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Event Notification Report for September 22, 2003

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
09/17/2003 - 09/22/2003

** EVENT NUMBERS **


40049 40154 40155 40160 40164 40165 40166 40168 40170 40171 40172
40173 40174 40175 40176 40177 40178 40179 40181 40182 40183 40184 40185
40186 40187

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 40049
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: GEORGE STOROLIS
HQ OPS Officer: BILL GOTT
Notification Date: 08/06/2003
Notification Time: 19:12 [ET]
Event Date: 08/06/2003
Event Time: 16:30 [EDT]
Last Update Date: 09/18/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
CLIFFORD ANDERSON (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

UNANALYZED CONDITION

"On 8/06/2003 at 1630 hours, the Beaver Valley Power Station (BVPS) Unit 2 control room was notified by Engineering that the manual operator actions specified in Unit 2 post-fire procedures are not adequate for defeating a potential fire-induced spurious operation of the Power Operated Relief Valves (PORVs). The procedure step de-energizes the PORVs by opening breakers at the d-c distribution panel. This action alone would not be sufficient to prevent a cable-to-cable hot short from re-energizing the circuit since the de-energized circuit is routed in cable trays with other energized circuits in the affected fire areas. Preliminary reviews have identified the following potentially affected fire areas:

CB-1 Control Building Instrumentation and Relay Area
CB-2 Control Building Cable Spreading Room
CB-3 Control Building Main Control Room
CB-6 Control Building West Communication Room
CT-1 Cable Tunnel
CV-1 Cable Vault and Rod Control Area
SB-1 Emergency Switchgear Room (Orange)
RC-1 Reactor Containment

"An hourly roving fire watch patrol has been established for the affected fire areas as compensatory measures, with the exception of the Main Control Room and the Reactor Containment area, until the condition is fully evaluated and resolved. The Main Control Room is continuously manned and does not require an hourly fire watch patrol. The Reactor Containment area is not accessible during normal power operations and, as such, compensatory measures for this area will include a once-per-shift verification of remote instrumentation by operations personnel to confirm that there are no abnormal conditions or indications for this area.

"This condition was discovered during the review of manual operator actions for fire-induced spurious operations to confirm the safe shutdown circuit analysis is consistent with the manual actions identified in the procedures.

"This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii) as an unanalyzed condition that significantly degraded plant safety since the failure to assure the PORVs remain in the closed position could result in the failure to meet the fire protection safe shutdown criteria. BVPS Unit 2 was licensed to the NUREG 0800 Standard Review Plan 9.5.1 "Fire Protection Program", and License Condition 2.F requires compliance to the provisions of the approved fire protection program as described in the Final Safety Analysis Report. UFSAR Section 9.5A.1.2.1.6 states that the safe shutdown capability should not be adversely affected by a fire in any plant area which results in spurious actuation of the redundant valves in any one high-low pressure interface line. Even though there is a very low likelihood of multiple shorts causing a spurious PORV actuation in an ungrounded DC circuit, the existing actions to prevent re-energizing the circuit and causing a spurious actuation of the PORVs is not consistent with the NRC guidance for high-low pressure interface valves.

"The NRC resident inspector has been notified."

* * * UPDATE ON 8/7/03 AT 1726 EDT FROM D. SOMMERS TO E. THOMAS * * *

"On 8/07/03 at 1515, the following additional areas were identified as being potentially affected by this condition:

CV-2 Cable vault and Rod Control Area (East)
CV-3 Cable vault and Rod Control Area (Elev 755'6")
SB-2 Emergency Switchgear Room (Purple)
SB-3 Service Bldg. Cable Tray Area
ASP Alternative Shutdown Panel Room

"Interim compensatory measures in the form of hourly roving watch patrols have been expanded to include the above noted areas until the condition is fully evaluated and resolved.

"The NRC Resident Inspector has been notified."

Notified the Region 1 Duty Officer (C. Anderson)

* * * UPDATE 0940 EDT ON 9/18/03 FROM PETE SENA TO S. SANDIN * * *

The licensee is retracting this report based on the following:

"Beaver Valley Power Station (BVPS) Unit No. 2 retracts the notification made on 08/06/2003 at 19:12 hrs regarding the event reported under 10 CFR 50.72(b)(3)(ii)(B) [ENS #40049]. The previous notification identified a potential unanalyzed condition that significantly degraded plant safety since the failure to assure the PORVs remain in the closed position could result in the failure to meet the Fire Protection Program safe shutdown criteria.

"The postulated event for spurious PORV opening due to an external cable-to-cable hot short from a fire was subsequently analyzed. It was determined that since the reactor core does not experience an unrecoverable plant condition and the radiological conditions remained bounded by analyzed DBAs, the plant's safe shutdown capability for a fire event is maintained. Although the now-credible spurious opening of a PORV is a deviation from the current Fire Protection Program criteria, the results of the spurious PORV opening does not adversely impact the plant's safe shutdown capability and hence is not a significant degradation of plant safety. Therefore this condition is not reportable pursuant to either 10 CFR 50.72(b)(3)(ii)(B) nor 50.73(a)(2)(ii)(B) as an unanalyzed condition that significantly degraded plant safety.

"Compensatory measures in the form of shiftly fire watch patrols for the affected fire areas, with the exception of the Main Control Room and Reactor Containment area (as described in prior notifications), will remain in place until the Fire Protection Program non-conformance issue is dispositioned."

The licensee informed the NRC Resident Inspector. Notified R1DO(Gray).

