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Event Notification Report for July 5, 2005

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
07/01/2005 - 07/05/2005

** EVENT NUMBERS **


40911 41806 41811 41815 41816 41818 41819

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
General Information or Other Event Number: 40911
Rep Org: U.S. DEPARTMENT OF ENERGY
Licensee: RADECO, LLC
Region: 4
City: RICHLAND State: WA
County: BENTON
License #:
Agreement: Y
Docket:
NRC Notified By: JOHN H. SWAILES
HQ OPS Officer: HOWIE CROUCH
Notification Date: 07/30/2004
Notification Time: 12:39 [ET]
Event Date: 07/30/2004
Event Time: [PDT]
Last Update Date: 07/01/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
JAMES TRAPP (R1)
THOMAS DECKER (R2)
JOHN MADERA (R3)
RUSSELL BYWATER (R4)

Event Text

PART 21 SAFETY HAZARD WITH RADECO PORTABLE AIR SAMPLER MODEL H-809VI

The U.S. Department of Energy, Office of River Protection in Richland, WA has identified a potential safety issue with Radeco portable air sampler model H-809VI. This type of portable air sampler is utilized in the commercial nuclear industry.

A Health Physics Technician experience a mild shock while handling a Radeco portable air sampler when the sample holder was touched. Radeco has issued a recommendation or opinion for H-809V series electrical grounding.

Facilities should check sample holders on the Radeco H-809 and H-810 series samplers to assure proper grounding and no voltage on the sample holder.

** RETRACTION OF PART 21 FROM TANK FARMS (T.SMITH) TO J. KNOKE ON 07/01/05 ***

"The Department of Energy (DOE), Office of River Protection (ORP) in Richland, Washington requests closure of the referenced submitted courtesy notification of a potential safety issue with RADeCO, portable air sampler, model H-809VI to the Nuclear Regulatory Commission. ORP's basis for closure of the submitted courtesy notification is as follows:

"The Underwriters Laboratory (UL) concluded the RADeCO Portable Air Sampler Model H-809VI, serial Number 8499, instrument DOES NOT present a generic safety problem. The report is available by request only.

"The RADeCO Portable Air Sampler instrument passed all of the UL tests.

"ORP concludes the matter does not represent a reportable concern covered by 10 CFR Part 21 requirements because loss of a single air monitor because of this issue would not increase risk to public health and safety when other instruments are in place to detect atmospheric radioactivity."

Notifications were provided to R1DO(White), R2DO( Bonser), R3DO(Cameron), R4DO(Clark), NMSS (Holonich), and NRR (Carpenter).

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General Information or Other Event Number: 41806
Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: ENERGIZER
Region: 1
City: ASHEBORO State: NC
County:
License #: 076-1755-0G
Agreement: Y
Docket:
NRC Notified By: J. MARION EADDY III
HQ OPS Officer: PETE SNYDER
Notification Date: 06/28/2005
Notification Time: 17:06 [ET]
Event Date: 06/28/2005
Event Time: [EDT]
Last Update Date: 06/28/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JOHN WHITE (R1)

Event Text

AGREEMENT STATE REPORT LOST / MISSING SOURCE

The State provided the following information via facsimile:

"The North Carolina Radioactive Materials branch was made aware of the loss [of] a Po-210 static elimination source from the Energizer facility in Asheboro, NC today.

"The agency interviewed the Staff Environmental Coordinator this afternoon via telephone. The information for the missing source is as follows:
Isotope: Po-210
Activity: 20 millicuries as of 3 March 2004 (decay corrected to 2.38 mCi at time of loss)
Make: NRD LLC
Model: P-2031-1000
Serial No.: A2DP844

"The licensee continues to search for the missing source. North Carolina Radioactive Materials Branch continues to monitor the situation and will dispatch health physicists to investigate as necessary."

