated above (transient power increases) are not required unless reactor power level exceeds 102%. Accordingly, this event is not reportable as power level only reached 101.9% momentarily.

"Based on the above, the 24 hour notification made on 2/13/2004 is being retracted."

The licensee has notified the NRC Resident Inspector. Notified R4 DO (J. Clark)

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General Information or Other Event Number: 40581
Rep Org: MARYLAND DEPT OF THE ENVIRONMENT
Licensee: INDEPENDENT CONSULTANTS AND ENGINEERING
Region: 1
City: FRIENDLY State: MD
County: PRINCE GEORGES
License #: MD-33-154-01
Agreement: Y
Docket:
NRC Notified By: BOB NELSON
HQ OPS Officer: BILL GOTT
Notification Date: 03/10/2004
Notification Time: 15:10 [ET]
Event Date: 03/09/2004
Event Time: 14:00 [EST]
Last Update Date: 03/10/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
EUGENE COBEY (R1)
FRED BROWN (NMSS)

Event Text

AGREEMENT STATE REPORT - DAMAGED MOISTURE DENSITY GAUGE

A dump truck ran over a Campbell Pacific Nuclear moisture density gauge at 1400 EST on 3/9/10 in Friendly, MD. The gauge had a 10 millicuries Cs-137 and 40 millicuries Am-241:Be source, serial number AM7147. The sources were intact and were packaged and shipped back to the licensee, Independent Consultants and Engineers of Upper Marlboro, MD. There was no detected leakage. The Gauge serial number is MD-30907147.

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General Information or Other Event Number: 40582
Rep Org: ILLINOIS EMERGENCY MGMT. AGENCY
Licensee: LOYOLA UNIVERSITY OF CHICAGO
Region: 3
City: CHICAGO State: IL
County:
License #: IL-01695-01
Agreement: Y
Docket:
NRC Notified By: JOE KLINGER
HQ OPS Officer: BILL GOTT
Notification Date: 03/10/2004
Notification Time: 18:32 [ET]
Event Date: 03/09/2004
Event Time: [CST]
Last Update Date: 03/10/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
KENNETH RIEMER (R3)
EUGENE COBEY (R1)
JOHN GREEVES (NMSS)

Event Text

AGREEMENT STATE REPORT - REMOVABLE CONTAMINATION ON RECEIVED PACKAGE

"Loyola University of Chicago, a broadscope academic licensee, notified the agency that a package containing two vials of Phosphorous-32 was found to contain levels of removable P-32 contamination in excess of the regulatory limits. The package was received on Friday, March 5, 2004 and surveyed on Tuesday, March 9. 315,000 dpm/100 square centimeters was measured using a pancake probe. A swipe of an area on the exterior surface of the package was found to contain 26,000 dpm/100 square centimeters. This exceeds the maximum allowable level of 22,000 dpm/100 sq centimeters removable contamination. Further examination of the package revealed that contamination was also found on a plastic bag containing an inner container and the vials of liquid P-32 (1 vial contained 500 microcuries, the other 250 microcuries) and on the exterior surface of the inner plastic container. The contamination measured on the items on the interior of the package ranged from a maximum of 4,700 dpm to 120 dpm/ 100 sq centimeters. However, the interior of the inner container and the exterior surfaces of the vials were not contaminated. The consultant performed surveys of the area where the package was opened and no additional contamination was noted. The shipper was Perkin-Elmer, Boston, MA. The carrier was Airborne Express.

"The licensee notified the shipper, Perkin Elmer, and Airborne Express. The Hazmat representative for Airborne Express, contacted the Agency and stated that Airborne Express is currently trying to perform radiation surveys of all ground vehicles and the two planes involved in transport of this package. The package was transferred via Airborne Ground transportation from the Perkin Elmer Boston, MA, facility and transferred to a plane at Boston's airport. It was then flown to the Airborne facility in Wilmington, Ohio. The package was later flown to Chicago O'Hare then transported via Airborne Express Ground vehicle to the Illinois licensee's facility.

"The MA radiation control program also contacted the Illinois radiation control program and discussed this matter. The licensee's consultant is currently conducting additional surveys of the Illinois facility to see if any additional P-32 contamination can be found. The Agency will also perform independent surveys and an investigation to try to determine the source of contamination." Illinois report number IL040012.

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General Information or Other Event Number: 40584
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: XRI TESTING
Region: 4
City: LAFAYETTE State: LA
County:
License #: LA-2918-L01
Agreement: Y
Docket:
NRC Notified By: SCOTT BLACKWELL
HQ OPS Officer: STEVE SANDIN
Notification Date: 03/11/2004
Notification Time: 14:41 [ET]
Event Date: 01/30/2004
Event Time: [CST]
Last Update Date: 03/11/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
TROY PRUETT (R4)
TOM ESSIG (NMSS)

Event Text

RADIOGRAPHER MAY HAVE EXCEEDED ANNUAL EXPOSURE LIMIT

"XRI reported that [a radiographer] received an annual exposure of 6.120 R for the year of 2003. [The Radiographer] had a dose of 4.016 R prior to December of 2003. [The Radiographer] received a dose of 2.104 R for December 2003. Once the badge results were discussed with [the Radiographer] in January of 2004, he stated that his badge had dropped near a source. [The Radiographer] did not feel that it needed to be reported at that time because of the distance from the source. According to the facilities files [the Radiographer] received 0.315 R for the month of December 2003. As a result of this incident there have been some additional steps taken to prevent reoccurrence. All radiographers have been retrained. Also if a radiographer receives a dose of 4.0 R by December, that radiographer will not be allowed to perform radiograph operations until the next calendar year. If that limit is reached prior to that date, the radiographer may be granted specified permission to work on monitored low production jobs."