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General Information or Other Event Number: 40154
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: UNKNOWN
Region: 4
City:  State: CA
County: CONTRA COSTA
License #:
Agreement: Y
Docket:
NRC Notified By: MARK GOTTLIEB
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/12/2003
Notification Time: 12:39 [ET]
Event Date: 09/09/2003
Event Time: [PDT]
Last Update Date: 09/12/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
LINDA HOWELL (R4)
FRED BROWN (NMSS)

Event Text

AGREEMENT STATE REPORT INVOLVING A RECOVERED SOURCE

"At 4:30 pm on 9/9/03 the radiation alarm pegged at off scale at the Keller Canyon Land fill from a load of trash from the Contra Costa Transfer Station. The facility's Bicron probe indicated (off scale) on the drivers side of the truck. The passenger side probe was fluctuating above normal but not off scale. [DELETED], the Operations Manager informed RHB Berkeley of the radiation alarms and that Contra County Environmental Health had also been notified. Based upon this conversation it was determined that the truck will be secured in a restricted area and access will be restricted and warning tape and signs will be used. Arrangements were made to visit the facility on 9/10/03 to determine the cause of the radiation alarms.

"The facility was visited on 9/10/03 and after surveys it was determined the source of the radiation alarms was cesium 137. The maximum reading on side of the dump truck was 2.5 milliRem/hr and 0.7 mRem at one meter using an Eberline RO 20 Calibrated 4/03. A Bicron Fieldspec was also used and it was determined that radiation was from cesium 137 based upon the 662 kev gamma photon. The truck was moved to an isolated area and the driver using hydraulics pushed the load out as while surveys were conducted to indicate when the source of radiation had left the truck. Based upon the identification of cesium 137 a sealed source was suspected. After the surveys indicated the source of the radiation was on the ground, rakes and wood were used to move the trash to identify the location of the source. Following surveys and raking, a small one inch cylinder or rod was identified as the source of the radiation readings. The source resembled the end of a moisture density gauge source rod. Based upon surveys it was calculated that the source contained about 8-10 milliCuries of cesium 137. Using tools the rod was placed in a lead pig and transported to CPN for further investigation. The investigation will try to determine if the rod was cut or broken off the source rod and if the serial number on the source can be used to locate it's previous owner. Surveys of the load and truck using a Ludlum Survey meter with a pancake G-m model 44-9 probe indicated their was no contamination from the source. CPN will also perform a leak on the source.

"Troxler and Pacific Nuclear were also contacted to see if there were any unusual requests for a new source rod in the last six months. Both companies indicated they were not aware of any such requests. Further information will be provided following this investigation.

"The engraved source capsule serial number is CDCW 556, 9290. This information has been reported to Troxler, Rancho Cordova, who will report it to the RSO, Troxler, North Carolina, where source/gauge/customer files are kept."

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General Information or Other Event Number: 40155
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: RABA-KISTNER CONSULTANTS, INC.
Region: 4
City: SAN ANTONIO State: TX
County:
License #: L01571-000
Agreement: Y
Docket:
NRC Notified By: JAMES H. OGDEN, JR.
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/12/2003
Notification Time: 16:44 [ET]
Event Date: 07/30/2003
Event Time: [CDT]
Last Update Date: 09/12/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
LINDA HOWELL (R4)
PATRICIA HOLAHAN (NMSS)

Event Text

AGREEMENT STATE REPORT INVOLVING A STOLEN TROXLER GAUGE

A Troxler Model 3411, Serial No 10540, containing two sealed sources: 1.48 GBq/40mCi (+/- 10%), Am-241:139, Serial No. 46-1962 and 0.30 GBq/8 mCi (+1-10%), Cs-137, Serial No. 40-7974, was stolen from an employee's truck at his residence. The cable securing the case had been cut and the case pried open with the gauge, calibration (standard) block and gauge paperwork removed. A police report was submitted to the San Antonio Police Department.

Texas Incident No.: I-8051

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General Information or Other Event Number: 40160
Rep Org: UTAH DIVISION OF RADIATION CONTROL
Licensee: UTAH VALLEY REGIONAL MEDICAL CENTER
Region: 4
City: PROVO State: UT
County:
License #: UT2500129
Agreement: Y
Docket:
NRC Notified By: JULIE FELICE
HQ OPS Officer: RICH LAURA
Notification Date: 09/15/2003
Notification Time: 18:25 [ET]
Event Date: 09/15/2003
Event Time: 15:52 [MDT]
Last Update Date: 09/15/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
ANTHONY GODY (R4)
PATRICIA HOLAHAN (NMSS)

Event Text

UTAH AGREEMENT STATE REPORT ON MEDICAL EVENT

"A patient was administered 15 millicuries of I-131 sodium iodide rather than 4 millicuries for a post-ablation scan. The administrative dosage differed from the prescribed dosage by more than 20% of the prescribed dosage."

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Power Reactor Event Number: 40164
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: WILLIAM WOODBURY
HQ OPS Officer: RICH LAURA
Notification Date: 09/16/2003
Notification Time: 23:17 [ET]
Event Date: 09/16/2003
Event Time: 22:40 [EDT]
Last Update Date: 09/18/2003
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
ANNE BOLAND (R2)
JOSE CALVO (NRR)
RICHARD WESSMAN (IRO)
GENE CANUPP (FEMA)
TOM SAREERAM (DHS)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 94 Power Operation 94 Power Operation
2 N Y 96 Power Operation 96 Power Operation

Event Text

UNUSUAL EVENT AT BRUNSWICK DUE TO HURRICANE WARNING

"Hurricane warning issued. There is no significant impact to the safety of the plant at this time. The plant area is not currently experiencing any unusual winds. Unit 1 is at 94% and Unit 2 is at 96% power."

