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Event Notification Report for July 30, 2004

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
07/29/2004 - 07/30/2004

** EVENT NUMBERS **


40889 40898 40900 40904 40905 40906 40908

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 40889
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: JIM MILLIGAN
HQ OPS Officer: STEVE SANDIN
Notification Date: 07/21/2004
Notification Time: 19:32 [ET]
Event Date: 07/21/2004
Event Time: 11:55 [CDT]
Last Update Date: 07/29/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
TOM FARNHOLTZ (R4)

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

EOF DECLARED INOPERABLE DUE TO UNACCEPTABLE AIR FLOW RATES IN FILTRATION MODE

"At 1155, 7/21/04, Callaway Plant declared the Emergency Offsite Facility (EOF) inoperable due to unacceptable air flow rates when the ventilation system was in the Filtration mode. Normally the ventilation system is designed to operate with a positive pressure in the EOF in order to prevent in-leakage of unfiltered air. During regularly scheduled maintenance, it was discovered that if a fume hood exhaust fan was operated with the EOF ventilation in the Filtration mode, it was possible to develop a negative pressure condition within the EOF. A station Work Request has been generated and ventilation equipment has been aligned so that a positive pressure can be maintained until the problem has been corrected."

The licensee noted that regularly scheduled maintenance is performed on a yearly frequency. The licensee informed the NRC Resident Inspector.


* * * UPDATE ON 07/29/04 @ 1640 BY EURMAN HENSON TO CHAUNCEY GOULD * * * RETRACTION

7/29/04: A review was conducted of both the test data obtained on 7/21/04 and the methodology utilized. This review determined that the methodology was incorrect and resulted in unsatisfactory test data. The test was performed again on 7/23/04 with satisfactory results. Based upon this information, it was concluded that the EOF had not been inoperable as initially reported and this Event Notification is being retracted.

The NRC Resident Inspector was notified.

Notified Reg 4 RDO (Russ Bywater)

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General Information or Other Event Number: 40898
Rep Org: COLORADO DEPT OF HEALTH
Licensee: COLORADO STATE UNIVERSITY
Region: 4
City: FORT COLLINS State: CO
County:
License #: 002-27
Agreement: Y
Docket:
NRC Notified By: ED STROUD
HQ OPS Officer: STEVE SANDIN
Notification Date: 07/27/2004
Notification Time: 12:42 [ET]
Event Date: 07/26/2004
Event Time: [MDT]
Last Update Date: 07/27/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RUSSELL BYWATER (R4)
CHARLIE MILLER (NMSS)

Event Text

AGREEMENT STATE REPORT INVOLVING STUCK IRRADIATOR SOURCE

Yesterday, July 26, 2004, Colorado State University, a Colorado licensee, notified the Department that a source used in one of their panoramic irradiators became stuck in the exposed position during a routine service check. The University's Radiation Safety Officer locked and posted the irradiator room to prevent further entry. The room was designed for irradiator use, so, there is no potential for exposures to staff or members of the public. The maker of the irradiator, JL Shepherd, was notified, and a plan is being developed to manually move the source to the shielded position.

Location: Colorado State University, Fort Collins, Colorado
License: Colorado # 002-27
Irradiator: JL Shepherd Model #354
Source: Amersham, Cs-137, 21.7 Ci

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General Information or Other Event Number: 40900
Rep Org: WA DIVISION OF RADIATION PROTECTION
Licensee: NORTHWEST INSPECTION
Region: 4
City: SPOKANE State: WA
County:
License #: WN-IR065-1
Agreement: Y
Docket:
NRC Notified By: ARDEN C. SCROGGS
HQ OPS Officer: STEVE SANDIN
Notification Date: 07/27/2004
Notification Time: 14:55 [ET]
Event Date: 06/25/2004
Event Time: [PDT]
Last Update Date: 07/27/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RUSSELL BYWATER (R4)
PATRICIA HOLAHAN (NMSS)

Event Text

AGREEMENT STATE REPORT INVOLVING A STOLEN/RECOVERED RADIOGRAPHY CAMERA

The following information was provided by the State of Washington to the NRC via email:

"This is notification of an event in Washington State as reported to or investigated by the WA Department of Health, Office of Radiation Protection.

"STATUS: new

"Licensee: Northwest Inspection
"City and State: Richland, Washington
"License Number: WN-IR065-1
"Type of License: Industrial Radiography

"Date of Event: 25 June 2004 (reported July 26)

"Location of Event: Spokane, Washington
"ABSTRACT: (where, when, how, why; cause, contributing factors, corrective actions, consequences, Dept. of Health (DOH) on-site investigation; media attention):

"The licensee's radiation safety officer reported that they had had a radiography vehicle stolen, with a radiography exposure device secured inside (device and source information not yet known). The Radiographer, at the end of the day, had left the radiography vehicle unattended while that Radiographer entered a work-site office to complete paperwork. The Assistant Radiographer had left the work-site earlier when actual radiography had concluded.

