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Event Notification Report for March 16, 2010

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
03/15/2010 - 03/16/2010

** EVENT NUMBERS **


45737 45755 45757 45764 45767 45768

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 45737
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [ ] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: CHARLES MORGAN
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 03/02/2010
Notification Time: 11:30 [ET]
Event Date: 03/02/2010
Event Time: 07:30 [EST]
Last Update Date: 03/15/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
JOHN WHITE (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling 0 Refueling

Event Text

PRESSURIZER SAFETY NOZZLE WELD DEGRADATION

"A Unit-1 Pressurizer Safety Relief Valve Nozzle to Safe-end Weld, (#4SR-1006-1) was discovered to have an indication not acceptable under ASME Section XI, IWB-3600. The weld is on a 4 inch diameter line to the pressurizer safety relief valve (RV-201). The weld is in our dissimilar metal weld inspection program and was scheduled to be examined this RFO [refueling outage] in accordance with MRP-139 requirements. Initial inspections on 3/1/10 found an indication and the indication was confirmed by a second NDE level 3 examiner. Indication is circumferential, initiated at ID and propagates approximately 1.8 inches circumferentially to about approximately 70% through wall. ASME IWB-3500 allows up to 12.5% through wall for class 1 welds. The defect was found using phased array Ultrasonic Testing (UT). The NDE report is being reviewed and characterized at this time.

"At this time, we believe the most probable cause of the indication is primary water stress corrosion cracking. No active leaks have been identified, the defect is not through wall.

"Unit 1 is in Mode 6. A team has been established and repair options are being investigated."

The licensee notified the NRC Resident Inspector.

* * * RETRACTION PROVIDED AT 0922 EDT ON 03/15/2010 BY ROBERT MARTIN TO JEFF ROTTON * * *

"On March 7, 2010, manually indexed phased-array ultrasonic examination of the U1 Pressurizer Safety Relief Valve Nozzle to Safe-end Weld was performed. Based on these inspections, it was determined on March 13, 2010 that the indication does not exhibit stress corrosion cracking characteristics and is not consistent with ultrasonic responses associated with inside diameter (ID) connected geometry. Therefore, the U1 Pressurizer Safety Relief Valve Nozzle to Safe-end Weld is acceptable from an ASME Code Section XI perspective. On this basis, the indication did not result in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded and the issue is not reportable under 10 CFR 50.72(b)(3)(ii)(A).

"The NRC resident was notified of this retraction."

Notified the R1DO (Chris Cahill)

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General Information or Other Event Number: 45755
Rep Org: COLORADO DEPT OF HEALTH
Licensee: HACH COMPANY
Region: 4
City: LOVELAND State: CO
County:
License #:
Agreement: Y
Docket:
NRC Notified By: EDGAR ETHINGTON
HQ OPS Officer: DONG HWA PARK
Notification Date: 03/10/2010
Notification Time: 10:21 [ET]
Event Date: 03/10/2010
Event Time: [MST]
Last Update Date: 03/10/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MICHAEL HAY (R4DO)
ANGELA MCINTOSH (FSME)
ILTAB via email ()

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - POTENTIALLY LOST STATIC ELIMINATOR

The following information was obtained from the State of Colorado via email:

"A general licensee, Hach Company - Loveland Facility, has notified the Colorado Department of Health that it lost a Nuclestat (static eliminator) device containing 10 milliCuries of Polonium 210. The model number is P-2021, Serial Number A2FR969 which was shipped on May 17, 2007 from NRD, LLC.

"The licensee states that the facility has been audited and personnel questioned. No other details are available at this time.

"The Colorado Department of Health has initiated an investigation of this incident."