The wind speed at the site is 14 miles per hour at the time of this report.

The NRC Resident Inspector was notified by the licensee.

* * * UPDATE ON 09/18/03 AT 1753 EDT FROM FRANK RAMPERSAD TO NATHAN SANFILIPPO * * *

Brunswick has terminated the Unusual Event at 1740 EDT. This is based upon the hurricane warning being lifted.

The licensee has notified the NRC Resident Inspector.

Notified Wessman (DIRO), Boland (R2DO), FEMA (C. Bagwell), DHS (C. Wilson), Calvo (NRR EO).

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 40165
Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: RANDALL CADE
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/17/2003
Notification Time: 10:29 [ET]
Event Date: 09/17/2003
Event Time: 08:43 [CDT]
Last Update Date: 09/19/2003
Emergency Class: ALERT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
ANTHONY GODY (R4)
DAVID SKEEN (NRR)
RICHARD WESSMAN (IRO)
KEN SWEETSER (FEMA)
STUART BAILEY (DOE)
Ms. RAWLS (NRC)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Cold Shutdown 0 Cold Shutdown

Event Text

POST ALERT EMERGENCY DECLARATION BASED ON CALCULATED RCS INVENTORY LOSS

"The plant is currently in Mode 5 for a Refueling outage. Reactor Coolant System (RCS) level was being maintained just below the Reactor Vessel flange, 1012.33 feet, with Shutdown Cooling in service and Shutdown Cooling Purification in service. RCS temperature was 100F. At 0821 a lowering level was noted on the Control Room level indications LI-119 and LI-197. At 0824 Shutdown Cooling Purification was secured and the lowering level was stopped with an indicated RCS level 1010.33 feet. At 0843 it was determined that approximately 1350 gallons of RCS water was lost over the 3 minutes that the event lasted. It was determined that during that time conditions existed to enter EAL 1.4, RCS leak greater than 40 gpm. At no time was Shutdown Cooling lost and RCS temperature remained at 100F. At 0825 Abnormal Operating Procedure (AOP-19) was entered. Makeup to the RCS was initiated immediately and level was completely restored at 0842 with charging pumps secured. It has not been determined at this time where the inventory went. A walkdown of the Containment and Auxiliary Building has been completed.

"At this time the plant is stable with an RCS level on 1012.5 feet."

The licensee is conducting an investigation and will provide an update to this report. The licensee informed both the State of NE and IA and the NRC Resident Inspector.

* * * UPDATE AT 1109 EDTR ON 09/19/03 FROM ERICK MATZKE TO S. SANDIN * * *

The licensee is retracting this report based on the following:

"On September 17, 2003, the Fort Calhoun Station notified the NRC that conditions had existed, for about 3 minutes, to make an alert notification. No alert was declared as the time the station was in the condition was such, a limited time. The condition that required the notification was a reactor coolant system (RCS) leak of >40 GPM. The event occurred as follows:

"At approximately 0821 on September 17, 2003, Operations noted decreasing level in the reactor vessel. This was indicated on both of the shutdown RCS level indicators. Due to the uncontrolled (indicated) reduction in RCS level, AOP-19 was entered. Within minutes, the indicated level had dropped from 1012' 6" to 1010' 3". Shutdown cooling purification was isolated. The two (2) charging pumps running for shutdown purification were left in operation. After a few minutes, the charging pump's 80 gpm flow caused the RCS level to stop dropping and RCS level began to rise. During and immediately following this event, numerous walkdowns of containment and the auxiliary building were performed that ensured there was no loss of water from the RCS. No coolant leakage was noted during the walkdowns.

"The cause of the level change was small pressure in the head making the indication read higher than actual. Disconnecting the HJTC clamp allowed a positive vent which caused indicated level to fall. When interviewing the craft performing the work on the HJTC, it was noted that when removing the clamp front a HJTC, the craft noticed a small amount of water bubbling on the HJTC and when an attempt was made to lift the HJTC hub, air was heard in the vicinity of the HJTC. Additionally the craft stated there was some resistance felt from the HTJC when attempting removal. The craft then contacted radiation protection to determine what personnel protection was required. On the second attempt to lift the hub, the craft heard air flow in the vicinity again. When the clamp was finally lifted there was little resistance. It is suspected that the air at the HJTC was due to a pressure differential between the vessel and the containment atmosphere. The higher pressure in the reactor vessel caused level indications to read higher than actual level by approximately 2 feet. When the HJTC flange opened, the change in pressure caused a redistribution of water levels in the RCS. This caused the indicated RCS level change.

"There was never a leak of RCS coolant outside of the RCS. Therefore, this event notification is being retracted."

The licensee informed the NRC Resident Inspector. Notified R4DO(Gody).

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Power Reactor Event Number: 40166
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: PHIL SANTINI
HQ OPS Officer: NATHAN SANFILIPPO
Notification Date: 09/17/2003
Notification Time: 17:44 [ET]
Event Date: 09/17/2003
Event Time: 17:35 [EDT]
Last Update Date: 09/17/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
Person (Organization):
HAROLD GRAY (R1)
JOSE CALVO (NRR)

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

HURRICANE FORCE WINDS WITHIN 500 NAUTICAL MILES OF PLANT

The Indian Point Unit 2 Technical Specification 3.14.A requires prompt notification of the NRC when hurricane force winds are within 500 nautical miles of the plant. Indian Point will continue to monitor the situation and update as necessary.

