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> May 13
Event Notification Report for May 13, 2008
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U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
05/12/2008 - 05/13/2008
** EVENT NUMBERS **
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| Power Reactor |
Event Number: 44201 |
Facility: HATCH
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: D. H. JONES
HQ OPS Officer: PETE SNYDER
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Notification Date: 05/12/2008
Notification Time: 10:30 [ET]
Event Date: 03/19/2008
Event Time: [EDT]
Last Update Date: 05/12/2008
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Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
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Person (Organization):
DEBORAH SEYMOUR (R2)
PAUL KROHN (R1)
HIRONORI PETERSON (R3)
DALE POWERS (R4)
C. VERN HODGE (NRR)
J. THORP (NRR)
OMID TABATABAI (NRO)
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| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
N |
Y |
92 |
Power Operation |
92 |
Power Operation |
| 2 |
N |
Y |
57 |
Power Operation |
57 |
Power Operation |
Event Text
GENERAL ELECTRIC HITACHI CR120A RELAY/RELAY COIL WIRE CLAMP CRACKING
Southern Nuclear Company made this notification of a potential defect in components received by its Edwin I. Hatch Nuclear Plant. The potential defect may exist in ninety-six (96) subject components: ninety-four (94) General Electric Hitachi (GEH) CR120A relays and two (2) GEH CR120A relay coils.
The wire clamps supplied with these relays and relay coils may be susceptible to cracking. The wire clamps serve to secure the wire connections to the relays and relay coils. Currently there are thirty-seven (37) CR120A relays and one (1) CR120A relay coil installed. The components not currently installed have been placed on hold.
The licensee has followed the recommendations of GEH by visually inspecting all installed components for cracks. No cracks were found.
The licensee will replace the clamps on one subject relay installed in the Main Control Room Environmental Control System. The clamps on the components installed in the Source Range Monitoring and Intermediate Range Monitoring instruments show no signs of cracking will be left installed as is. Replacement wire clamps will be ordered from GEH. The licensee plans to replace the clamps on the other stock components. |
| Fuel Cycle Facility |
Event Number: 44202 |
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: CALVIN PITTMAN
HQ OPS Officer: HOWIE CROUCH
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Notification Date: 05/12/2008
Notification Time: 15:34 [ET]
Event Date: 05/12/2008
Event Time: 12:30 [CDT]
Last Update Date: 05/12/2008
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Emergency Class: NON EMERGENCY
10 CFR Section:
76.120(c)(2) - SAFETY EQUIPMENT FAILURE
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Person (Organization):
DEBORAH SEYMOUR (R2)
JOSEPH GIITTER (NMSS)
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Event Text
24-HR REPORT - UF6 RELEASE DETECTION SYSTEM FAILURE
"At 1230 CDST, on 05-12-08 the Plant Shift Superintendent (PSS) was notified that an alarm was received for the C-331 Unit 3 Cell 5 UF6 Release Detection (PGLD) System. Operators responded and found that the READY and MANUAL lights for this system were not illuminated. This PGLD System contains detectors that cover C-331 Unit 3 Cell 5 and Sections 2 and 3 of the cell bypass piping. At the time of this alarm, unit 3 Cell 5 and some areas of Sections 2 and 3 of the cell bypass were operating above atmospheric pressure. TSR 2.4.4.1 requires that at least the minimum number of detector heads in the cell and in each defined section of the cell bypass are operable during steady state operations above atmospheric pressure. With the Unit 3 Cell 5 PGLD system inoperable, none of the required cell heads and only 2 of the required 3 heads in Sections 2 and 3 of the cell bypass were operable. This PGLD System was declared inoperable, TSR LCO 2.4.4.1.A.1 and 2.4.4.1.C.1 were entered and a continuous smoke watch was put in place within one hour. Engineering has determined that the system would not have been able to perform its intended safety function when this alarm came in. This event is reportable as a 24 hour event in accordance with 10 CFR 76.120(c)(2)(i). This is an event in which equipment is disabled or fails to function as designed when: a.) the equipment is required by a TSR to prevent releases, prevent exposures to radiation and radioactive materials exceeding specified limits, mitigate the consequences of an accident, or restore this facility to a pre-established safe condition after an accident; b.) the equipment is required by a TSR to be available and operable and either should have been operating or should have operated on demand, and c.) no redundant equipment is available and operable to perform the required safety function.
"The NRC Senior Resident Inspector has been notified of this event.
"PGDP Assessment and Tracking Report No. ATR-08-1412; PGDP Event Report No. PAD-2008-14; Worksheet No. Responsible Division: Operations" |
| Power Reactor |
Event Number: 44205 |
Facility: SALEM
Region: 1 State: NJ
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: GARY MEEKINS
HQ OPS Officer: PETE SNYDER
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Notification Date: 05/12/2008
Notification Time: 20:48 [ET]
Event Date: 05/12/2008
Event Time: 15:00 [EDT]
Last Update Date: 05/12/2008
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Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
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Person (Organization):
PAUL KROHN (R1)
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| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 2 |
N |
Y |
84 |
Power Operation |
20 |
Power Operation |
Event Text
SHUT DOWN INITIATED DUE TO INOPERABLE STEAM GENERATOR FLOW CHANNELS
"This 4-hour notification is being made to report that Salem Unit 2 has initiated a manual reactor shutdown in accordance with [Technical Specification] 3.0.3. The shutdown was initiated due to all eight steam generator steam flow channels being declared inoperable at 1500 on 5/12/08. All eight steam flow channels were indicating lower than actual steam flow such that the high steam flow coincident with low steam pressure or low-low Tave would not occur within the allowable values specified in the technical specifications. Salem Unit 2 is currently in Mode 1. Reactor Coolant System Temperature is 551 degrees Fahrenheit with pressure @ 2235 PSIG. Salem Unit 2 has no other shutdown Tech. Spec. action statements in effect. Prior to the initiating event Salem Unit 2 was raising power at 1/2 % per hour after 2R16 refueling outage.
"All ECCS and ESF Systems are available.
"No personnel injuries have occurred as a result of the shutdown.
"No radiological release due to this event.
"21 service water pump is cleared and tagged for strainer replacement. 21A and 23B circulating water pumps are cleared and tagged for maintenance."
The licensee notified the NRC Resident Inspector. |
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