| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
09/07/2012 - 09/10/2012 ** EVENT NUMBERS ** |
 | Part 21 | Event Number: 47833 | Rep Org: MITSUBISHI HEAVY INDUSTRIES, LTD.
Licensee: MITSUBISHI HEAVY INDUSTRIES, LTD
Region: 1
City: ARLINGTON State: VA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: EI KADOKAMI
HQ OPS Officer: JOHN KNOKE | Notification Date: 04/13/2012
Notification Time: 15:58 [ET]
Event Date: 02/21/2012
Event Time: [EDT]
Last Update Date: 09/07/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
| Person (Organization):
BLAKE WELLING (R1DO)
KATHLEEN O'DONOHUE (R2DO)
DAVID HILLS (R3DO)
VINCENT GADDY (R4DO)
PART 21 GROUP (EMAI)
| Event Text PART 21 INTERIM REPORT - STEAM GENERATOR TUBE WEAR
This interim Part 21 is in regard to San Onofre Nuclear Generating Station, Unit 2, Steam Generator replacement.
"During the first refueling outage following steam generator replacement, eddy current testing identified ten total tubes with depths of 90 to 28 percent of the tube wall thickness. Some of the affected tubes were located adjacent to retainer bars. The retainer bars are part of the floating anti-vibration bar (AVB) structure that stabilizes the u-bend region of the tubes.
"Other tubes in the two steam generators had detectable wear associated with support points elsewhere in the AVB structure. Each steam generator has 9727 tubes with an 8 percent (778 tubes) design margin for tube plugging.
"Discovery Date: February 13, 2012
"Evaluation completion schedule date: May 31, 2012"
"Those Mitsubishi Heavy Industries customers potentially affected by this issue have been notified and will receive a copy of this interim report."
Reference Document: UET-20120089
Interim Report No: U21-018-IR (0)
Notified R1DO (Joustra), R2DO (Nease), R3DO (Peterson), R4DO (O'Keefe), and Part 21 Group via email.
* * * UPDATE FROM MITSUBISHI HEAVY INDUSTRIES, LTD VIA FAX ON 6/4/12 AT 1145 EDT * * *
The vendor changed the number of tubes identified with wear depths of 90 to 28 percent from ten tubes to six tubes and only some of the tubes were adjacent to retainer bars.
Notified R1DO (Cahill), R2DO (Vias), R3DO (Passehl), R4DO (Gepford) and Part 21 Groups via email.
* * * UPDATE FROM MITSUBISHI HEAVY INDUSTRIES, LTD VIA FAX ON 9/7/12 AT 1539 EDT * * *
"MHI evaluated that the deviation contains a reportable defect for San Onofre Nuclear Generating Station Unit 2 and 3."
Notified R4DO (Gaddy) and Part 21 Reactor Group via email. |
| Part 21 | Event Number: 47990 | Rep Org: MITSUBISHI HEAVY INDUSTRIES, LTD.
Licensee: MITSUBISHI HEAVY INDUSTRIES, LTD.
Region: 1
City: ARLINGTON State: VA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: MIKE SCHULTZ
HQ OPS Officer: HOWIE CROUCH | Notification Date: 04/19/2012
Notification Time: 12:33 [ET]
Event Date: 02/13/2012
Event Time: [EDT]
Last Update Date: 09/07/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
| Person (Organization):
CHRISTOPHER CAHILL (R1DO)
STEVEN VIAS (R2DO)
DAVE PASSEHL (R3DO)
HEATHER GEPFORD (R4DO)
PART 21 GRP (EMAIL) ()
| Event Text PART 21 - STEAM GENERATOR TUBE WEAR ADJACENT TO RETAINER BARS
The following information was obtained from Mitsubishi Heavy Industries, LTD on April 19, 2012 was inadvertently added to Event Notification #47833 as an update to that event. The vendor's intent was to issue two interim reports; one for San Onofre Nuclear Generating Station (SONGS) Unit 2 and one for SONGS Unit 3. The information was obtained via fax:
"On January 31, 2012, San Onofre Unit 3 shut down due to indications of a steam generator tube leak. Steam generator tube inspections confirmed one small leak on one tube in one of the two steam generators. Continuing inspections of 100% of the steam generator tubes in both Unit 3 steam generators discovered unexpected wear, including tube to tube as well as tube to tube support structural wear. Inspection, testing, and analysis of SG tube integrity in both Unit 3 SGs is ongoing. In-situ pressure testing identified eight Unit 3 SG tubes that did not meet the target performance criteria in Technical Specification for tube integrity. One of the failed tubes was the leaking tube that required the Unit 3 shutdown.