Colorado Report Number: I10-03

THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

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General Information or Other Event Number: 45757
Rep Org: NV DIV OF RAD HEALTH
Licensee: LAS VEGAS PAVING CORPORATION
Region: 4
City: LAS VEGAS State: NV
County:
License #: 00-11-0255-01
Agreement: Y
Docket:
NRC Notified By: TIM MITCHELL
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 03/11/2010
Notification Time: 12:43 [ET]
Event Date: 03/11/2010
Event Time: 05:45 [PST]
Last Update Date: 03/11/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MICHAEL HAY (R4DO)
JIM WHITNEY (ILTA)
ANGELA MCINTOSH (FSME)

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE

A Troxler moisture density gauge was stolen from an open bed truck at the employee's residence. The gauge was chained in the back of the truck. The theft was discovered at 0545 PST on 3/11/2010. "RSO was notified at 0550 PST, Las Vegas Metropolitan Police (LVMPD) at 0555 PST and the Nevada State Health Division at 0556 PST. The State is following the incident and working with LVMPD. Follow-up information will be provided to the NRC on the situation and entered into NMED. LVMPD Event No.: 100311-0802."

Troxler model 3440
Serial Number: 17916
Sources: Am-241:Be 40 mCi Be (Model No.47- Serial No.13357) and Cs-137 8 mCi 137 (Model No. 50,Serial No. 7401)

Nevada Incident Number: NV100003

THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL

Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

This source is not amongst those sources or devices identified by the IAEA Code of Conduct for the Safety & Security of Radioactive Sources to be of concern from a radiological standpoint. Therefore is it being categorized as a less than Category 3 source.

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Power Reactor Event Number: 45764
Facility: DAVIS BESSE
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] B&W-R-LP
NRC Notified By: LARRY MYERS
HQ OPS Officer: VINCE KLCO
Notification Date: 03/13/2010
Notification Time: 04:45 [ET]
Event Date: 03/12/2010
Event Time: 21:43 [EST]
Last Update Date: 03/15/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
MONTE PHILLIPS (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling 0 Refueling

Event Text

CONTROL ROD DRIVE MECHANISM NOZZLE INDICATIONS

"On March 12, 2010, during the Davis-Besse Nuclear Power Station Unit No. 1 (DBNPS) refueling outage, the documented results of planned ultrasonic (UT) examinations performed on the Control Rod Drive Mechanism (CRDM) nozzles penetrating the reactor vessel closure head (RVCH) identified that two of the nozzles inspected to date did not meet the applicable acceptance criteria. Each of these two nozzles have similar indications that appear to penetrate into the nozzle walls from a lack of fusion point at the outer diameter of the nozzle and the J-Groove weld. Leak path detection was performed on both nozzles with the results showing no leak path. Bare metal visual examinations are scheduled to be performed on all nozzles to determine if there is any pressure boundary leakage. Both indications will require repair prior to returning the vessel head to service. There are sixty-nine nozzles and all will be subject to these UT inspections.

"It is important to note that this notification is being provided prior to the completion of all of the required UT and VT [Visual Tests] examinations for these two nozzles and the remaining nozzles. The indications were detected with a blade probe used to detect axially-oriented indications. The remaining probe that is used to complete the UT examination in each of these two penetrations is a blade probe that is used to identify circumferentially-oriented indications.

"The examinations are being performed to meet the requirements of 10CFR50.55a(g)(6)(ii)(D) and ASME Code Case N-729-1, to identify potential flaws/indications well before they grow to a size that could potentially affect the structural integrity of the reactor vessel head pressure boundary."

The licensee notified the NRC Resident Inspector and will notify the State of Ohio and both Lucas and Ottawa Counties.

* * * UPDATE ON 3/13/2010 AT 1903 FROM LARRY MEYERS TO MARK ABRAMOVITZ * * *

"On March 13, 2010, additional Control Rod Drive Mechanism nozzles (4 and 59) were identified that did not meet the applicable acceptance criteria. The indications on these nozzles are similar in nature and location to the indications previously reported for nozzles 28 and 33. These indications will also require repair prior to returning the vessel head to service.

"Like the two previously reported nozzles, this notification is being provided prior to the completion of all of the required examinations for the nozzle and the remaining nozzles. The indications were detected with a blade probe used to detect axially-oriented indications. The remaining probe that will be used to complete the examination in this penetration is a probe sensitive to circumferentially-oriented indications.