"During the brief time the vehicle was unattended, reported to be about 2 minutes, the vehicle was taken. The Radiographer called the police and the radiation safety officer when the vehicle was noticed missing.

"A short time later, reported to be about 30 minutes, a Spokane area resident noticed the truck, stuck by the side of the road. The resident used licensee identification, from the outside of the vehicle, to contact the licensee. The licensee had the resident call local police. The police secured the vehicle. Later, the licensee recovered the vehicle. The locked camera storage/transportation container had not been disturbed.

"No Media attention noted.

"Notification Reporting Criteria: 10 CFR, Part 20.2201(a)(1)(ii)

"Isotope and Activity involved: Not yet known

"Overexposures? (number of workers/members of the public; dose estimate; body part receiving dose; consequence): None, N/A

"Lost, Stolen or Damaged? (mfg., model, serial number): Stolen (briefly), camera and source information is not yet known.

"Disposition/recovery: Recovered without additional incident.

"Leak test? Not yet known

"Vehicle: (description; placards; Shipper; package type; Pkg. ID number)
"The vehicle is a combination of pick-up truck with industrial trailer. The trailer serves as the darkroom and camera storage. No placards since package was a Yellow II. Type B package inside a convenience over-pack.

"Release of activity? None, N/A

"Event Report # WA-04-043"

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Power Reactor Event Number: 40904
Facility: SALEM
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRUCE LASHBROOK
HQ OPS Officer: JOHN MacKINNON
Notification Date: 07/29/2004
Notification Time: 02:15 [ET]
Event Date: 07/28/2004
Event Time: 21:00 [EDT]
Last Update Date: 07/29/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
Person (Organization):
JAMES TRAPP (R1)

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

UNIDENTIFIED REACTOR COOLANT SYSTEM (RCS) LEAK


"This is an 8-hour notification being made to report exceeding the design basis for the reactor coolant leakage outside of containment. An unidentified reactor coolant system (RCS) leak of 1.0 gpm on Salem Unit 1 occurred on 7/28/04 at 2100 hours. It was discovered (that) a pressure instrument weld from 13 charging pump [PDP] discharge piping failed in the auxiliary building. Tech Specs for RCS unidentified leakage was entered. Station abnormal operating procedures (ABRC-001 RCS Leak) were entered and leakage monitoring program referenced. The leak was isolated closing the root valve of the instrument line (discharge pressure transmitter) by 2135 hours. The RCS leakage was outside of containment and was greater than design of 3840 cc/hr. This leakage would have exceeded the GDC-19 limits for control room habitability during the time of the leak initiation and leak isolation. 13 charging pump remained in service and the leak is locally isolated. The tech spec for RCS unidentified leakage was exited and ASME tech spec for the failed weld was entered. There were no unusual or unexpected responses. All systems functioned as required. There were no personnel injuries."

A maintenance tech in the auxiliary building notified control room of a leak about the same time that control room personnel noticed that the Volume Control Tank level was decreasing approx. 0.3gpm. The area around the Positive Displacement Pump (PDP) was roped off and the leak was isolated. Airborne levels in the roped off area was 8000 cpm (from 2130 to 2200 hours). Nobody was evacuated from auxiliary building. At 0040 hours airborne samples were within normal limits. The area around # 13 PDP is still roped off until the surface contamination is cleaned up. Lower Alloways Creek Township will be notified of this by the licensee.

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

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Power Reactor Event Number: 40905
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: KEN CHISM
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 07/29/2004
Notification Time: 12:14 [ET]
Event Date: 07/29/2004
Event Time: 09:42 [EDT]
Last Update Date: 07/29/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
THOMAS DECKER (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 88 Power Operation 46 Power Operation

Event Text

PLANT ENTERED LCO ACTION STATEMENT DUE TO MALFUNCTION OF A SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER.

On July 29, 2004, at approximately 0351 hours, testing of Suppression Chamber-to-Drywell vacuum breakers commenced in accordance with Periodic Test 0PT02.3.1, "Suppression Chamber-to-Drywell Vacuum Breaker Operability Test." At 0357 hours, it was determined that vacuum breaker 2-CAC-X18D had an open indication. Technical Specifications (TS) Limiting Condition for Operation (LCO) 3.6.1.6, "Suppression Chamber-to-Drywell Vacuum Breakers," Condition B was entered for one suppression chamber-to-drywell vacuum breaker (2-CAC-X18D) not indicating closed. Required Action B.1 of TS LCO 3.6.1.6 provides 4 hours to verify the vacuum breaker closed. Attempts to confirm the vacuum breaker closed were unsuccessful and at 0757 hours, TS LCO 3.6.1.6 Condition C was entered. Required Action C.1 is to be in Mode 3 (Hot Shutdown) in 12 hours and Required Action C.2 is to be in Mode 4 (Cold Shutdown) in 36 hours. Initiation of the plant shutdown required by TS LCO 3.6.1.6 commenced at 0942 hours.