"Discovery date: February 21, 2012
"Evaluation completion schedule date: August 31, 2012"
Interim Report: U21-019-IR
Reference Document: UET-20120105
Original notifications (per EN# 47833) were made to R1DO (Joustra), R2DO (Nease), R3DO (Peterson), R4DO (O'Keefe), and Part 21 Group via email.
Notified R1DO (Cahill), R2DO (Vias), R3DO (Passehl), R4DO (Gepford) and Part 21 Groups via email.
* * * UPDATE FROM MITSUBISHI HEAVY INDUSTRIES, LTD VIA FAX ON 6/4/12 AT 1145 EDT * * *
The vendor reported that eight Unit 3 SG tubes did not meet the target performance criteria in Technical Specifications for tube integrity.
Notified R1DO (Cahill), R2DO (Vias), R3DO (Passehl), R4DO (Gepford) and Part 21 Groups via email.
* * * UPDATE FROM MITSUBISHI HEAVY INDSUSTRIES, LTD VIA FAX ON 9/7/12 AT 1539 EDT * * *
"MHI evaluated that the deviation contains a reportable defect for San Onofre Nuclear Generating Station Unit 2 and 3."
Notified R4DO (Gaddy) and Part 21 Reactor Group. |
| !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 48246 | Facility: DIABLO CANYON
Region: 4 State: CA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAN STERMER
HQ OPS Officer: JOHN KNOKE | Notification Date: 08/29/2012
Notification Time: 00:16 [ET]
Event Date: 08/28/2012
Event Time: 17:00 [PDT]
Last Update Date: 09/08/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
DAVID PROULX (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text MITIGATING ACTIONS IMPLEMENTED FOR INOPERABLE CONTROL ROOM ENVELOPE
"On August 28, 2012, 17:00 PDT, Pacific Gas and Electric Company (PG&E) identified additional release pathways that could affect the control room (CR) operator dose following a Large-Break Loss-of-Coolant Accident (LBLOCA). Consequently, PG&E declared the control room envelope (CRE) inoperable and is establishing mitigative actions in accordance with TS 3.7.10, Action B.1, 'Initiate action to implement mitigating actions' immediately, and Action B.2, 'Verify mitigating actions ensure CRE occupant exposures to radiological hazards will not exceed limits, and CRE occupants are protected from smoke and chemical hazards' within 24 hours.
"PG&E is establishing mitigative actions in accordance with TS 3.7.10 and RG 1.196. These mitigative actions are for operations control room personnel to administer potassium iodide and don self-contained breathing apparatus equipment in a timely fashion should a LBLOCA occur. They will be communicated and controlled by a standing order to the control room staff.
"PG&E previously established controls on other release pathways that offset the potential increases to the maximum predicted offsite dose due to the new release pathways. No increase in maximum predicted offsite dose is expected from the new release pathways.
"Diablo Canyon (DCPP) is making this 8-hour, non-emergency notification under 10 CFR 50.72(b)(3)(ii)(B) and 10 CFR 50.72(b)(3)(v)(D).
"Plant personnel notified the NRC Resident Inspector."
