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Event Notification Report for August 11, 2008

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
08/08/2008 - 08/11/2008

** EVENT NUMBERS **

Power Reactor	Event Number: 44384
Facility: BYRON Region: 3 State: IL Unit: [1] [ ] [ ] RX Type: [1] W-4-LP,[2] W-4-LP NRC Notified By: STEVE GODBY HQ OPS Officer: DONALD NORWOOD	Notification Date: 08/04/2008 Notification Time: 22:00 [ET] Event Date: 08/04/2008 Event Time: 18:45 [CDT] Last Update Date: 08/08/2008
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE	Person (Organization): DAVID HILLS (R3)

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

Event Text

LOSS OF 84 OF 94 EMERGENCY SIRENS DUE TO INCLEMENT WEATHER

"At approximately 1830, a severe thunderstorm moved through Ogle County. At 1845, 84 of 94 emergency sirens for Byron Station became inoperable. There is currently no estimated time of repair due to the severe number of power outages."

Sirens affected provide coverage for Ogle County (population ~52,000) and a small portion of Winnebago County (population ~296,000). These are utility owned sirens. These sirens are not shared with other sites. In the event of a need for the sirens, a contingency plan using a "route alert" by the state will be implemented.

There are no off-site power or grid concerns.

The NRC Resident Inspector was notified by the licensee. No other state or local government agencies have been notified by the licensee.

* * * UPDATE ON 8/5/08 AT 0321 FROM GODBY TO SNYDER * * *

Troubleshooting and restoration activities continue for the emergency sirens. Presently 73 of 94 sirens remain inoperable.

Notified R3DO (Hills).

* * * UPDATE AT 0645 ON 8/5/2008 FROM STEVE GODBY TO MARK ABRAMOVITZ * * *

At this time, 44 of the sirens are still inoperable. The licensee estimates that all sirens will be operable by 1800 CDT today.

The licensee will notify the NRC Resident Inspector.

Notified the R3DO (Hills).

* * * UPDATE AT 0902 EDT ON 8/5/2008 FROM GREG BALESTRIERI TO MARK ABRAMOVITZ * * *

At 0755 CDT, 55 sirens were inoperable. The licensee will notify the NRC Resident Inspector.

Notified the R3DO (Hills).

* * * UPDATE AT 1258 EDT ON 8/5/2008 FROM GREG BALESTRIERI TO S. SANDIN * * *

At 1155 CDT, 48 sirens were inoperable. The licensee notified the NRC Resident Inspector.

Notified the R3DO (Hills).

* * * UPDATE AT 1713 EDT ON 8/5/2008 FROM GREG BALESTRIERI TO S. SANDIN * * *

At 1500 CDT, 46 sirens were inoperable. The licensee notified the NRC Resident Inspector.

Notified the R3DO (Hills).

* * * UPDATE AT 1933 EDT ON 8/5/2008 FROM JIM LYNDE TO S. SANDIN * * *

Six (6) more sirens have been returned to service. Forty (40) sirens remain inoperable. The licensee notified the NRC Resident Inspector.

Notified the R3DO (Hills).

* * * UPDATE AT 2255 EDT ON 8/5/2008 FROM JIM LYNDE TO J. KOZAL * * *

Seven (7) more sirens have been returned to service. Thirty-three (33) sirens remain inoperable. The licensee notified the NRC Resident Inspector.

Notified the R3DO (Hills).

* * * UPDATE AT 0757 EDT ON 8/6/2008 FROM MARTY WOLFE TO J. ROTTON * * *

As of 0600 CDT on 08/06/08, four (4) more sirens have been returned to service. Twenty-nine (29) sirens remain inoperable with estimate of greater than 24 hours before restoration. The licensee notified the NRC Resident Inspector.

Notified the R3DO (Hills).

