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Event Notification Report for September 30, 2004

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
09/29/2004 - 09/30/2004

** EVENT NUMBERS **


40982 41075 41076 41080

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General Information or Other Event Number: 40982
Rep Org: GENERAL ELECTRIC COMPANY
Licensee: GENERAL ELECTRIC COMPANY
Region: 1
City: WILMINGTON State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JASON S. POST
HQ OPS Officer: MIKE RIPLEY
Notification Date: 08/24/2004
Notification Time: 17:36 [ET]
Event Date: 08/24/2004
Event Time: [EDT]
Last Update Date: 09/30/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
EUGENE COBEY (R1)
JOEL MUNDAY (R2)
ERIC DUNCAN (R3)
WILLIAM JOHNSON (R4)
VERN HODGE (NRR)

Event Text

PART 21 REPORTABLE CONDITION AND 60-DAY INTERIM REPORT NOTIFICATION: NON-CONSERVATIVE SAFETY LIMIT MINIMUM CRITICAL POWER RATIO

Global Nuclear Fuel (GNF) and GE Nuclear Energy (GENE) have determined that the current GNF process for determination of the Safety Limit Minimum Critical Power Ratio (SLMCPR) can result in a non-conservative SLMCPR. GENE has historically used a non-conservative SLMCPR impact of 0.01 as the threshold for reportability under 10CFR21. A preliminary screening evaluation has been completed for all plants operating with a SLMCPR calculated by GNF to determine those that have a nonconservative impact of 0.01 or greater. Verification has been completed for those plants that the screen showed to have a non-conservative SLMCPR impact of 0.01 or greater. Verification has not been completed for the plants that the screen showed had an impact of less than 0.01 or were unaffected, thus requiring a 60-Day Interim Report notification pending verification completion.

The plants for which GNF calculates the SLMCPR are identified [below]. Those plants for which the preliminary screen indicated that the current SLMCPR is unaffected are identified as a 60-Day Interim Report. Upon completion of verification (assuming the results of the screen are confirmed) the status of these plants will be changed to Not Reportable. GENE will provide a follow-up report to the NRC by September 29, 2004. The plants for which the current SLMCPR is non-conservative by 0.01 or greater are identified as a Reportable Condition under 10CFR21.21(d). These plants will take action to address the Reportable Condition.

GNF has notified all plants that have been confirmed to be affected. The plants that have a non-conservative SLMCPR for current plant operation will take action to mitigate the potential impact. Depending on the specific circumstances, mitigating actions to protect the SLMCPR may include increasing the OLMCPR to assure compliance with the low flow calculated SLMCPR. In some cases sufficient conservatism may exist in the OLMCPR at low flow to bound the increased SLMCPR. Each affected plant will notify the NRC and take appropriate action if their Technical Specifications are affected.

There are no actions necessary for the plants that are unaffected pending completion of verification. If, in the course of verification, GNF determines that there is an impact, the affected utility will be notified immediately. GNF will complete the verification and GENE, will provide a follow-up letter to the NRC by September 29, 2004.

Affected and 60-Day Interim Notification Plants:

60-Day Interim Report: Clinton, Oyster Creek, Brunswick 1, Brunswick 2, Nine Mile Point 2, Fitzpatrick (60-Day interim report for current operation, Reportable Condition for SLMCPR licensing submittal), Pilgrim, Vermont Yankee, Dresden 2, Dresden 3, LaSalle 1, LaSalle 2, Limerick 1, Limerick 2, Peach Bottom 2, Peach Bottom 3, Quad Cities 1, Quad Cities 2, Perry 1, Duane Arnold, Monticello, Hope Creek, Hatch 1, Hatch 2, Browns Ferry 2

Reportable Condition: Nine Mile Point 1, Fermi 2, Fitzpatrick (60-Day interim report for current operation, Reportable Condition for SLMCPR licensing submittal), Cooper.

* * * UPDATE FROM JASON POST (VIA FAX) TO CROUCH @ 2354 HRS. EST ON 09/29/04 * * *

In part, the update reads:

"The evaluation for the potentially unaffected plants has now been completed. The results of the screening calculation have been confirmed: this is not a reportable condition for the plants that were previously identified as a 60-Day Interim Report notification in MFN 04-081" (See above).