* * * UPDATE AT 1600 EDT ON 9/8/12 FROM GLEN GOELZER TO PETE SNYDER * * *
"PG&E is retracting EN 48246, based on the results from a new dose analysis coupled with compensatory measures implemented to ensure that the analysis input parameters and assumption will not be inadvertently exceeded. The analysis concluded that the CRE was operable and that CR doses remained below regulatory limits.
"Plant personnel notified the NRC resident inspector."
Notified R4DO (Gaddy). |
| Agreement State | Event Number: 48254 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: HENLEY-JOHNSTON & ASSOCIATES, INC.
Region: 4
City: DALLAS State: TX
County:
License #: L00286
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: STEVE SANDIN | Notification Date: 08/30/2012
Notification Time: 13:25 [ET]
Event Date: 08/30/2012
Event Time: 09:45 [CDT]
Last Update Date: 08/30/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAVID PROULX (R4DO)
FSME RESOURCE (EMAI)
ILTAB via email ()
MEXICO via fax ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - STOLEN TROXLER MOISTURE DENSITY GAUGE
The following information was received from the State of Texas via email:
"On August 30, 2012, the licensee notified the Agency [Texas Department of State Health Services] that at approximately 0945 hrs CDT a Troxler model 3430 moisture/density gauge, containing a 40 millicurie Americium-241/Beryllium source and an 8 millicurie Cesium-137 source, had been stolen out of the back of one of its pickup trucks [a white Chevrolet C-1500] outside a hotel in Lubbock, Texas. The licensee's employee had gone inside to check out of the hotel and when he came back outside he found both chains securing the gauge had been cut and the gauge was gone. The local police department was notified by the employee. The licensee will notify the manufacturer and other gauge service companies. The Agency will notify the Texas Association of Pawn Brokers. An investigation into this event is ongoing and information will be updated as it is received per SA-300 [Reporting Material Events].
"Gauge Information: Troxler Model 3430, Serial # 25088
"Sources: Americium-241/Beryllium -- 40 millicuries -- Serial #75-7262, Cesium-137 -- 8 millicuries -- 47-21295"
Texas Incident #: I-8981
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 |
| Agreement State | Event Number: 48256 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: MDI OF ABILENE
Region: 4
City: ABILENE State: TX
County:
License #: L06133
Agreement: Y
Docket:
NRC Notified By: CHRIS MOORE
HQ OPS Officer: STEVE SANDIN | Notification Date: 08/30/2012
Notification Time: 14:53 [ET]
Event Date: 08/30/2012
Event Time: [CDT]
Last Update Date: 08/30/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAVID PROULX (R4DO)
FSME RESOURCE (EMAI)
ILTAB via email ()
MEXICO via fax ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text AGREEMENT STATE REPORT - IMPROPER SALE AND TRANSFER OF RADIOACTIVE SOURCE
The following information was received from the State of Texas via email:
"On August 30, 2012, a company contracted by a licensee to conduct a closeout of an imaging facility notified the Agency [Texas Department of State Health Services] that the licensee had sold an ADAC Gamma/PET Camera early in 2012 without proper shipping and transfer paperwork and with a 20 millicurie Cesium-137 seal source located inside the PET scanner. The PET scanner with internal source was brokered and sold to a company overseas. Details of the date of sale, broker company, and who purchased the device are unknown. An investigation into this event is ongoing and information will be updated as it is received per SA 300 [Reporting Material Events].
"The State of Texas event number for this event is I - 8982.
