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Event Notification Report for January 2, 2006

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/30/2005 - 01/02/2006

** EVENT NUMBERS **


42116 42231 42237

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 42116
Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: ROBERT KIDDER
HQ OPS Officer: STEVE SANDIN
Notification Date: 11/04/2005
Notification Time: 03:32 [ET]
Event Date: 11/03/2005
Event Time: 16:00 [EST]
Last Update Date: 12/30/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
MONTE PHILLIPS (R3)

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

TS REQUIRED COMPONENTS INADVERTENTLY RENDERED INOPERABLE DUE TO INADEQUATE REVIEW OF WORK CLEARANCE

"At 0200 on 11/03/05 a clearance was authorized that defeated the DW [Drywell] pressure high and Rx [Reactor] vessel low isolation features to valves in the Nuclear Closed Cooling System and Instrument Air Systems. The required T.S. [Technical Specification] actions after this discovery are that the plant should have been in Mode 3 at 1600 on 11/3/05. The clearance was removed and the circuit restored to operability at 0142 on 11/4/05. The time of discovery for the loss of safety function was 2345 on 11/3/05."

The clearance was to perform pre-planned maintenance activities. The licensee plans on entering this incident into their corrective action program and will issue a Condition Report.

The licensee informed the NRC Resident Inspector.

* * * RETRACTION ON 12/30/2005 AT 10:07 FROM KENNETH RUSSELL TO ABRAMOVITZ * * *

"An 8-hour notification was made on November 3, 2005, in accordance with 10CFR50.72(b)(3)(v)(D), Accident Mitigation. This report was made when it was discovered that a clearance had unintentionally deenergized a portion of the containment isolation logic. This logic would have prevented a containment isolation valve for the nuclear closed cooling system and a containment isolation valve for the instrument air system from closing on a signal due to high drywell pressure or reactor vessel low level as designed.

"The condition was determined not to be a loss of containment (leakage) function since each containment penetration also has an inboard containment check valve which is leak tested and is credited for preventing leakage. The check valves in both penetrations were successfully tested to be in conformance with 10 CFR 50 Appendix J Option B criteria in March 2005. The containment isolation (instrumentation) function was also not lost. Only the logic for Group 2A outboard valves was deenergized. This was a small portion of the outboard logic and had no impact on the inboard logic. Since neither the containment function nor the containment isolation function was lost, there was no loss of safety function for an accident mitigation function and ENF 42116 Is retracted.

"As discussed in ENF 42116, a Technical Specification violation occurred and is reportable per 10CFR50.73(a)(2)(i)(B), as a condition prohibited by Technical Specifications." The licensee will be submitting a written LER for the 10CFR50.73(a)(2)(i)(B) event.

The licensee notified the NRC Resident Inspector.

Notified the R3DO (Hills).

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Other Nuclear Material Event Number: 42231
Rep Org: AMERICAN TECHNICAL SERVICES
Licensee: AMERICAN TECHNICAL SERVICES
Region: 4
City: SIOUX FALLS State: SD
County:
License #: 40-27465-01
Agreement: N
Docket:
NRC Notified By: MIKE HUDSON
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 12/27/2005
Notification Time: 13:13 [ET]
Event Date: 12/08/2005
Event Time: [MST]
Last Update Date: 12/30/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
JEFFREY CLARK (R4)
SANDRA WASTLER (NMSS)
JIM WHITNEY (EMAIL) (TAS)

Event Text

LOST TROXLER MOISTURE DENSITY GUAGE

American Technical Services (Sioux Falls, SD) sent a Troxler Moisture Density Gauge to QALTEK (Idaho Falls, ID) for repairs. The gauge was picked up by DHL Express at 14:15 CST on 12/08/2005 and has not arrived at its destination. DHL is searching for the gauge.

Troxler Model 3400
Serial Number 25721
Cs-137 source #47-22091, 0.3 GBq [8 millicuries]
Am-241:Be source 1.48 GBq [40 millicuries]

* * * UPDATE FROM M. HUDSON TO P. SNYDER AT 1444 ON 12/30/05 * * *

The licensee is retracting this report based on the following: The shipping company temporarily lost track of the item and found it in their system. The gauge was delivered with no evidence of tampering on 12/30/05 at 1130 CST.

Notified R4DO (Clark), NMSS EO (Ruland), TAS (Whitney).

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.

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Power Reactor Event Number: 42237
Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [1] [ ] [ ]
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: RICHARD HARRIS
HQ OPS Officer: STEVE SANDIN
Notification Date: 12/31/2005
Notification Time: 19:16 [ET]
Event Date: 12/31/2005
Event Time: 14:12 [CST]
Last Update Date: 12/31/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
JEFFREY CLARK (R4)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 95 Power Operation 94 Power Operation

Event Text

AUTOMATIC ACTUATION OF THE EMERGENCY FEEDWATER (EFW) DUE TO A TRANSIENT ON THE "B" MAIN FEEDWATER (MFW) PUMP

"The EFW actuation occurred when the 'B' MFW pump RPM rose then dropped to ~4000 rpm. The MFW pump then recovered immediately. This transient caused EFIC [Emergency Feedwater Initiation Control] to actuate and both EFW pumps received start signals on invalid low SG level from the EFIC low range level instruments. These instruments measure level based upon a dp [differential pressure] across an orifice and are not considered reliable at 95% power and full MFW flow. All other SG level instruments indicate SG level was above EFIC setpoint during the MFW pump transient. This can be concluded by reviewing the OTSG [Once Through Steam Generator] level prior to and during the transient. Prior to the transient the EFIC low range level instruments indicated a level of ~24 inches. During the transient the EFIC low range level instruments indicated as low as 4 inches. However, the Startup Range level only lowered from ~122 inches prior to the transient to ~120 inches.

"Both EFW pumps were immediately overridden and stopped once it was verified this was not an actual under feed condition to the OTSGs. No EFW injection into the OTSGs occurred due to the EFW actuation."

There was no ongoing maintenance at the time which would have explained the "B" MFW pump transient.

The licensee informed the NRC Resident Inspector.

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