The licensee has notified the NRC Resident Inspector.


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Power Reactor Event Number: 40168
Facility: SURRY
Region: 2 State: VA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: TERRY HUFF
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/18/2003
Notification Time: 09:16 [ET]
Event Date: 09/18/2003
Event Time: 09:00 [EDT]
Last Update Date: 09/18/2003
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
ANNE BOLAND (R2)
JOSE CALVO (NRR)
RICHARD WESSMAN (IRO)
JIM DUNKER (FEMA)
THOMAS YATES (DHS)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 75 Power Operation 0 Hot Shutdown
2 M/R Y 100 Power Operation 0 Hot Shutdown

Event Text

UNUSUAL EVENT DECLARED DUE TO EXPECTED SEVERE WEATHER

At 0900 EDT the licensee declared an Unusual Event as a precautionary measure due to expected severe weather from hurricane Isabel. Current wind speed and direction is 10-15 mph sustained with gusting to 20 mph from the NNE direction. No additional staff other than those for the planned outage have been brought onsite.

The licensee informed state/local agencies and the NRC Resident Inspector.

* * * * UPDATE 1608 ET FROM T. HUFF TO M. RIPLEY * * * *

As of 1600 ET, Surry Unit 1 commenced a power reduction of 200 mwe (100% to approximately 75% power) in anticipation of grid instabilities due to heavy weather. One of eight circ water screens is degraded due to river debris and its associated circulating water pump has been secured. On-site meteorological panels are out of service. Additionally, the Emergency Operating Facility (EOF) is out of service due to a loss of power.

Notified R2DO (A. Boland).

* * * UPDATE 2101 EDT FROM DUANE SHEPHEARD TO NATHAN SANFILIPPO * * *

The following was received via fax from the licensee:

"With Surry Power Station Unit 1 at approximately 75% reactor power and Unit 2 at 100% reactor power, a manual reactor trip was initiated on Unit 1 at 1728 and on Unit 2 at 1732, due to the loss of the '1G' and `2G' buses which supply power to all eight circulating water pumps for both units. The loss of the buses occurred during high winds and rain associated with Hurricane Isabel, although no hurricane force winds were onsite prior to or at the time of the event. A discretionary Notification of Unusual Event had been declared earlier at 0900 due to the severe weather.

"On Unit 1, the 'B' inadequate core cooling monitor (ICCM) failed. The 'A' ICCM remained operable throughout. All control rods fully inserted and the shutdown margin for Unit 1 was determined to be satisfactory. On Unit 2, eight rod position indicators showed greater than 10 steps but less than 20 steps following the reactor trip. Emergency boration was initiated. All Unit 2 IRPIs [Individual Rod Position Indications] are currently indicating less than five steps and the shutdown margin was satisfactory.

"Auxiliary feedwater automatically initiated as designed for both units on low low steam generator level following the trip. Primary RCS temperature decreased to approximately 543 and 538 degrees on Unit 1 and 2 respectively and was stabilized at 547 degrees.

"No primary safety or relief valves were actuated during the event on either unit. As a result of the loss of the circulating water pumps, the emergency service water pumps were started to conserve intake canal level. After start, 2 out of the 3 emergency service water pumps tripped on high water temperature. The pumps were checked and restarted 14 minutes later. Also due to the need to conserve intake canal level, the main steam trip valves on both units were closed and primary temperature is being maintained by use of the secondary power operated relief valves. No indication of primary to secondary leakage exists on either unit, therefore no adverse radiological consequences resulted from this event.

"Both units are currently stable at hot shutdown. At 1845, the 2G bus was energized and circulating water pumps were started. The emergency service water pumps were secured and are in standby.

"This 4 hour and 8 hour report is being made for Surry Units 1 and 2 in accordance with 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A)."

Notified R2DO (A. Boland), NRR EO (J. Calvo), DIRO (R. Wessman), FEMA (Chuck Bagwell), DHS (Colleen Wilson).

* * *UPDATE AT 1948 EDT ON 9/19/03 FROM BILL SUMMERS TO E. THOMAS* * *

The licensee terminated their unusual event due to the following conditions:
- severe weather has left the area
- both units are stable at hot shutdown on offsite power
- 2 of 3 ESW pumps are operable, and the third ESW pump is being prepared for an operational test
- 45 of 67 sirens remain inoperable, but the sirens will be restored when power to the grid is restored

The licensee will notify the NRC Senior Resident Inspector, as well as state and local officials

Notified R2DO (Boland), NRR EO (Calvo), DIRO (McGinty), FEMA (M. Eaches), DHS (D. Licastro)

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Power Reactor Event Number: 40170
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: JOHN CAVES
HQ OPS Officer: NATHAN SANFILIPPO
Notification Date: 09/18/2003
Notification Time: 15:43 [ET]
Event Date: 09/18/2003
Event Time: 14:33 [EDT]
Last Update Date: 09/19/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
ANNE BOLAND (R2)

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

LOSS OF MORE THAN 20% OF OFFSITE EMERGENCY SIRENS

The following was received via fax from the licensee:

"As of 2:33 PM EDT, more than 20% of the offsite emergency sirens were inoperable for greater than one hour due to loss of power caused by Hurricane Isabel. Currently 27 of 81 sirens are out of service. The State of North Carolina and all four counties within the 10-mile emergency planning zone were notified and are in stand-by to implement mobile route alerting if needed. At this time, Harris cannot estimate the time of siren recovery. This requires an 8-hour non-emergency notification per 10CFR 50.72(b)(3)(xiii) due to the loss of a significant portion of the offsite notification system. The NRC Senior Resident Inspector was informed."