"Equipment: ADAC Gamma/PET Camera
"Source: Cesium-137 -- 20 millicuries -- CZ882"
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. |
| Non-Agreement State | Event Number: 48259 | Rep Org: ACUREN INSPECTION
Licensee: ACUREN INSPECTION
Region: 1
City: CHARLESTON State: WV
County:
License #: 42-27593-01
Agreement: N
Docket:
NRC Notified By: CHRIS DIXON
HQ OPS Officer: JOHN KNOKE | Notification Date: 08/31/2012
Notification Time: 09:54 [ET]
Event Date: 04/28/2012
Event Time: 09:45 [EDT]
Last Update Date: 08/31/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
JOHN ROGGE (R1DO)
FSME RESOURCE (EMAI)
| Event Text IR-192 SOURCE DISCONNECTED FROM RADIOGRAPHY CAMERA
At 0945 hours on 4-28-2012, the radiographer at the jobsite in Willeysville, WV reported to his Division Manager that the source in a Sentinel 880 Delta camera, S/N D4132, was disconnected and could not be retracted into the shielded position following the first exposure. The Division Manager contacted the Acuren Cincinnati RSO for assistance. Arrangements were made for both the Division Manager and Cincinnati RSO who had extensive experience in source retrieval to respond to the jobsite. The source was successfully retrieved by 1805 hours the same day.
The camera, crank, guide tube, and quick connect were transported to the Ona lab to be shipped to QSA for investigation on Monday morning, 4-30-2012.
There were no personnel overexposures associated with this incident.
Corrective actions included: All radiographic personnel were immediately notified of the source disconnect incident to raise awareness of equipment checks and no-go-gage test. Acuren Division Manager and RSO conducted the misconnect test [Acuren terminology] on all radiographic equipment cranks and cameras as of 5-4-12. |
| Agreement State | Event Number: 48260 | Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: UNIVERSITY OF VIRGINIIA
Region: 1
City: CHARLOTTESVILLE State: VA
County:
License #: 540-248-1
Agreement: Y
Docket:
NRC Notified By: CHARLES COLEMAN
HQ OPS Officer: STEVE SANDIN | Notification Date: 08/31/2012
Notification Time: 15:19 [ET]
Event Date: 08/31/2012
Event Time: [EDT]
Last Update Date: 08/31/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JOHN ROGGE (R1DO)
FSME EVENT RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - PATIENT RECEIVED LESS THAN THE PRESCRIBED FRACTIONAL DOSE
The following information was received from the Commonwealth of Virginia via email:
"On August 31, 2012, the licensee reported that a wire drift error occurred during a high dose rate afterloader procedure on August 31. The patient undergoing a tandem and ovoid treatment was scheduled to receive a fraction dose of 6 Gray. Because of the wire drift error the fraction was terminated prior to completion and the patient received only 0.73 Gray. The licensee has informed the patient and the referring physician. The cause of the error and the patient's revised treatment plan are being reviewed by the licensee. The Virginia Radioactive Material Program will review the circumstances of the event."
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient. |
| Agreement State | Event Number: 48261 | Rep Org: NV DIV OF RAD HEALTH
Licensee: UNIVERSITY OF NEVADA
Region: 4
City: LAS VEGAS State: NV
County:
License #: 03-13-0305-01
Agreement: Y
Docket:
NRC Notified By: SNEHA RAVIKUMAR
HQ OPS Officer: STEVE SANDIN | Notification Date: 08/31/2012
Notification Time: 15:48 [ET]
Event Date: 10/01/2011
Event Time: [PDT]
Last Update Date: 08/31/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAVID PROULX (R4DO)
FSME EVENT RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - STUDENT RECEIVED POTENTIAL INHALATION OVEREXPOSURE
The following information was received from the State of Nevada via email:
"A graduate student inhaled a mixture of U-233 and U-238 while working in the lab grinding a compound of Uranium Octoxide. [The graduate student] used a glove box instead of the hood with the HEPA filter, contrary to UNLV [University of Nevada Las Vegas] approved procedure.
"This happened twice and could have been between October 1, 2011 and April 1, 2012.
"The first bioassay, based on an inhalation date of October 1, 2011, showed 17.72 rem total. When the inhalation date was assumed to be April 1, 2012, the result was 5.52 rem.
"[U-233]*1.6 = [U-238] contribution.
