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Event Notification Report for May 27, 2004

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
05/26/2004 - 05/27/2004

** EVENT NUMBERS **


40763 40770 40776 40777 40778

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General Information or Other Event Number: 40763
Rep Org: MISSISSIPPI DIV OF RAD HEALTH
Licensee: IMAGING CENTER OF COLUMBUS
Region: 1
City: COLUMBUS State: MS
County:
License #: MS-327-01
Agreement: Y
Docket:
NRC Notified By: B. J. SMITH
HQ OPS Officer: JOHN MacKINNON
Notification Date: 05/21/2004
Notification Time: 12:28 [ET]
Event Date: 05/20/2004
Event Time: 11:00 [CDT]
Last Update Date: 05/21/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JOHN CARUSO (R1)
LINDA PSYK (NMSS)

Event Text

MISSISSIPPI AGREEMENT STATE REPORT: LEAKING SOURCE

Description of Incident: Approximately 11:00 central time on 5-20-04, The Division of Radiological Health, MS State Dept. of Health, was notified that a leaking Cesium 137 source was found when a consultant was preparing sealed sources for disposal. The leaking source was found in the bottom of a storage container (original pig from Du Pont) that was used to store a Du Pont Merck Model NER-401H 592 microcurie Cs-137 dose calibrator source. The leaking source was found after the dose calibrator source had been removed from the storage pig and determined to be free of contamination. The leaking source was discovered in a crack at the bottom of the storage pig and was in excess of .005 microcuries removable contamination. A consultant stated that the leaking source appeared to be about the size of a pencil lead. Instead of trying to remove the contaminated source from the pig, he put epoxy in the pig to seal it in place to ready it for disposal. He estimated that the source was probably used as a check source. The dose calibrator source was originally purchased from Du Pont Merck in 1982. All tests for leakage/contamination were negative for over 20 years. It is our belief that the leaking source was in the pig when it was purchased from Du Pont Merck. The licensee had never been licensed for any other Cs-137 sources.

Describe clean-up actions: Consultant had removed all sources and completed close-out surveys and wipes for termination of license.

List Radiation measurements taken: Consultant stated that survey readings at top of storage pig were approximately 0.2 mRem/hr.

List any other actions required of DRH: follow up as required and notify NMED.

Case Closed: Yes

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 40770
Facility: SURRY
Region: 2 State: VA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: LARRY WHEELER
HQ OPS Officer: JOHN MacKINNON
Notification Date: 05/22/2004
Notification Time: 15:06 [ET]
Event Date: 05/21/2004
Event Time: 21:46 [EDT]
Last Update Date: 05/26/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
JAY HENSON (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Hot Standby 0 Hot Standby

Event Text

UNANALYZED CONDITION DUE TO AUXILIARY FEEDWATER NOT BEING IN COMPLIANCE WITH JUSTIFICATION FOR CONTINUED OPERATION (JCO).

"At 2146 hours on 05/21/04, Unit 2 entered a 30 Hr. clock to Cold Shutdown (CSD) in accordance with T.S.3.0.1 due to Auxiliary Feedwater (AFW) not being in compliance for Continued Operation (JCO) SC 03-002 configuration. Auxiliary Feedwater was declared inoperable at 2146 hours. During post trip recovery, Emergency Procedure, 2-ES-0.1, directed that the six (6) AFW motor operated valves (MOVs) be checked opened after securing the AFW Pumps. This is contrary to the AFW JCO, which requires four (4) MOVs out of six (6) to be closed for AFW to remain Operable. At 0040 hours on 5/22/04 the correct valve alignment in accordance with the JCO was established and the 30 hour TS 3.0.1 clock was exited.

"This event is reportable in accordance with 10CFR50.72(b)(3)(ii)(B); any event or condition that results in the Station being in an unanalyzed condition that significantly degrades plant safety.

"The NRC resident has been notified."

The licensee found out about this event today during event investigation. See Surry Unit 2 events 40769, 40768 and 40771.

* * * RETRACTION FROM WOODZELL TO CROUCH ON 05/25/04 @ 2347 EDT * * *

The following information was received from the licensee via facsimile:

"At 1506 hours on 5/22/04, Surry Power Station made an 8-hour Non-Emergency Notification in accordance with 10CFR50.72 (b)(3)(ii)(B) for an unanalyzed condition due to Auxiliary Feedwater (AFW) not being aligned in accordance with Justification for Continued Operation (JCO) SC 03-002 for 2 hours and 54 minutes following a reactor trip. (Event Number 40770).