"Additionally, during the bare metal visual examination of the outer surface of the reactor vessel closure head, boric acid deposits were found at CRDM nozzles 4 and 33 that are indicative of primary water leakage. The visual examination of the RVCH is continuing."

The licensee notified the NRC Resident Inspector, State of Ohio, and local government.

Notified the R3DO (Phillips).

* * * UPDATE ON 3/15/2010 AT 0800 EDT FROM THOMAS PHILLIPS TO JEFF ROTTON* * *

Update to Davis-Besse event #45764 initially reported 3/13/2010 at 0445 and adding an additional 10 CFR 50.72 reporting criteria.

"On March 15, 2010, the FirstEnergy Nuclear Operating Company is issuing a press release regarding the Davis-Besse Nuclear Power Station Unit No. 1 reactor vessel head (RVCH) Control Rod Drive Mechanism nozzles that have indications that do not meet the applicable acceptance regulatory criteria. The results of the ongoing planned ultrasonic (UT) examinations performed on these nozzles penetrating the RVCH have identified indications that will require repair prior to returning the vessel head to service. Currently, there are twelve nozzles which will be repaired, two of which have evidence of primary water leakage found during the bare metal visual examination of the outer surface of the reactor vessel closure head. There are sixty-nine nozzles and all are subject to these UT inspections.

"It is important to note that this media release is being provided prior to the completion of all of the required examinations for these and the remaining nozzles."

The licensee notified the NRC Resident Inspector and will be notifying the State of Ohio and both Lucas and Ottawa Counties.

Notified R3DO (Monte Phillips)

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Power Reactor Event Number: 45767
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: TODD CREASY
HQ OPS Officer: HOWIE CROUCH
Notification Date: 03/15/2010
Notification Time: 12:51 [ET]
Event Date: 03/15/2010
Event Time: 09:46 [EDT]
Last Update Date: 03/15/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
ART BURRITT (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling 0 Refueling

Event Text

SECONDARY CONTAINMENT BYPASS LEAKAGE EXCEEDED TECHNICAL SPECIFICATION LIMIT

"Appendix J Local Leak Rate Testing has determined that Secondary Containment Bypass Leakage (SCBL) has been exceeded for Unit 1. During performance of leak rate test SE-159-045, the combined SCBL limit of 15 scfh [standard cubic feet per hour] for as-found minimum pathway was exceeded as specified in Tech Spec SR 3.6.1.3.11.

"Acceptance Criteria Test results were within Acceptance Criteria for the 10CFR50 Appendix J limits of 0.6 La [maximum allowed leakage rate].

"This event is being reported as a degraded or unanalyzed condition pursuant to 10CFR50.72(b)(3)(ii)(A)."

The RHR system containment spray penetration isolation valve was being tested when the failure occurred. The valve will be repaired and re-tested.

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 45768
Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: JIM CASE
HQ OPS Officer: HOWIE CROUCH
Notification Date: 03/15/2010
Notification Time: 14:45 [ET]
Event Date: 03/15/2010
Event Time: 08:10 [EDT]
Last Update Date: 03/15/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MICHAEL KUNOWSKI (R3DO)

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

EMERGENCY RESPONSE DATA SYSTEM OUT OF SERVICE DUE TO COMPUTER FAILURE

"On March 15, 2010, at approximately 0810 hours EDT, the plant computer system (ICS) was taken out of service for a planned outage to set the computer time to Eastern Daylight Time. During the time change adjustment, the ICS experienced a hard memory fault which required additional efforts to recover the ICS. At approximately 1205 hours EDT, the ICS was restored to normal operation. During the time ICS was out of service, the Safety Parameter Display System (SPDS), the Emergency Response Data System (ERDS), and the automatic mode calculation of the Computer Aided Dose Assessment Program (CADAP) were unavailable.

"This event is being reported in accordance with 10 CFR 50.72(b)(3)(xiii), as a condition that results in a major loss of offsite communications capability. The NRC Resident Inspector has been notified."

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