"The student will be getting a third bioassay on September 5, 2012 at the Lawrence Livermore National Lab (LLNL). This will involve a low-energy chest count to detect Th-234 and an organ count, looking at the kidneys for Uranium.
"The student has been restricted from all lab work since April.
"The bioassay was done at Test America." |
| Part 21 | Event Number: 48285 | Rep Org: AMETEK SOLIDSTATE CONTROLS
Licensee: AMETEK SOLDSTATE CONTROLS
Region: 3
City: COLUMBUS State: OH
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ROBERT GEORGE
HQ OPS Officer: PETE SNYDER | Notification Date: 09/07/2012
Notification Time: 12:45 [ET]
Event Date: 03/14/2012
Event Time: [EDT]
Last Update Date: 09/07/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
KENNETH RIEMER (R3DO)
PART 21 REACTOR GRP (EMAI)
| Event Text PART 21 - IMPROPER SELECTION OF INVERTER CAPACITORS
"PRODUCT: 10 KVA inverter Model 86VC0100-15, 3 phase 480 VAC output. Limited to systems supplied to Exelon Byron and Braidwood units. Capacitors C10 through C15 part number 03-040060-00.
"COMPONENT DESCRIPTION: Suppression capacitors, Ametek part number 03-040060-00, used in positions C10 through C15 on Model 86-VC0100-15 only.
"PROBLEM YOU COULD SEE: Capacitor could arc internally and open internally and externally.
"CAUSE: the manufacturer's investigation revealed that due to improper selection of capacitor used may fail due to a corona effect internally.
"EFFECT ON SYSTEM PERFORMANCE: The capacitor may short internally and open circuit by forcing lead separation from the device.
"ACTION REQUIRED: Replace the capacitor(s) with Ametek part 03-040041-20. The replacement is rated at 370 VAC and used in a 277 VAC circuit.
"AMETEK SOLIDSTATE CONTROLS CORRECTIVE ACTION: The defect is limited to the units supplied to Exelon Byron and Braidwood plants under Ametek joc C103552."
Both the Byron and Braidwood plants are already informed of this condition. |
| Fuel Cycle Facility | Event Number: 48287 | Facility: AREVA NP INC RICHLAND
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION
FABRICATION & SCRAP
COMMERCIAL LWR FUEL
Region: 2
City: RICHLAND State: WA
County: PENTON
License #: SNM-1227
Agreement: Y
Docket: 07001257
NRC Notified By: CALVIN MANNING
HQ OPS Officer: PETE SNYDER | Notification Date: 09/07/2012
Notification Time: 19:18 [ET]
Event Date: 09/07/2012
Event Time: 15:53 [PDT]
Last Update Date: 09/07/2012 | Emergency Class: ALERT
10 CFR Section:
70.32(i) - EMERGENCY DECLARED
| Person (Organization):
MARK LESSER (R2DO)
VICTOR MCCREE (R2)
SCOTT MOORE (NMSS)
GORDON BJORKMAN (NMSS)
JANE MARSHALL (IRD)
| Event Text FIRE IN PLASMA CUTTER RECIRCULATING VENTILATION SYSTEM
"At 1553 PDT Areva Richland declared an Alert due to a fire [greater than 15 minutes] in the waste handling / packaging area within the UO2 Building. The fire was associated with a plasma cutter HEPA filter in the recirculation system. The plasma arc filter is a stand alone filter that recirculates the air into the room. The room ventilation system has two HEPA filters in series before it exhausts out of the stack.
"Personnel in the building evacuated when a smoke alarm activated. All personnel from the evacuated building were accounted for. The fire was confined to the plasma cutter filters and is now believed to be extinguished."
Notified DHS, DOE, DHS NICC, HHS, EPA, USDA and Canada.
