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Event Notification Report for December 24, 2007

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
12/21/2007 - 12/24/2007

** EVENT NUMBERS **


43748 43859 43860 43862 43863 43864

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General Information or Other Event Number: 43748
Rep Org: ENERTECH
Licensee: ENERTECH
Region: 4
City: BREA State: CA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: KEVIN McKOWN
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/25/2007
Notification Time: 19:10 [ET]
Event Date: 10/25/2007
Event Time: [PDT]
Last Update Date: 12/21/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
CHUCK CAIN (R4)
ROBERT HAAG (R2)
VERN HODGE (email) (NRR)

Event Text

POTENTIAL 10CFR PART 21 REPORTABLE CONDITION FOR ENERTECH CARTRIDGE SOLENOID VALVE

The following notification was received via fax:

"This submittal provides initial notification to your office that we have opened an evaluation for a potential reportable condition under 10CFR Part 21. Based on technical data provided by the San Onofre Power Plant, two (2) Enertech normally energized, normally open, cartridge solenoid valves, part number C9113S, installed on PME dump valves have not operated within the closure time design parameters. Upon investigation SCE determined higher than expected levels of contamination, internal oxidation and pitting collectively effected the valves response time. This valve was introduced to the industry in Dec 2004. Enertech is working closely with plant personnel to determine the cause of this condition, determine a resolution, and prepare a formal Evaluation Report within the next 50 days. If at any time during the evaluation process, a defect is discovered, we will provide an amended notification to this communication.

"No other Power Plants have reported similar problems to Enertech. The solenoid valve under evaluation has multiple safety related applications. The following plants will be contacted if a reportable condition exists: SCE, STP, KHNP, Entergy (Waterford), and Dominion (Surry)."

* * * UPDATE FROM ENERTECH (MCKOWN) TO HUFFMAN VIA FAX AT 1845 EST ON 12/21/07 * * *

"Our 60 day evaluation has concluded that a 10 CFR Part 21 reportable condition does not exist regarding this issue. We have reached this conclusion on the following basis:

"Our evaluation could not establish our valve has a defect, a deviation, or a departure from a technical requirement.

"Enertech worked with SCE plant personnel to determine the cause of the 2 solenoid valves condition. The root cause of the failure of the inlet solenoid valve cartridges to operate was corrosion buildup at poppet flow orifice.

"Enertech was unable to duplicate the SONGS Unit 3 experience using valves that had been exposed to trapped hydraulic fluid with high water content for periods of 20-26 months. We inspected and tested valves in our inventory and valves previously shipped to other sites, resulting in no observed corrosion. Concluding the event did not have a common mode failure.

"The solenoid valve cartridge has been used by a significant number of nuclear utilities, including SONGS Unit 2, without identifying similar situations to those experienced at SONGS Unit 3."

R4DO (Pruett), R2DO (Shaeffer) and the Part 21 Coordinators (Hodge and Thorp via e-mail) have been notified

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Power Reactor Event Number: 43859
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: MARK LOOSBROCK
HQ OPS Officer: JOE O'HARA
Notification Date: 12/21/2007
Notification Time: 07:14 [ET]
Event Date: 12/21/2007
Event Time: 04:13 [CST]
Last Update Date: 12/21/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
ERIC DUNCAN (R3)
JERRY DOZIER (NRR)
BRIAN MCDERMOTT (IRD)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 35 Power Operation

Event Text

TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO BOTH EDG'S BEING DECLARED INOPERABLE

"This notification is being made to report a Technical Specification required shutdown due to Prairie Island Nuclear Generating Plant (PINGP) Train B Unit 1 emergency diesel generator (D2) being out of service for maintenance and Prairie Island Nuclear Generating Plant (PINGP) Train A Unit 1 emergency diesel generator (D1) being declared inoperable as a result of the Bus 15 load sequencer failure.

"On 12/20/07, at approximately 2355 hours (CST), with PINGP Unit 1 in MODE 1, D2 out of service for maintenance activities, SP 1306, D2 Diesel Generator Relay Functional Test, was being performed. This surveillance test requires the performance of SP 1094; Bus 15 Load Sequencer Test which failed during the test. This resulted in the Bus 15 Load Sequencer being declared inoperable per T.S. 3.3.4 and D1 Diesel Generator being declared inoperable. With D2 and D1 EDG's inoperable entered TS 3.8.1.F which requires Unit 1 to be in Mode 3 within 6 hours. Unit 1 shutdown commenced at 0413.

"Corrective actions for this event are in progress and are being tracked via the corrective action program."

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

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Power Reactor Event Number: 43860
Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: ROBERT KIDDER
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 12/21/2007
Notification Time: 12:31 [ET]
Event Date: 12/21/2007
Event Time: 08:25 [EST]
Last Update Date: 12/21/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
ERIC DUNCAN (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

SECONDARY CONTAINMENT BYPASSED FOR SHORT PERIOD

"Annulus Exhaust Gas Treatment System (AEGTS) 'A' was removed from service (INOPERABLE) to obtain a charcoal sample. AECTS 'B' Train was the OPERABLE Train. At 0825 hours, the charcoal plenum for the 'A' train was opened to obtain a charcoal sample resulting in alarms for AECTS 'B' low flow and Annulus low differential pressure. Based on this indication AEGTS 'B' and secondary containment were INOPERABLE. AEGTS 'B' flow was restored to normal following closure of the charcoal plenum and annulus differential pressure was restored to normal at 0833 hours, restoring secondary containment.