"Upon further analysis, this event was determined not to be immediately reportable. Based on calculations performed by Dominion Nuclear Safety Analysis in Engineering Transmittal ET NAF-04-0045, Rev 0, a risk-based period of time was calculated to allow operations personnel a defined period of time to realign the AFW system in accordance with this JCO. Operators must not exceed 150 hours to restore the acceptable JCO configuration during all modes where AFW is required to be operable. Since the amount of time the system was not in the JCO alignment was less than 150 hours, plant risk increase was maintained less than the limits specified in Regulatory Guide 1.177.

"This notification is being made to retract the report made on 5/22/04 based on the above discussion. The NRC resident has been notified."

The NRC Headquarters Operations Officer notified R2DO (Ayres).

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Research Reactor Event Number: 40776
Facility: IDAHO STATE UNIVERSITY
RX Type: 0.005 KW AGN-201M #103
Comments:
Region: 4
City: POCATELLO State: ID
County: BANNOCK
License #: R-110
Agreement: Y
Docket: 05000284
NRC Notified By: JOHN BENNION
HQ OPS Officer: JEFF ROTTON
Notification Date: 05/26/2004
Notification Time: 09:38 [ET]
Event Date: 05/24/2004
Event Time: 09:00 [MDT]
Last Update Date: 05/26/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
NON-POWER REACTOR EVENT
Person (Organization):
MIKE RUNYAN (R4)
TERRY REIS (NRR)

Event Text

BREACH OF PRIMARY FISSION PRODUCT BARRIER

During routine annual maintenance, a fueled control rod was determined to have a cladding failure. The control rod end cap weld was broken and the fuel in the fueled control rod had been exposed. A preliminary radiological assessment was performed and showed negligible release. There was minimum surface contamination isolated to the area of the breach. Radiation readings on contact were less than 20 millirem/hour. All air sample concentrations were well below 10CFR20 Derived Air Concentration (DAC) limits.

Licensee notified the NRC Program Manager for Non Power Reactors and the Region 4 RA.

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Power Reactor Event Number: 40777
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GORDON ROBINSON
HQ OPS Officer: BILL GOTT
Notification Date: 05/26/2004
Notification Time: 17:55 [ET]
Event Date: 05/26/2004
Event Time: 16:00 [EDT]
Last Update Date: 05/26/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
RICHARD CONTE (R1)

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

OFF SITE NOTIFICATION

"This event is being reported under 10CFR50.72(b)(2)(xi) as an item of public interest and an event for which other government agencies have been notified.

"At 1600 on 5/26/2004, the operations Shift Manager was notified by the Security Shift Supervisor that an individual [truck driver] had been arraigned by a LLEA [Local Law Enforcement Agency] judge for prohibited items (drug paraphernalia) which were discovered during a routine entrance search of personnel and vehicles. The items were discovered outside the protected area [and] were determined to not pose a threat or attempted threat. The LLEA was called and responded to the site access area and removed the individual to the local barracks, where he was subsequently arraigned on a misdemeanor. The individual's name has been removed from the Susquehanna LLC visitors list.

"The Manager of Nuclear Security briefed NRC Region #1 Inspector, Dana Caran, concerning the incident."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 40778
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: GLENN HUTTON
HQ OPS Officer: ARLON COSTA
Notification Date: 05/27/2004
Notification Time: 01:21 [ET]
Event Date: 05/27/2004
Event Time: 00:33 [EDT]
Last Update Date: 05/27/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
RICHARD CONTE (R1)

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

Event Text

AUTOMATIC REACTOR SCRAM WHILE PERFORMING SCHEDULED SHUTDOWN

"During a reactor shutdown for scheduled maintenance, a full reactor scram was generated from the Nuclear Instrumentation System.

"IRMs [Intermediate Range Monitoring detectors] 13, 14 and 18 spiked causing scram signals in both RPS [Reactor Protection Systems].

"All systems functioned properly post scram, all operator actions were correct. Holding reactor pressure at 900 psig to perform leakage inspection. Following [the leakage] inspection [operations intend] to proceed to cold shutdown."

All control rods inserted fully into the core and excess decay heat is currently being diverted to the main condenser, as necessary.

The licensee notified the NRC Resident Inspector.

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