This condition is being reported in accordance with 10 CFR 50.72(b)(2)(i) as the initiation of any nuclear plant shutdown required by the plant's TS.

INITIAL SAFETY SIGNIFICANCE EVALUATION

The initial safety significance of this condition is considered to be minimal. The actual position of the vacuum breaker cannot be confirmed, however if one vacuum breaker was not closed, communication between the drywell and suppression chamber air space could occur, and as a result, there is a potential, for primary containment overpressurization due to this bypass leakage if a loss of coolant accident were to occur. The plant is currently proceeding to hot shutdown with all Emergency Core Cooling systems operable.

CORRECTIVE ACTIONS

Determine the required corrective actions after entry into the drywell following shutdown. The safety significance of the event will be reviewed when the actual condition of the vacuum breaker is known.

The NRC Resident Inspector has been notified.

* * * UPDATE ON 07/29/04 @ 1654 FROM KEN CHISM TO CHAUNCEY GOULD * * *

On July 29, 2004, at 1517 hours, a manual scram was inserted to shut down the Unit 2 reactor from approximately 23 percent of rated thermal power. The reactor shutdown was implemented to meet the requirements of Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.6 Required Action C.1 to be in Mode 3 in 12 hours. All control rods fully inserted into the core and no ECCS actuation occurred or relief valves lifted. Following the scram, an expected reactor vessel coolant level shrink occurred causing coolant level to decrease below the Low Level 1 setpoint. This coolant level decrease resulted in a Primary Containment Isolation Valve isolation signal to Group 2 (Drywell Equipment and Floor Drain, Traversing In-core Probe, Residual Heat Removal (RHR) Discharge to Radwaste, and RHR Process Sample), Group 6 (Containment Atmosphere Control/Dilution, Containment Atmosphere Monitoring, and Post Accident Sampling System), and Group 8 (RHR Shutdown Cooling Suction and RHR Inboard Injection) isolation valves. The isolation signal closed all of the valves that were open at the time of the expected initiation.

The plant is currently in mode 3 and proceeding with a normal cooldown to Mode 4.

The NRC Resident Inspection was informed.

Notified Reg 2 RDO (Tom Decker).

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Power Reactor Event Number: 40906
Facility: DAVIS BESSE
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] B&W-R-LP
NRC Notified By: LARRY MYERS
HQ OPS Officer: HOWIE CROUCH
Notification Date: 07/29/2004
Notification Time: 12:51 [ET]
Event Date: 07/29/2004
Event Time: 11:03 [EDT]
Last Update Date: 07/29/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JOHN MADERA (R3)
SUZANNE BLACK (NRR)

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

INDUSTRIAL ACCIDENT ON THE OWNER CONTROLLED AREA

The following information was received from the licensee via facsimile:

"(Time 1103 hrs.[EDT]) A lawn mowing company was working outside the protected area when a mower rolled over on the individual doing the mowing. The mowing evolution was near a pond. The mower went over the edge of the pond, landing in the water. The individual operating the mower was trapped under the mower in the water. Several employees from the Davis Besse training center saw the mower in the water and pulled the individual from the water. The victim was not breathing at that time.

"CPR was performed and Life Flight called. Helicopter on site at 1123 [hrs.] and transported victim to St. Vincent Hospital. Helicopter lifted off from the site at 1138 [hrs.]. The victim was breathing on her own at that time but still unconscious."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 40908
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [ ] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: RAGER ORZELL
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 07/29/2004
Notification Time: 15:46 [ET]
Event Date: 07/29/2004
Event Time: 12:10 [EDT]
Last Update Date: 07/29/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JAMES TRAPP (R1)

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

OFFSITE NOTIFICATION DUE TO RAW SEWAGE DISCHARGE TO LAKE ONTARIO

A report was received in the Unit 2 Control Room by Site personnel that raw sewage appeared to be seeping from a manhole inside the protected area. The Fire Department and Environmental Department were dispatched to the area. It was reported back to the Unit 2 Control Room that raw sewage was seeping from the manhole and filling nearby ditch and flowing to a storm sewer.

Due to the leakage, Nine Mile Point entered their HAZMAT response procedure. Initial investigation for the sewage release found the sewage lift station pumps' control switch in the "OFF" position preventing the pumps from operating. The lift station pumps were restarted and the discharge from the manhole stopped. Lift station pumps continue to function properly and cleanup efforts are underway. Investigation is underway on why the lift station pump control switches were in the off position. Based upon initial calculations, it was determined approximately 3000 gallons of raw sewage was released from manhole to a nearby storm sewer which discharges to Lake Ontario.

Nine Mile Point has notified the Oswego County Department of Health and New York State Department of Environmental Conservation. No hazards exist to offsite personnel and no wildlife has been adversely affected.


The Licensee notified the NRC Resident Inspector, Local and State agencies.

Page Last Reviewed/Updated Friday, March 30, 2012
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