* * * UPDATE AT 2345 ON 8/6/2008 FROM BRIAN HERRING TO MARK ABRAMOVITZ * * *

At 2200 CDT 8/6/2008, 17 sirens are still inoperable. The estimated time to repair the remaining sirens is approximately 24 hour.

The licensee notified the NRC Resident Inspector.

Notified the R3DO (Hills) via e-mail.

* * * UPDATE AT 1542 ON 8/8/2008 FROM MIKE LINBEMANN TO JOHN KNOKE * * *

As of 1432 CDT on 08/08/08 all emergency sirens for Byron Station are operable.

The licensee notified the NRC Resident Inspector. Notified the R3DO (Hills)

Power Reactor	Event Number: 44387
Facility: NINE MILE POINT Region: 1 State: NY Unit: [1] [ ] [ ] RX Type: [1] GE-2,[2] GE-5 NRC Notified By: DON SHEEHAN HQ OPS Officer: MARK ABRAMOVITZ	Notification Date: 08/06/2008 Notification Time: 21:09 [ET] Event Date: 08/06/2008 Event Time: 18:40 [EDT] Last Update Date: 08/08/2008
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE	Person (Organization): MEL 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

Event Text

SAFETY PARAMETER DISPLAY SYSTEM ASSESSMENT LOST

"This 8-hour non-emergency report is being made based upon requirements of 10CFR50.72(b)(3)(xiii) which states, 'The licensee shall notify the NRC as soon as practical and in all cases within eight hours of the occurrence of any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability (e.g., significant portion of control room indication, Emergency Notification System, or offsite notification system)'.

"At 18:40 ET on Wednesday, August 06, 2008, the Reactor Operator At-the-Controls (OATC) discovered that the Safety Parameter Display System (SPDS) Computer Display was not updating data. This was discovered during periodic Control Room panel walkdowns.

"The last data update on the SPDS display was at 20:02 ET on Tuesday, August 05, 2008.

"All other Plant Process Computer functions are available. Information Technology Department personnel will be investigating the cause of the loss of SPDS capability, which is currently unknown.

"No other Control Room emergency assessment capabilities have been adversely affected. All Control Room panel indicators and annunciators are responding properly."

The licensee notified the NRC Resident Inspector.

* * * UPDATE AT 0935 ON 08/08/08 FROM BRIAN FINCH TO JEFF ROTTON * * *

"On Wednesday, August 06, 2008 at 2151 EDT, the Plant Process Computer (PPC) was shutdown and successfully restarted at 2318 EDT. Upon restart, SPDS was verified operable."

The licensee notified the NRC Resident Inspector.

Notified R1DO (Krohn).

Research Reactor	Event Number: 44396
Facility: ARMED FORCES RADIOBIOLOGY RSCH INST RX Type: 1100 KW TRIGA MARK-F Comments: Region: 1 City: BETHESDA State: MD County: MONTGOMERY License #: R-84 Agreement: Y Docket: 05000170 NRC Notified By: STEVE MILLER HQ OPS Officer: BILL HUFFMAN	Notification Date: 08/08/2008 Notification Time: 09:57 [ET] Event Date: 07/29/2008 Event Time: 10:13 [EDT] Last Update Date: 08/08/2008
Emergency Class: NON EMERGENCY 10 CFR Section: NON-POWER REACTOR EVENT	Person (Organization): ALEXANDER ADAMS (NRR)

Event Text

TECHNICAL SPECIFICATION VIOLATION - LOW POWER OPERATION WITHOUT GAS STACK MONITOR IN SERVICE

Technical Specification 3.5.1 requires that the Gas Stack Radiation Monitor be in service when the AFRRI reactor is at power. Based upon a licensee review of the operations log book on August 5, the licensee discovered that the reactor had operated at a low power level for a short duration while the Gas Stack Monitor was out of service. Specifically, a K-excess calculation was conducted at 10:13 EDT on 7/29/08 at a power level of 5 watts. While this activity was in progress, the Gas Stack Rad Monitor was inoperable for maintenance reasons and had not been verified to be in service as required by technical specifications and procedures. The K-excess calculation was completed and the reactor shutdown by 10:17 EDT (duration of TS violation was approximately 4 minutes). The licensee has provided remedial training to facility operators.