* * * UPDATE 0910 EDT ON 9/19/03 FROM JOHN CAVES TO S. SANDIN * * *

The licensee is updating this report to include that less than 20% of the emergency sirens are inoperable as of 2000 hours 9/18/03.

The licensee informed the NRC Resident Inspector. Notified R2DO(Boland).

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Power Reactor Event Number: 40171
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: BOB FRANSSEN
HQ OPS Officer: MIKE RIPLEY
Notification Date: 09/18/2003
Notification Time: 22:08 [ET]
Event Date: 09/18/2003
Event Time: 20:00 [EDT]
Last Update Date: 09/19/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
HAROLD GRAY (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Cold Shutdown 0 Cold Shutdown
3 N N 0 Refueling 0 Refueling

Event Text

LOSS OF 27 OF 97 EMERGENCY SIRENS DUE TO STORM

"Peach Bottom has been notified that 27 of 97 emergency sirens are out of service as a result of storm conditions. 15 of the sirens are located in southern Lancaster County. The other 12 sirens are located throughout York, Harford, and Cecil Counties.

"The individual counties have been notified of the out of service conditions."

The licensee has notified the NRC Resident Inspector and will be notifying State agencies.

* * * UPDATE 0303 EDT ON 9/19/03 FROM BOB FRANSSEN TO S. SANDIN * * *

Due to adverse weather conditions, the number of emergency sirens out of service has risen to 80. The affected counties and PEMA have been notified.

The licensee will inform the NRC Resident Inspector. Notified R1DO(Gray).

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Power Reactor Event Number: 40172
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: TOM FOWLER
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/19/2003
Notification Time: 00:37 [ET]
Event Date: 09/18/2003
Event Time: 21:11 [EDT]
Last Update Date: 09/20/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
HAROLD GRAY (R1)

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

Event Text

LOSS OF EMERGENCY SIREN CAPABILITY DUE TO ADVERSE WEATHER CONDITIONS

"Due to the effects of severe weather related to Hurricane Isabel, local power outages have resulted in an excessive number of sirens within the Salem/Hope Creek 10-mile Emergency Protection Zone (EPZ) being unavailable. At 21:11 on September 18, 2003, 29 offsite sirens were unavailable (22 in Delaware and 7 located in New Jersey). As of 22:11, some sirens have been restored, but there are still 14 unavailable in Delaware and 7 unavailable in New Jersey. It is likely that the functionality of the EPZ sirens will continue to change due to the ongoing severe weather. Sirens will be recovered when power is restored.

"This notification is being for both Salem Generating Station and Hope Creek Generating Station pursuant to 10CFR50.72(b)(3)(xiii) as a major loss of emergency assessment, offsite response, or communication capability. Salem Units 1 and 2 are operating at 100% power with all safety related equipment operable.

"Hope Creek is operating at 94% power with all safety related equipment operable. Power is reduced due to the degraded performance of the non-safety related ventilation system that cools the Reactor Recirculation Pump Motor-Generator Sets."

The licensee informed the NRC Resident Inspector.

* * * UPDATEON 09/20/03 @ 1000 BY KOPCHICK TO GOULD * * *

"There are currently 11 unavailable sirens within the Salem/Hope Creek 10-mile Emergency Preparedness Zone (EPZ) (6 in New Jersey and 5 in Delaware). The current availability of sirens no longer constitutes a major loss of emergency assessment capability, offsite response capability, or offsite communication capability pursuant to 10C'FR50.72(b)(3)(xiii). It is anticipated that all sirens will be rendered available as power is restored and storm recovery actions are completed. No further updates to this event report will be provided."

The NRC Resident Inspector was informed.

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Power Reactor Event Number: 40173
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DON E. ROLAND
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/19/2003
Notification Time: 01:07 [ET]
Event Date: 08/29/2003
Event Time: 10:25 [EDT]
Last Update Date: 09/19/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
HAROLD GRAY (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

INVALID ACTUATION OF CONTAINMENT ISOLATION VALVES

"On August 29th, 2003 at approximately 1025 EDT, an electrical perturbation affecting both Unit 1 & 2 at PPL Susquehanna LLC resulted in a partial isolation of Primary Containment Isolation valves on Division 1, specifically A & B Containment Radiation Monitors and the Containment Instrument Gas Purge supply valve.

"This event is being reported as an invalid system actuation and is reportable under 10CFR 50.73(a)(2)(iv)(A). The condition meets the criteria of 10CFR 50.73(a)(2)(iv)(B)(2) due to a general containment isolation signal that affected containment isolation valves in more than one system. This notification is being provided via 60 day optional phone call as permitted under 10CFR 50.73(a)(1) in lieu of a written LER.

"The event was initiated when Operators were returning a Unit 1 13.8 KV Non-ESS breaker back in service following routine maintenance. When the breaker was restored to its closed position, a fault downstream of the breaker caused it to immediately re-open. The 13.8 Kv system supplies power to both unit's Division 14kV ESS busses. The perturbation was sufficient to cause several 'fail closed' containment isolation valves to actuate and close. The transient caused other non-safety related plant equipment to trip/auto-start, no other safety-related equipment or functions were lost. There also were no challenges to the reactor systems or containments. All plant equipment and/or systems were capable of being restored to their original alignment. The fault that caused the electrical perturbation originated at a non-ESS transformer and is currently being replaced."

The licensee will inform the NRC Resident Inspector.