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General Information or Other Event Number: 41811
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: CHAPMAN MEDICAL CENTER
Region: 4
City: ORANGE State: CA
County:
License #: 1946-30
Agreement: Y
Docket:
NRC Notified By: ROBERT GREGER
HQ OPS Officer: MIKE RIPLEY
Notification Date: 06/29/2005
Notification Time: 16:45 [ET]
Event Date: 06/28/2005
Event Time: 07:00 [PDT]
Last Update Date: 06/29/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JEFFERY CLARK (R4)
MICHELE BURGESS (NMSS)

Event Text

CALIFORNIA AGREEMENT STATE REPORT - LOST AND RECOVERED IR-192 IMPLANTATION SEEDS

The State provided the following information via email:

"On Tuesday, June 28, 2005, I received a call from Waste Management of Orange that the radiation alarm had sounded. They separated the radioactive waste from the other waste and placed the radioactive waste in their secure holding area until I could arrive. Around 11:30 a.m. I went out to the facility and took surveys and tried to identify the radionuclide - my batteries on the MCA were running low, but based on the peaks I thought it could be either Ga-67 or Ir-192. The load had been picked up from Chapman Hospital so I contacted them and brought the waste back to the hospital where the RSO was going to do a positive identification. This morning I stopped at the hospital and took some readings outside the waste storage area and did another identification scan using the Bicron Field spec. I contacted the Imaging Director [name deleted]. He said they did find an Ir-192 ribbon (which contained 6 seeds). They put this ribbon with the 19 other ribbons that were being returned to the manufacturer. A 48 year old female patient received 20 ribbons (each with 6 seeds) on 6-20-05. The total activity was 58.19 mCi (activity per ribbon with 6 seeds = 2.9 mCi). The Oncology Physician [name deleted], feels the ribbon could have been dislodged before she was discharged on 6-24-05. This ribbon could have been in the bedding under the patient for some period of time. He will do an evaluation to determine the effects of the ribbon being under the patient for a given time and the effects of a lower dose being administered. [The Imaging Director] states that the found ribbon was placed in with the other 19 ribbons that will be going back to the manufacturer. He has counted and accounted for the 20 ribbons that were originally sent and confirms all 20 are now accounted for. The facility will send me a report about this incident and will outline their corrective actions to avoid disposal of such ribbons in the future."

California Report No. 062805

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Power Reactor Event Number: 41815
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: NICHOLAS AVRAKOTOS
HQ OPS Officer: JOHN KNOKE
Notification Date: 06/30/2005
Notification Time: 19:49 [ET]
Event Date: 06/30/2005
Event Time: 19:29 [EDT]
Last Update Date: 07/01/2005
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
JOHN WHITE (R1DO)
CYNTHIA CARPENTER (NRR)
MELVYN LEACH (IRD)
STEINDURF (FEMA)
CRAIG (DHS)
B.HOLIAN (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

Event Text

PRIMARY CONTAINMENT INOPERABLE DUE TO SMALL CRACK IN TORUS

The licensee has determined that the small weep hole crack in the torus (x in shape) is in a position which requires the plant to initiate a normal shutdown to cold shutdown conditions. The crack is located about 5 feet below the waterline and just below the HPCI exhaust pipe discharge. Due to the location of this crack the licensee's engineering staff showed via analysis that it would be prudent to restrict the number of thermal cycles the crack receives. The plant is in a 1 hour Technical Specification LCO shutdown action statement. At 19:50 the licensee commenced the Technical Specification shutdown to cold shutdown conditions.

As an additional item, one of the four Emergency Diesel Generators was deemed inoperable at the time of the event, and continues to be in a LCO action statement.

The licensee made notifications to the State and local agencies, and will notify the NRC Resident Inspector.