Notified R1DO(Rogge), R2DO(Lesser), R3DO(Kozak), R4DO(Howell) and NRREO(Hodges).

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General Information or Other Event Number: 41075
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: PROFESSIONAL SERVICE INDUSTRIES, INC.
Region: 1
City: Haines City State: FL
County: Polk County
License #: 0022-17
Agreement: Y
Docket:
NRC Notified By: CHARLES ADAMS
HQ OPS Officer: JOHN MacKINNON
Notification Date: 09/27/2004
Notification Time: 11:25 [ET]
Event Date: 09/27/2004
Event Time: 00:00 [EDT]
Last Update Date: 09/27/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JOHN CARUSO (R1)
TOM ESSIG (NMSS)
MATTHEW HAHN (TAS)

Event Text

STOLEN TROXLER MOISTURE DENSITY GAUGE

"Metal ship container was broken into and the gauge was stolen. It was last seen close of business on Friday the 24th and discovered stolen Monday the 27th. The keys were not taken. The Haines City PD has been notified. Owner will offer a $500 reward. Florida is investigating."

Incident Location: HWY 27, 5 miles south if I-4 (Polk County near Haines City) Temp work storage site.

Troxler: Model number 3430' 8 millicuries of cesium-137 and 40 millicures of Am-241/Be. Serial number of the gauge is 27404.

License type: Specific; 3L(1).

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Power Reactor Event Number: 41076
Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: TONY CHITWOOD
HQ OPS Officer: BILL GOTT
Notification Date: 09/28/2004
Notification Time: 13:44 [ET]
Event Date: 09/28/2004
Event Time: 10:30 [PDT]
Last Update Date: 09/29/2004
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
LINDA HOWELL (R4)
SUZANNE BLACK (NRR)
SUSAN FRANT (IRD)
JUNE PAULEY (DHS)
BOB CAULDWELL (FEMA)
STEVE BAILEY (DOE)

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

UNUSUAL EVENT DECLARED DUE TO SEISMIC ACTIVITY

"Earthquake felt at plant site [at 1015 PDT] registering 0.012 g. No damage on plant site noted. Release to the environment remains within normal operating levels, and effluent radiation monitors did not alarm. No protective action required."

The Licensee notified the NRC Resident Inspector.

* * * UPDATE FROM T. CHITWOOD TO W. GOTT AT 1428 EDT ON 09/28/04 * * *

"Plant walk down in progress. No damage noted." The Licensee notified the NRC Resident Inspector.

* * * UPDATE FROM GLENN COELZER TO MACKINNON AT 2132 EDT ON 09/28/04

Information Call: No plant damage detected by walk downs or equipment testing. R4DO (Linda Howell) notified.

The Licensee will notify the NRC Resident Inspector.

* * * UPDATE FROM JEFF KNISLEY TO CROUCH AT 0313 EDT ON 09/29/04 * * *

Information Call: No plant damage detected by walk downs or equipment testing.

The licensee notified the NRC Resident Inspector. R4DO(Howell) will be notified.

* * * UPDATE FROM GLENN GOELZER TO W GOTT AT 1532 EDT ON 9/29/04 * * *

The licensee terminated the NOUE at 1215 PDT. "No plant damage has been detected by plant walkdowns or equipment testing." NRC exited Monitoring at 1600 EDT

Notified R4DO (L Howell), NRR (Skeen, Borchardt), IRD (Frant, Wilson), Chairman Office (Holahan), EDO (Mitchell), PAO, Dir of Comm. (Outlaw), DHS (Morison), FEMA (Caldwell), USDA (Thomas), DOE (Wyatt), NRC DOT (Crews), and HHS (R. Harlan)

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Power Reactor Event Number: 41080
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: STEVE PRUSSMAN
HQ OPS Officer: JOHN MacKINNON
Notification Date: 09/29/2004
Notification Time: 14:37 [ET]
Event Date: 09/29/2004
Event Time: 11:00 [EDT]
Last Update Date: 09/29/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
JOHN ROGGE (R1)

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

Event Text

RANDOM FITNESS FOR DUTY TEST

A random fitness for duty test determined that an Entergy Supervisor tested positive for alcohol. This was confirmed under the fitness for duty program at approximately 1100 hours. A work history review has been conducted and no work or behavioral issues identified. Removal of access authorization was not established.

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

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