"AEGTS 'B' was declared operable at 0845 hours. Early indication is that a discharge damper in the AEGTS 'A' train had not operated properly. This condition was determined to be reportable in accordance with 10 CFR 50.72(b)(3)(V)(C) and (D), as condition that could have prevented the safety function of structures or systems that are needed to: (C) Control the release of radioactive material; or (D) Mitigate the Consequences of an accident."

The licensee notified the NRC Resident Inspector.

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Other Nuclear Material Event Number: 43862
Rep Org: KEY TECH
Licensee: KEY TECH
Region: 1
City: KEYPORT State: NJ
County:
License #: 29-19282-01
Agreement: N
Docket:
NRC Notified By: FONG CHEN
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 12/21/2007
Notification Time: 16:07 [ET]
Event Date: 12/19/2007
Event Time: 10:00 [EST]
Last Update Date: 12/21/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
Person (Organization):
PAMELA HENDERSON (R1)
ABY MOHSENI (FSME)

Event Text

DAMAGED MOISTURE DENSITY GAUGE

The Troxler moisture density gauge was being used at a construction site in Newark, New Jersey near Jackson Street. The gauge was not in use and the source rod was in the safety position when a roller rolled over part of the gauge. The area around the gauge was cordoned off until the RSO performed radiation surveys and performed a wipe test. The survey indicated no contamination or leakage. The wipe test was shipped to Troxler and verified no radioactive material leakage. The gauge is currently in the licensee's gauge storage room awaiting disposition.

Troxler Moisture Density gauge Model 3440
Serial Number 16356
One Cs-137 source (typically 8 milliCuries)

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Power Reactor Event Number: 43863
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [ ] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: DAVE FIELDS
HQ OPS Officer: JEFF ROTTON
Notification Date: 12/21/2007
Notification Time: 16:57 [ET]
Event Date: 12/21/2007
Event Time: 14:45 [EST]
Last Update Date: 12/21/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
SCOTT SHAEFFER (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

RCS PRESSURE BOUNDARY LEAKAGE ON RCP SEAL INJECTION LINE

"With unit shut down in Mode 3 with all CEAs inserted preparing for startup, RCS Pressure Boundary leakage was identified. Leakage appears to be from a weld to Reactor Coolant Pump Seal Injection Line. Leakage is much less than one gallon per minute. Implementing Technical Specification LCO 3.4.6.2 Reactor Coolant System Operational Leakage Action (a) to place the unit in Cold Shutdown within the following 30 hours. Commencing plant cooldown for repair."


The licensee notified the NRC Resident Inspector.

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Fuel Cycle Facility Event Number: 43864
Facility: PADUCAH GASEOUS DIFFUSION PLANT
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
                   6903 ROCKLEDGE DRIVE
                   BETHESDA, MD 20817 (301)564-3200
Region: 2
City: PADUCAH State: KY
County: McCRACKEN
License #: GDP-1
Agreement: Y
Docket: 0707001
NRC Notified By: BILLY WALLACE
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 12/23/2007
Notification Time: 19:02 [ET]
Event Date: 12/23/2007
Event Time: 03:58 [CST]
Last Update Date: 12/23/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
76.120(c)(1) - UNPLANNED CONTAMINATION
OTHER UNSPEC REQMNT
Person (Organization):
SCOTT SHAEFFER (R2)
ABY MOHSENI (FSME)

Event Text

SMALL UF6 PROCESS LEAK

"On 12/23/2007 at 0358 the C-333 unit 3 cell 1 PGLD (process gas leak detection) head (YE-5) at stage 5 actuated. Along with the PGLD actuation a seal alarm and a vibration alarm on stage 7 were received. A nearby operator on the cell floor responded to the alarm and observed a small UF6 release from the stage 7A seal cavity. To stop the release the cell was immediately shut down from the ACR which lowered the cell's pressure to below atmospheric pressure. The exact amount of material released has not been determined. Checks by health physics personnel found the actual amount of UF6 released was not significant and resulted in a relatively small area of contamination on the end of the compressor near the seal that failed and on the floor immediately around the end of the compressor.

"The actuated PGLD head is a Q safety system component. At the time of the incident the cell was operating in a mode which required the system to be operational. This is being reported based on SAR 6.9 Table 1, J2 (unplanned actuation of a Q safety system) and 10 CFR 76.120(c)(1)(i) (unplanned contamination event).

"The NRC Resident Inspector has been notified of this event.

"PGLD Problem Report Nos. ATRC-07-3433; PGLD Event Report No. PAD-2007-022; NRC Event Number 43864"

Page Last Reviewed/Updated Thursday, March 29, 2012
Thursday, March 29, 2012