* * * UPDATE FROM CALVIN MANNING TO JOHN KNOKE AT 0036 EDT ON 09/08/12 * * *
At 1609 PDT the fire was extinguished and a re-flash watch set. The ventilation system in the UO2 Building was restored. The area of the fire is quarantined off, pending further investigation. No injuries were reported and there were no offsite radiological releases. At 2135 PDT, Areva Richland exited the Alert.
Notified R2DO (Lessor), IRD (Marshall), NMSS (Bjorkman), DHS, DOE, DHS NICC, HHS, EPA, USDA and Canada. |
| Power Reactor | Event Number: 48288 | Facility: ROBINSON
Region: 2 State: SC
Unit: [2] [ ] [ ]
RX Type: [2] W-3-LP
NRC Notified By: GEORGE CURTIS
HQ OPS Officer: JOHN KNOKE | Notification Date: 09/08/2012
Notification Time: 08:16 [ET]
Event Date: 09/08/2012
Event Time: 08:00 [EDT]
Last Update Date: 09/08/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MARK LESSER (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text EMERGENCY OFFSITE FACILITY/TECHNICAL SUPPORT CENTER VENTILATION MAINTENANCE
"This is a non-emergency eight hour notification for a loss of Emergency Assessment Capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) because the work activity affects the functionality of an emergency response facility.
"Planned maintenance activities are being performed today to the Emergency Offsite Facility (EOF)/Technical Support Center (TSC) HVAC. The work entails replacement of a pressure switch. The filtration portion of the system will not be affected by this work. This work activity is planned to be performed and completed expeditiously within about 3.5 hours including establishing and removing the clearances and performing post maintenance testing; however, restoration time required during the maintenance could exceed the time required to activate the TSC.
"If an emergency condition occurs that requires activation of the EOF and TSC, plans are to utilize the EOF and TSC during the time this work activity is being performed as long as habitability conditions allow. The Emergency Response Organization team members will be relocated to alternate locations if required by habitability conditions in accordance with emergency implementing procedures. Alternate emergency response facilities will remain available in the event that relocation is necessary."
The licensee has notified the NRC Resident Inspector. Licensee has also notified state and local agencies.
* * * UPDATE FROM GEORGE CURTIS TO DONALD NORWOOD AT 1025 EDT ON 9/8/2012 * * *
The maintenance work was completed. The TSC and EOF were declared operable as of 1025 EDT. The licensee will notify the NRC Resident Inspector.
Notified R2DO (Lesser). |
| Power Reactor | Event Number: 48289 | Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: KEITH MAESTAS
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 09/08/2012
Notification Time: 13:12 [ET]
Event Date: 09/08/2012
Event Time: 12:30 [EDT]
Last Update Date: 09/08/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MARK LESSER (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 12 | Power Operation | 12 | Power Operation | | 4 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text HISTORICAL TECHNICAL SUPPORT CENTER VENTILATION EVALUATION DEFICIENCY
"FPL (Florida Power & Light) previously reported (EN 47819) that a portion of the Turkey Point Technical Support Center (TSC) Heating Ventilation and Air Conditioning System (HVAC) was deenergized for maintenance during two extended periods. FPL concluded that due to the condition, the TSC may not have been fully functional under every postulated design basis accident scenario. As a result of further investigation, FPL has been unable to validate the historical TSC design basis assumptions for habitability for an indeterminate period in the past. Among the issues identified include (a) seized HVAC isolation damper, (b) unsecured HVAC balancing damper, and (c) voids in the concrete shield wall. Additionally, while the original design basis did not provide for any unfiltered air inleakage, the HVAC system was constructed and maintained to ensure only that a positive pressure could be achieved.
"FPL has addressed the TSC issues. A new dose analysis and recent tracer gas test have established TSC compliance with the current licensing basis. Therefore, the TSC is fully functional at this time.
"This report is made for historical conditions in accordance with 10 CFR 50.72(b)(3)(xiii)."
The licensee notified the NRC Resident Inspector. | |