*** UPDATE ON 06/30/05 AT 22:24 EDT FROM T. PAGE TO J. KNOKE ***

"With the plant operating at 100% on June 27, 2005 during RCIC Torus Suction piping inspection per ST-24H, inspectors discovered a TORUS leak in the vicinity of a TORUS Support between Bays A and P. The leak was quantified as slight weepage with streaking and a small puddle below leak. This was captured in the plant corrective action program on CR-JAF-2005-02593. Subsequent non destructive examination determined that the leakage was from a small through wall crack. The condition was discussed with the NRC Staff at that time. Initial evaluation at that time determined that there was reasonable expectation of operability, an Operational Decision Making Instruction (ODMI) was prepared and implemented to monitor the leakage while further engineering evaluation was conducted. On June 30,2005 further engineering analysis determined that operability of the primary containment was not assured and at 19:29 on June 30, 2005 the Shift Manager declared Primary Containment Inoperable and entered Technical Specification LCO 3.6.1.1 Condition A, Primary Containment Inoperable, and declared an Unusual Event under EAL 9.1.2. Preparations were made for a reactor shutdown and the shutdown was commenced at 20:00.

"At the time of the event the A Train of EDGs was out of service for a planned maintenance LCO. At this time the NRC Resident has been informed."

The A Train EDG is not available nor operable if needed.

The R1DO (White) and NRR EO (Carpenter) have been notified.

**** UPDATE ON 07/01/05 AT 1720 EDT FROM N. AVRAKOTOS MACKINNON ***

An Unusual Event was terminated at 1716 EDT due to achieving cold shutdown. R1DO (John White), NRR EO (Cynthia Carpenter), IRD Manager (M. Leach), FEMA (Todd Kuzia) and DHS (Craig) notified.

NRC Resident Inspector, State and Local officials were notified by the licensee.

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Power Reactor Event Number: 41816
Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: PATRICK FALLON
HQ OPS Officer: ARLON COSTA
Notification Date: 07/01/2005
Notification Time: 00:08 [ET]
Event Date: 06/30/2005
Event Time: 19:31 [EDT]
Last Update Date: 07/01/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
JAMNES CAMERON (R3)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Cold Shutdown 0 Cold Shutdown

Event Text

UNANALYZED CONDITION RELATED TO THE STANDBY FEEDWATER PUMPS AND CONTROL CIRCUITS

"During an NRC Triennial Fire Protection Audit the Inspector identified a fuse coordination issue between 130VDC supply circuit and breaker trip circuit fuses for the Standby Feedwater (SBFW) Pump switchgear. The coordination ratio was found to be too low to support requirements for fire related safe shutdown equipment under Generic Letter 81-12. Impacted equipment is SBFW Pumps A & B and control circuits required for Appendix R Alternative Shutdown auxiliary equipment. This event is being reported as an unanalyzed condition that significantly degraded plant safety under 10CFR50.72(b)(3)(ii)(B).

"The impacted equipment has been declared inoperable and a team is currently working on design changes to change fuse sizes for the breaker trip circuit/supply circuit to meet the requirements of Generic Letter 81-12."

The licensee notified the NRC Resident Inspector.

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Hospital Event Number: 41818
Rep Org: MOUNTAINSIDE HOSPITAL
Licensee: MOUNTAINSIDE HOSPITAL
Region: 1
City: MONCLAIR State: NJ
County:
License #: 29-03297-02
Agreement: N
Docket:
NRC Notified By: ROBERT SASSO
HQ OPS Officer: JOHN KNOKE
Notification Date: 07/01/2005
Notification Time: 18:13 [ET]
Event Date: 07/01/2005
Event Time: 12:00 [EDT]
Last Update Date: 07/02/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
INFORMATION ONLY
Person (Organization):
JOHN WHITE (R1)
JOSEPH HOLONICH (NMSS)

Event Text

RADIOACTIVE SOURCES NOT REMOVED PRIOR TO SHIPMENT

A Mountainside Hospital representative informed us that a nuclear medicine camera was mistakenly transported with 28 Gadolinium-153 sources inside the camera. The total source activity is 20 millicuries and the calculated source strength is approximately 2 milliRem/hr at 1 meter. The representative contacted the driver transporting the camera, who was at the Pennsylvania/Ohio border, notified him that radioactive sources were inside the camera and requested he return the camera and sources back to Mountainside Hospital.