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Power Reactor Event Number: 40174
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: JIM WILSON
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/19/2003
Notification Time: 01:22 [ET]
Event Date: 09/19/2003
Event Time: 01:20 [EDT]
Last Update Date: 09/19/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
Person (Organization):
HAROLD GRAY (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Cold Shutdown 0 Cold Shutdown
3 N N 0 Refueling 0 Refueling

Event Text

SECURITY REPORT INVOLVING LIMITED SUSPENSION OF ICMS

The licensee is implementing a limited suspension of Interim Compensatory Measures (ICMs) due to high sustained winds.

The licensee will inform the NRC Resident Inspector. Contact the Headquarters Operations Officer for additional details.

* * * UPDATE 0455 EDT ON 9/19/03 FROM JIM WILSON TO S. SANDIN * * *

The licensee has reimplemented all ICMs due to abatement of the adverse weather conditions. The licensee will inform the NRC Resident Inspector. Notified R1DO(Gray).

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Power Reactor Event Number: 40175
Facility: CALVERT CLIFFS
Region: 1 State: MD
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: AL KELLY
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/19/2003
Notification Time: 01:41 [ET]
Event Date: 09/18/2003
Event Time: 21:05 [EDT]
Last Update Date: 09/19/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
HAROLD GRAY (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

LOSS OF EMERGENCY SIREN CAPABILITY DUE TO ADVERSE WEATHER CONDITIONS

A significant portion of emergency sirens (43 of 72) located in Calvert, St. Mary's and Dorchester county are unavailable due to a loss of power. Restoration is not expected until dayshift when the effects of Tropical Storm Isabel have abated.

The licensee informed the NRC Resident Inspector.

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Power Reactor Event Number: 40176
Facility: LIMERICK
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GARY SCHIENDELMAN
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/19/2003
Notification Time: 04:16 [ET]
Event Date: 09/19/2003
Event Time: 04:00 [EDT]
Last Update Date: 09/19/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
HAROLD GRAY (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

LOSS OF EMERGENCY SIREN CAPABILITY DUE TO ADVERSE WEATHER CONDITIONS

"32 of 165 offsite sirens not functioning due to loss of power/equipment failure because of ongoing storm."

The licensee will inform the affected counties/PEMA and the NRC Resident Inspector.

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Power Reactor Event Number: 40177
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [3] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: BOB FRANSSEN
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/19/2003
Notification Time: 04:55 [ET]
Event Date: 09/19/2003
Event Time: 01:45 [EDT]
Last Update Date: 09/19/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
HAROLD GRAY (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Cold Shutdown 0 Cold Shutdown
3 N N 0 Refueling 0 Refueling

Event Text

LOSS OF POWER TO THE TECHNICAL SUPPORT CENTER

"Peach Bottom lost power to the TSC from 0145 to 0255 this morning due to a temporary loss of the Station Blackout Line (SBO). The SBO line, and subsequently power to the TSC, has been restored. The station meteorological data was lost due to the initial power loss with the SBO at 0145. The meteorological data remains out of service at this time.

"Contingency plans exist for the use of an alternate TSC, if required. Use of data from local and national weather services is available in place of the station meteorological data.

"Additionally, Peach Bottom has notified the FAA that power has been lost to the flashing lights at the top of high voltage towers in the river."

The licensee informed the NRC Resident Inspector.

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Power Reactor Event Number: 40178
Facility: THREE MILE ISLAND
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP
NRC Notified By: JOHN SCHORK
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/19/2003
Notification Time: 05:23 [ET]
Event Date: 09/19/2003
Event Time: 02:24 [EDT]
Last Update Date: 09/19/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
HAROLD GRAY (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 10 Power Operation

Event Text

LOSS OF EMERGENCY SIREN CAPABILITY DUE TO ADVERSE WEATHER CONDITIONS

"TMI is notifying the NRC Operations Center in accordance with 10 CFR 50.72 (b)(2)(xi), Notification of Other Government Agency and 10 CFR 50.72 (b)(3)(xiii) Major Loss of Emergency Preparedness Capabilities. At 0224 AM on Friday, September 19 it was determined that 25 of 79 of the public emergency sirens for Three Mile Island Unit 1 were inoperable due to loss of power due to Tropical Storm Isabel. Subsequently, it has been determined that 32 of 79 of the sirens are inoperable. The inoperable sirens are located throughout the five risk counties around TMI. The inoperability of the sirens around TMI impacts a large segment of the population.

"Contingency actions have been established for the deficient sirens. Automatic route alerting, that is the coordinated use of vehicles that will make loudspeaker announcements throughout affected areas will be utilized if the need should arise prior to restoration of power to the inoperable sirens. Local power company line crews have been notified of the loss of power to the sirens and are working to restore power on a priority basis to the sirens."

The licensee informed the affected counties/PEMA and the NRC Resident Inspector.

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Power Reactor Event Number: 40179
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: T. L. SHELTON
HQ OPS Officer: STEVE SANDIN
Notification Date: 09/19/2003
Notification Time: 11:25 [ET]
Event Date: 09/19/2003
Event Time: 09:30 [EDT]
Last Update Date: 09/19/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
ANNE BOLAND (R2)

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 62 Power Operation 62 Power Operation

Event Text

LOSS OF EMERGENCY SIREN CAPABILITY TO THE ADVERSE WEATHER CONDITIONS

"At 0930 on September 19, 2003 it was identified that there was a major loss of offsite response capability. 43 out of 63 early warning sirens were determined inoperable due to loss of power as a result of Hurricane Isabel.

"The State and NRC Resident Inspector will be notified of this event."