LA Report ID No.: LA040003

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Power Reactor Event Number: 40588
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [ ] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: GLENN BRIDGES
HQ OPS Officer: MIKE RIPLEY
Notification Date: 03/15/2004
Notification Time: 14:13 [ET]
Event Date: 03/15/2004
Event Time: 10:30 [EST]
Last Update Date: 03/15/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
HAROLD GRAY (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 3 Startup 0 Startup

Event Text

SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS DUE TO INOPERABLE ISOLATION INSTRUMENTATION

"During the planned shutdown for RFO9, the Reactor Water Clean Up (RWCU) Differential Flow Signals and the Reject Flow indicator did not receive a signal from the transmitters associated with the reject flow path from the reactor to the condenser in the RWCU system. Maintenance was contacted and the differential flow timers associated with these control loops were removed per operating procedure N2-OP-37 for the RWCU system and the Technical Specification Required Action for both required channels of Functions 4a and 4b in table 3.3.6.1-1 being inoperable was entered. This was required to allow venting of the transmitters and prevented an inadvertent isolation signal of the RWCU system.

"These primary containment isolation instruments were declared inoperable at 0830 on 3/15/2004. CONDITION B of LCO 3.3.6.1 was entered, which requires isolation capability to be restored in 1 hour. At 0930 on 3/15/04, CONDITIONS C and F were entered which require system isolation in one hour.

"At 1025, maintenance was completed; however, all post maintenance testing was not complete. At 1030, on 3/15/04 CONDITION F was not met and CONDITION H was entered. CONDITION H requires the unit be in MODE 3 in 12 hours and in MODE 4 in 36 hours.

"Since the unit was in a planned shutdown, with negative reactivity being inserted, it was unclear whether the entry into CONDITION H of Technical Specification 3.3.6.1 would have required actual insertion of negative reactivity for this situation. Thus, as a conservative action, NMPNS is reporting this event pursuant to 50.72(b)(2)(i) 'The initiation of any nuclear plant shutdown required by Technical Specifications.'

"The Differential flow timers were installed at 1129 on 3/15/04 with the plant in MODE 2. Operating procedures require a CHANNEL FUNCTION TEST prior to a declaration of operability, The CHANNEL FUNCTIONAL TEST is in progress."

The licensee notified the NRC Resident Inspector

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Power Reactor Event Number: 40589
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BILL HARRIS
HQ OPS Officer: MIKE RIPLEY
Notification Date: 03/15/2004
Notification Time: 17:13 [ET]
Event Date: 03/15/2004
Event Time: 15:18 [EST]
Last Update Date: 03/15/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
DAVID AYRES (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 100 Power Operation 0 Hot Standby

Event Text

AUTOMATIC REACTOR TRIP DUE TO MAIN GENERATOR ELECTRICAL FAULT SIGNAL

"At 1518 on 3/15/04, Unit 1 Reactor tripped due to a Main Turbine trip. The Main Turbine tripped due to a Main Generator electrical fault, Auxiliary Feedwater (AFW) started when both Main Feedwater Pumps tripped on Low Tave Feedwater isolation. The AFW start was expected on the Reactor Trip. All safety systems performed as required. Investigation is in progress to determine and correct the cause of this trip."

All control rods fully inserted; the electrical grid is stable; ECCS systems remain operable; decay heat is being removed via AFW and steam dumps. The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 40590
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [ ] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: ANDY NEWTON
HQ OPS Officer: MIKE RIPLEY
Notification Date: 03/15/2004
Notification Time: 18:40 [ET]
Event Date: 03/15/2004
Event Time: 13:30 [EST]
Last Update Date: 03/15/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
DAVID AYRES (R2)

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

Event Text

CONTRACT SUPERVISOR FITNESS FOR DUTY

At 1330 ET on 3/15/04, it was determined that a contract supervisor had tested positive for drugs on an access reinstatement urinalysis test. Access has been denied. The individual had only been badged for one day. A work review was conducted and no safety-related activities had been performed. Contact HOO for additional details.

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 40591
Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: SUNYOUNG KWON
HQ OPS Officer: RICH LAURA
Notification Date: 03/15/2004
Notification Time: 20:57 [ET]
Event Date: 03/15/2004
Event Time: 20:20 [EST]
Last Update Date: 03/15/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
HAROLD GRAY (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 A/R Y 100 Power Operation 0 Hot Standby

Event Text

AUTOMATIC REACTOR TRIP AT MILLSTONE 2 DUE TO SPURIOUS LOSS OF ONE MAIN FEED PUMP

The licensee reported that an automatic reactor trip occurred on 3/15/04 at 2020 EST due to the spurious trip of one main feed pump which caused a low steam generator water level trip signal. The plant has two main feed pumps. Operators reset the tripped main feed pump but steam generator levels didn't recover in time. The lowest level observed was in the "B" steam generator at 15% level as compared to the normal level of 65%. The trip setpoint is at 50% level. All control rods properly inserted into the core. The auxiliary feed water system automatically initiated as designed and expected. The plant remains stable in mode 3 while the licensee commenced the post trip review to determine the cause of the main feed pump trip. Decay heat removal was established using the AFW system to feed steam generators and bleed steam to the main condenser through the condenser dump valves.

The licensee notified the NRC Resident Inspector.

Page Last Reviewed/Updated Friday, March 30, 2012
Friday, March 30, 2012