The NRC project manager was notified by the licensee.

Power Reactor	Event Number: 44399
Facility: TURKEY POINT Region: 2 State: FL Unit: [ ] [4] [ ] RX Type: [3] W-3-LP,[4] W-3-LP NRC Notified By: MICHEAL COEN HQ OPS Officer: JASON KOZAL	Notification Date: 08/08/2008 Notification Time: 16:01 [ET] Event Date: 08/07/2008 Event Time: 12:30 [EDT] Last Update Date: 08/08/2008
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(ii)(A) - DEGRADED CONDITION	Person (Organization): GEORGE HOPPER (R2)

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

Event Text

DEGRADED PRINCIPAL SAFETY BARRIER

"This is a late non-emergency notification to the NRC Operations Center in accordance with 10 CFR 50.72(b)(3)(ii)(A) due to the degradation of a principal safety barrier.

"A flaw in a weld in a 3/4 inch test connection off the seal water injection line for the 4B reactor coolant pump was identified at approximately 1230 during a containment entry on August 7, 2008. The flaw is leaking at the rate of approximately 0.14 gpm (current total), it [the leak] is isolable, and the leakage is currently considered as unidentified leakage from the reactor coolant system. The Technical Specification limit for unidentified leakage is 1.0 gpm.

"Currently, the leak is being monitored while repair options are evaluated."

The licensee notified the NRC Resident Inspector.

Power Reactor	Event Number: 44400
Facility: BROWNS FERRY Region: 2 State: AL Unit: [1] [ ] [ ] RX Type: [1] GE-4,[2] GE-4,[3] GE-4 NRC Notified By: TIM BOLAND HQ OPS Officer: JASON KOZAL	Notification Date: 08/08/2008 Notification Time: 17:43 [ET] Event Date: 08/08/2008 Event Time: 05:05 [CDT] Last Update Date: 08/08/2008
Emergency Class: NON EMERGENCY 10 CFR Section: OTHER UNSPEC REQMNT	Person (Organization): GEORGE HOPPER (R2)

Unit	SCRAM Code	RX CRIT	Initial PWR	Initial RX Mode	Current PWR	Current RX Mode
1	N	Y	50	Power Operation	0	Hot Shutdown

Event Text

REACTOR SHUTDOWN DUE TO SMALL STEAM LEAK

"This is a Voluntary Notification in accordance with NUREG 1022 Section 2.7 of a controlled shutdown that can be considered to be of Generic Interest to the NRC and is not reportable otherwise per 10CFR50.72 or 10CFR50.73. Operations performed the controlled shutdown of Browns Ferry Unit 1 this morning in order to isolate and repair a small steam leak. The leak was determined to be from a Code Class 2 piping thermo-well located in the Unit 1 Steam Tunnel. The controlled shutdown was uneventful with all systems responding as expected. There was no impact to the health and safety of the public.

"Units 2 and 3 were operating at 50% power when Unit 1 was shutdown and were not affected by this event.

"The Senior NRC Resident Inspector has been notified of this Voluntary Notification."

Power Reactor	Event Number: 44401
Facility: PALO VERDE Region: 4 State: AZ Unit: [1] [2] [3] RX Type: [1] CE,[2] CE,[3] CE NRC Notified By: KENT CHAVET HQ OPS Officer: JOHN KNOKE	Notification Date: 08/08/2008 Notification Time: 20:50 [ET] Event Date: 08/08/2008 Event Time: 15:20 [MST] Last Update Date: 08/08/2008
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(xi) - OFFSITE NOTIFICATION	Person (Organization): MICHAEL SHANNON (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
2	N	Y	100	Power Operation	100	Power Operation
3	N	Y	100	Power Operation	100	Power Operation

Event Text

OFFSITE NOTIFICATION TO MARICOPA COUNTY ENVIRONMENTAL SERVICES

"Arizona Public Service Co. made an offsite notification to Maricopa County Environmental Services at 1520 MST on 8/8/08 to report a loss of power to the Palo Verde Nuclear Generating Station drinking water supply pumps. The pumps were out of service on 8/8/08 between the hours of 0532 and 0620 MST. Full service has been restored."