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Power Reactor Event Number: 40181
Facility: SURRY
Region: 2 State: VA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DUANE SHEPHEARD
HQ OPS Officer: ERIC THOMAS
Notification Date: 09/19/2003
Notification Time: 15:45 [ET]
Event Date: 09/19/2003
Event Time: 11:30 [EDT]
Last Update Date: 09/19/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
ANNE BOLAND (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Hot Shutdown 0 Hot Shutdown
2 N N 0 0

Event Text

LOSS OF SIRENS

"A poll of the Surry EWS sirens was conducted to determine operability of the siren system (Reference Hurricane Response Plan - Nuclear, Section 5.6). The poll was conducted from the back-up status logger at Innsbrook due to the unavailability of the primary status logger in the Surry LEOF (see Plant Issue - S-2003-4152).

"45 of the 67 sirens expected to respond to the siren polling are considered inoperable at this time due to power failure as a result of Hurricane Isabel (the status of 2 of these was indeterminate). 22 of the 67 sirens responded satisfactorily and are considered operational.

"This is a reportable event per VPAP - 2802 Attachment 3 d. Early Warning System second bullet "More than 25 percent of all sirens are unavailable" and the third bullet "The capability to alert a large segment of the population does not exist."

This discrepancy was discovered at 1130 EDT on 9/19/03.

The licensee notified the NRC Resident Inspector, as well as state and local government officials.

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Power Reactor Event Number: 40182
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: ART FITCH
HQ OPS Officer: MIKE RIPLEY
Notification Date: 09/19/2003
Notification Time: 17:54 [ET]
Event Date: 09/19/2003
Event Time: 16:00 [EDT]
Last Update Date: 09/19/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
HAROLD GRAY (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

LOSS OF EMERGENCY SIRENS DUE TO STORM

"At approximately 1535 [ET] on 9/19/03 the Susquehanna Control Room was notified that the 7.2 Kv supply line to the Tank Mountain repeater for activation of all emergency sirens was unavailable [approximately 121 sirens in Lucerne and Columbia Counties]. The backup batteries for the repeater were reported to be supplying power for repeater activation. Following further discussion with Emergency Planning personnel, Susquehanna LLC could not determine how long the battery supply would be available. At 1600 the ability to activate the emergency sirens was declared inoperable due to the inability to determine the status of the power source. Loss of ability to activate the emergency sirens is reportable under 10CFR50.72(b)(3)(xiii), Loss of Emergency Preparedness Capabilities, as an eight hour notification. The Susquehanna LLC Emergency Plan incorporates alternate means, i.e. Route Alert Teams, to notify the public during an emergency situation."

The licensee notified the NRC Resident Inspector and will be notifying State and local agencies.

* * * * UPDATE FROM R. FRY TO M. RIPLEY 2105 ET 09/19/03 * * * *

"As of 2010 hours [ET] on 9/19/2003, power was restored to the repeater that is used for emergency siren activation and the emergency sirens are considered operable. The NRC resident inspector has been updated."

The licensee will be notifying State and local agencies. Informed R1DO (H. Gray)

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Power Reactor Event Number: 40183
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: DAVID MANKIN
HQ OPS Officer: ERIC THOMAS
Notification Date: 09/19/2003
Notification Time: 20:11 [ET]
Event Date: 09/19/2003
Event Time: [CDT]
Last Update Date: 09/19/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
ROGER LANKSBURY (R3)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 93 Power Operation 93 Power Operation

Event Text

OFFSITE NOTIFICATION

The licensee notified the Iowa Department of Natural Resources, Linn County Sheriff, and the U.S. Coast Guard National Response Center of a reportable spill of fuel oil into the Cedar River per applicable reporting procedures. Dredging operations were underway, and while refueling dredging equipment located on a barge in the Cedar River, approximately one gallon of fuel oil was spilled into the Cedar river.

The licensee notified the NRC Resident Inspector, and will notify the state and local authorities.

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Power Reactor Event Number: 40184
Facility: GINNA
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: MIKE MICKLOW
HQ OPS Officer: ERIC THOMAS
Notification Date: 09/19/2003
Notification Time: 20:49 [ET]
Event Date: 09/19/2003
Event Time: 18:00 [EDT]
Last Update Date: 09/19/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
HAROLD GRAY (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Cold Shutdown 0 Cold Shutdown

Event Text

UNANALYZED CONDITION

While shutdown in Mode 5, containment recirculation sump 'B' was inspected for sump screen bypass flow paths in accordance with the requirements of NRC Bulletin 2003-01. Inspection results showed that approximately 25 square inches of space is available for recirculation flow to bypass the sump screens. This condition has the possibility of affecting the containment spray, safety injection and residual heat removal systems. The plant is stable in a refueling outage at approximately 95 degrees F, with normal residual heat removal in service and loop levels at 72 inches.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 40185
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: ART BREADY
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 09/20/2003
Notification Time: 00:18 [ET]
Event Date: 09/19/2003
Event Time: 20:41 [EDT]
Last Update Date: 09/20/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
HAROLD GRAY (R1)
JOSE CALVO (NRR)
AL AUSTIN (FEMA)
BOB TURNER (DOE)
LEN POPE (DHS)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 100 Power Operation 0 Hot Shutdown