Established a conference call with R1 (George Pangburn, Pam Henderson, John White), NMSS (Bill Brach, Joe Holonich), and NSIR (Phil Brochman).

*** UPDATE FROM R. SASSO TO J. KNOKE AT 14:23 ON 07/02/05 ***

A Mountainside Hospital representative informed us that the camera and sources have arrived back at the hospital without incident. The licensee removed all 28 shielded sources from the camera and detected no activity on the camera or truck. This confirmed that all sources have been removed. The R1DO (White) and NMSS EO (Holonich) were notified. An update was also emailed to R1 (George Pangburn, Pam Henderson, John White), NMSS (Bill Brach, Joe Holonich), and NSIR (Phil Brochman).

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General Information or Other Event Number: 41819
Rep Org: HOWDEN BUFFALO
Licensee: HOWDEN BUFFALO
Region: 3
City: NEW PHILADELPHIA State: OH
County:
License #:
Agreement: Y
Docket:
NRC Notified By: PAUL STEWART
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 07/01/2005
Notification Time: 18:32 [ET]
Event Date: 05/05/2005
Event Time: 16:15 [EDT]
Last Update Date: 07/02/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
JAMNES CAMERON (R3)
JOHN WHITE (R1)
BRIAN BONSER (R2)
JEFFREY CLARK (R4)
OMID TABATABAI email (NRR)

Event Text

PART 21 NOTIFICATION OF FAILED SURFACE COATINGS ON FANS

Howden Buffalo provided the following information via facsimile:

"In accordance with subject regulation and Howden Buffalo internal procedures, Howden Buffalo is submitting a report of a defect or failure to comply for basic components supplied to a nuclear facility.

"Duke Energy, Oconee Plant, reported insufficient adhesion of Carboline topcoat to Carboline primer, resulting in separation of the topcoat on two fans and one other fan inlet bell. The items were manufactured, painted, and supplied to Duke Oconee during the period February 2002 thru March 2002, as basic components in a nuclear safety related application. The three affected items were part of ten complete fans delivered to Duke Oconee both before and after the affected units.

"Howden Buffalo conducted an initial investigation that included both Duke Power Materials Engineering & Lab Services and Carboline. Our investigation concluded that coating materials were not defective however, application of Carboline primer was not in accordance with Carboline recommendations for sufficient curing of the primer, resulting in accumulation of VOC's from the uncured primer and ultimate separation of the topcoats.

"Howden Buffalo has reviewed internal plant procedures for application of Carboline primer and topcoat, including surface preparation, and found that the procedures failed to incorporate Carboline updated requirements for sufficient curing of the primer. All internal procedures are now revised to incorporate Carboline requirements in their entirety. Howden Buffalo procedures for supplying Carboline coating as a basic component were applicable during the period of October 2001 thru March 2005. Howden Buffalo is contacting each of these customers to a) advise of a potential defect in the Carboline coating, b) recommend inspection criteria, and c) provide contact information.

"Summary evaluation: Review of documentation for this sales order, including all paint surveillance records, does not support a conclusion that this defect is limited only to the fans delivered for this order. Root cause of paint failure would appear to be insufficient training in procedures for surface preparation and preparation and application of primer and paint. Environmental limitations for temperature and relative humidity may not have been correctly considered for drying time requirements. Notification to NRC and to all customers of safety-related coating is required."

Howden Buffalo item number: 540059-080
Reactor building cooling unit fans serial numbers 004, 005, and 006
Nature of defect: Insufficient adhesion of Carboline topcoat to Carboline primer - topcoat flaking from two fans and one fan inlet bell.

Affected safety related orders: Duke (Oconee) shipped 11/2/01
Exelon (Dresden) shipped 3/28/03
Edison Material Supply (SONGS) shipped 7/28/04
Amergen Energy (Oyster Creek) shipped 10/31/02

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