Skip to main content

Event Notification Report for November 06, 2001

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
11/05/2001 - 11/06/2001

EVENT NUMBERS
384693847138472

Other Nuclear Material
Event Number: 38469
Rep Org: MALLINCKRODT
Licensee: MALLINCKRODT
Region: 3
City: MARYLAND HEIGHTS   State: MO
County:
License #: 240420601
Agreement: N
Docket:
NRC Notified By: LINDA GRAHAM
HQ OPS Officer: FANGIE JONES
Notification Date: 11/06/2001
Notification Time: 10:50 [ET]
Event Date: 11/06/2001
Event Time: 09:15 [CST]
Last Update Date: 11/06/2001
Emergency Class: ALERT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
ANN MARIE STONE (R3)
CHARLIE MILLER (IRO)
RICHARD JOLLIFFE (RCT)
DOUGLAS BROADDUS (NMSS)
DOE, EPA, USDA (FAX)
Event Text
ALERT DECLARED DUE TO FIRE IN DECON AREA

An Alert was declared at 0915 CST due to a fire in Decon Area 2 in Building 600. The fire was smoke only, from an autoclave where a process of depyrogeneration of Mo-99 glassware was taking place. There was a piece of tygon tubing in the autoclave which became involved, producing the smoke. The Alert was exited at 0940 CST when the fire was out. There was no release to the environment and air samples taken in the laboratory showed no detectable activity.

The Maryland Heights Fire Department responded to the site.


Power Reactor
Event Number: 38471
Facility: NINE MILE POINT
Region: 1     State: NY
Unit: [] [2] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: D. CIFONELLI
HQ OPS Officer: JOHN MacKINNON
Notification Date: 11/06/2001
Notification Time: 14:01 [ET]
Event Date: 11/06/2001
Event Time: 11:32 [EST]
Last Update Date: 11/06/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
Person (Organization):
R1 IRC TEAM MANAGER (R1)
Power Reactor Unit Info
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
24-HOUR REPORT IN ACCORDANCE WITH OPERATING LICENSE DUE TO POTENTIAL MAXIMUM POWER LEVEL VIOLATION.

"This report is being made in accordance with Nine Mile Point Nuclear Station, Unit 2 Operating license No. NPF-69 Section 2.F, which in part states the following; "... shall report any violations of the requirements contained in section 2.C of this license in the following manner: initial notification shall be made within 24 hours to the NRC Operations Center via the Emergency Notification System, with written follow-up within 30 days in accordance with the procedures described in 10CFR 50.73 (b), (c), and (e)."

"The following text is an excerpt of a facsimile received by the licensee:

"General Electric (GE) report titled, Impact of Steam Carryover Fraction on Process Computer Heat Balance Calculation , September 2001, documents a non-conservative constant for moisture carryover fraction in the equation used to calculate plant heat balance. The report states that a number of later model GE BWR plants have moisture carryover fractions of less than 0.003%. Nine Mile Point Unit 2's heat balance assumed a 0.003% moisture carryover factor.

"Based on the above report from GE, on October 1, 2001 at 1926 hours Nine Mile Point Unit 2 implemented an Interim administrative power level limit of 3465 MWt (2 MWt less than the license limit of 3467 MWt) to conservatively account for a potential lower moisture carry over factor. in addition, a sample time period was reviewed to determine whether the Maximum Power level was exceeded while the non-conservative constant was in place. This review determined that on August 20, 2001 from 12:03 to 23:59 hours the Maximum Power Level Limit (3467 MWt) was exceeded by approximately 2 MWt. The time that Maximum Power Level was exceeded was previous to he date that NMP 2 was notified by GE of the potential non-conservative moisture carryover factor. Since the interim administrative limit has been implemented NMP 2 has not exceeded its Maximum Power Level. Additionally, the method used to calculate NMP 2's heat balance has been revised to eliminate the non-conservative moisture carryover factor."

The NRC Resident Inspector was notified of this event by the Licensee.

(Refer to event numbers 38330, 38337, 38340, 38344, 38445, 38347, 38349, and 38357 for similar events at Fermi, Perry, Hope Creek, Grand Gulf, Columbia Generating Station, Limerick 2, River Bend, and Limerick 1.)


Power Reactor
Event Number: 38472
Facility: BEAVER VALLEY
Region: 1     State: PA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: SAM CHECKETTS
HQ OPS Officer: JOHN MacKINNON
Notification Date: 11/06/2001
Notification Time: 15:38 [ET]
Event Date: 11/06/2001
Event Time: 14:16 [EST]
Last Update Date: 11/06/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
R1 IRC TEAM MANAGER (R1)
Power Reactor Unit Info
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 ON LOW-LOW STEAM GENERATOR WATER LEVEL.

"At 14:16 Unit One Reactor automatically tripped due to low-low level in the 1C Steam Generator. Feed Water Control Valve (FCV-FW-498) failed closed causing the 1C steam generator level to rapidly drop and reach the low-low level trip setpoint. All Control Rods fully inserted and all required equipment functioned properly. The plant is currently stable in mode 3 at normal pressure and temperature. Decay Heat removal is via the Steam Bypass valves. Normal and Auxiliary Feed Water systems are in service. Cause of the failure under investigation" Emergency Core Cooling Systems, Emergency Diesel Generators are fully operable if needed and the electrical grid is stable.

The NRC Resident Inspector was notified of this event by the licensee.