Event Text

PLANT HAD AUTO REACTOR SCRAM FROM 100% POWER DUE TO LOW REACTOR WATER LEVEL AS RESULT OF A PARTIAL LOSS OF OFFSITE POWER

"At 2041 hrs on 09/19/03, an electrical fault on 500 KV Bus Section 2 caused a Group A Transformer lockout. The Alpha and Charlie 4.16 KV vital busses did not transfer to their respective alternate infeeds from Group B Transformers, the associated Emergency Diesel Generators auto-started to supply their respective busses, and the associated Loss of Power sequencers initiated. This automatic electrical transfer caused a loss of the Alpha and Charlie Reactor Feedpumps due to a low hydraulic oil pressure signal, and Reactor level decreased to the low level RPS scram setpoint of 12.5 inches. All rods fully inserted in response to the RPS scram signal. Reactor water level dropped to approx. minus 25 inches and was subsequently returned to a normal level of 34 inches post-scram by the Bravo Reactor Feedpump. In addition, 7.2 KV Bus 10A110 failed to transfer to its alternate infeed breaker, and de-energized causing a loss of the Alpha and Delta Turbine Building Chillers, 00K107 Station Air Compressor, Alpha Primary Condensate Pump, Alpha Secondary Condensate Pump, and the Alpha Reactor Recirc Pump. The Alpha Fuel Pool Cooling and Cleanup Pump tripped during the electrical transient, and was subsequently restarted. The Alpha and Bravo Reactor Water Cleanup Pumps tripped during the electrical transient, and preparations are being made to restart the system. Core circulation is being supplied by the Bravo Reactor Recirc Pump. Reactor Pressure is being controlled by Turbine Bypass valves to the Main Condenser, and Reactor Pressure is 762 PSIG. Electrical Distribution personnel are inspecting Switchyard electrical components and relaying to determine the exact location and nature of the fault. Hope Creek-Salem 500 KV 5037 500 KV line has been isolated as a result of visual reports of arcing/tracking, and is considered a potential cause of the electrical transient. Forced outage team personnel have been assembled to review the event and develop a recovery plan. This event is being reported IAW 10CFR50.72(b)(2)(iv)(B) for the actuation of RPS on a low reactor water level signal and 10CFR50.72(b)(3)(iv)(A) due to the Emergency Diesel Generators start and sequencer initiation,"

Two (A&C) of four Emergency Diesels started and loaded to their busses. The B&D Emergency Diesels are available. The plant has two offsite power sources available, but only one is feeding the B&D vital busses.


The NRC Resident Inspector was notified.

* * * UPDATE ON 9/20/03 AT 1948 FROM A. BREADY TO E. THOMAS * * *

"Salem Unit 1, Unit 2, and Hope Creek Shut Down.

"After riding out Hurricane Isabel and supplying power to the PJM grid, Salem Units 1 and 2, and Hope Creek were shut down over the weekend due to salting in the switchyard.

"High winds and rough surf in the Delaware River resulted in salt deposits in the 500 KV switchyards at Salem and Hope Creek. These deposits caused electrical faults and arcing in both switchyards. Hope Creek automatically shut down on Friday at 8:41 p.m. due to problems initiated by the switchyard. Salem Unit 1 and Unit 2 were manually taken off line Saturday morning at 3:44 a.m. and 4:37 a.m. respectively.

"A team has been assembled to investigate the cause of the events. All three units will remain shutdown while the switchyards are cleaned and any necessary repairs are made. The cleaning of the salt from the switchyards has already begun."

Notified R1DO (H. Gray), NRR EO (J. Calvo), and DIRO (T. McGinty)

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Other Nuclear Material Event Number: 40186
Rep Org: GEOTEST
Licensee: GEOTEST
Region: 3
City: ST LOUIS State: MO
County:
License #: 24-26550-01
Agreement: N
Docket:
NRC Notified By: RICH EVANS
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 09/20/2003
Notification Time: 08:16 [ET]
Event Date: 09/18/2003
Event Time: [CDT]
Last Update Date: 09/22/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
ROGER LANKSBURY (R3)
C.W. (BILL) REAMER (NMSS)

Event Text

MISSING TROXLER GAUGE

The licensee has not been able to locate their technician who has had a Troxler gauge in his possession since the evening of 09/18/03. The missing gauge is a Troxler 3440 serial #24340 containing 8 millicuries Cs-137 and 40 millicuries Am-241/Be. The licensee has been unsuccessful in contact the technician at his various addresses. A police report was made with the Brentwood, MO Police Dept.

* * * UPDATE ON 09/22/03 @ 06:57 BY EVANS TO GOULD * * *

The gauge was found at one of the technician's residences on 09/20/03. It was intact and not damaged. The technician is still missing.

Notified Reg 3 RDO(Lanksbury) and NMSS(Reamer)

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Power Reactor Event Number: 40187
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: KOPCHICK
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 09/20/2003
Notification Time: 11:56 [ET]
Event Date: 09/20/2003
Event Time: 10:45 [EDT]
Last Update Date: 09/20/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
HAROLD GRAY (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Hot Shutdown 0 Hot Shutdown

Event Text

BOTH HOPE CREEK AND SALEM LOST ALL METEOROLOGICAL CAPABILITY

This notification is for both Hope Creek and Salem stations pursuant to 10CFR50.72(b)(3)(xiii) as a major loss of emergency assessment capability, offsite response capability, or offsite communication capability; specifically, the loss of all meteorological data for Hope Creek and Salem stations. Meteorological data is supplied to both stations via a common communications lank. Data is transmitted to Hope Creek then relayed to Salem. The problem in the communication link has been isolated to a faulty computer, which supplies Hope Creek with data. Troubleshooting and repairs are in progress; a projected availability time is not yet available.

The NRC Resident Inspector was notified.

Page Last Reviewed/Updated Friday, March 30, 2012
Friday, March 30, 2012