The licensee notified the NRC Resident Inspector.

Power Reactor	Event Number: 44402
Facility: COOPER Region: 4 State: NE Unit: [1] [ ] [ ] RX Type: [1] GE-4 NRC Notified By: ROY GILES HQ OPS Officer: BILL HUFFMAN	Notification Date: 08/09/2008 Notification Time: 05:24 [ET] Event Date: 08/09/2008 Event Time: 02:04 [CDT] Last Update Date: 08/09/2008
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): MICHAEL SHANNON (R4)

Unit	SCRAM Code	RX CRIT	Initial PWR	Initial RX Mode	Current PWR	Current RX Mode
1	M/R	Y	69	Power Operation	0	Hot Shutdown

Event Text

MANUAL REACTOR SCRAM DUE TO FAILURE OF REHEAT STOP VALVE TO OPEN DURING TURBINE VALVE TESTING

"While performing main turbine reheat stop valve surveillance testing, Reheat Stop Valve 1RV 1A failed to reopen simultaneously with a Moisture Separator C high level alarm. Plant alarm response procedures require a reactor scram in this situation. Operating crew inserted a manual scram at 0204 CDT. Immediately after the scram, RPV level responded as expected and dropped below the Group 2 containment isolation setpoint. All rods inserted fully. RPV level is being controlled with RFP A and the startup valves. RPV pressure is being controlled on the bypass valves. The Group 2 isolation was complete with no anomalies.

"This report is being submitted pursuant to 50.72(b)(2) for RPS actuation (4 hour report) and 50.72(b)(3) for a valid Group 2 isolation (8 hour report)."

The scram was characterized as uncomplicated. The lowest reactor vessel water level reached was - 20 inches. No safeties lifted during the transient and all systems functioned as required. The cause of the reheat stop valve failure to reopen is under investigation.

The NRC Resident Inspector has been notified.

Power Reactor	Event Number: 44404
Facility: HARRIS Region: 2 State: NC Unit: [1] [ ] [ ] RX Type: [1] W-3-LP NRC Notified By: SCOTT FAULKNER HQ OPS Officer: HOWIE CROUCH	Notification Date: 08/11/2008 Notification Time: 04:21 [ET] Event Date: 08/11/2008 Event Time: 00:49 [EDT] Last Update Date: 08/11/2008
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL	Person (Organization): GEORGE HOPPER (R2)

Unit	SCRAM Code	RX CRIT	Initial PWR	Initial RX Mode	Current PWR	Current RX Mode
1	M/R	Y	21	Power Operation	0	Hot Standby

Event Text

MANUAL REACTOR TRIP DUE TO DEGRADING CONDENSER VACUUM

"At 0049 EDT on 8/11/2008, the Harris Nuclear Plant was manually scrammed from 21% power due to indications of degrading condenser vacuum. At the time, a reactor shutdown was in progress with indications of a degraded condenser boot seal. The unit was stabilized in Mode 3 with no additional equipment failures or other complications."

The reactor is currently at normal operating pressure and temperature. The highest vacuum observed was 8". All rods inserted into the core after the manual trip. Auxiliary feed water did not start as a result of the trip. Steam generator level is being maintained via normal feed water flow path. Decay heat is being removed via the steam dumps to atmosphere. There is no known primary to secondary leakage. No power-operated or manual reliefs lifted during the transient. The grid is stable and loads are being supplied via the station start-up transformer.

The licensee has notified the NRC Resident Inspector.