ML073110629

Manual Scram Due to Lowering Intake Level

ML073110629
Person / Time
Site:	FitzPatrick
Issue date:	10/29/2007
From:	- No Known Affiliation
To:	Office of Nuclear Reactor Regulation
References
Download: ML073110629 (3)

Text

Page 6 of 8 NRC Notified By: ROBERT BROCK Last Update Date: 10/26/2007 HQ OPS Officer: JASON KOZAL Emergency Class: NON EMERGENCY Person (Organization):

10 CFR Section: DAVID HILLS (R3) 50.72(b)(3)(v)(D) - ACCIDENT MITIGATION SCRAM Current Unit Code RX CRIT Initial PWR Initial RX Mode PWR Current RX 1 N Y 100 Power Operation 100 Power Ope 2 N Y 100 Power Operation 100 Power Ope Event Text BOTH LOW TEMPERATURE OVERPRESSURE PROTECTION SYSTEMS OUT OF SERVICE "This 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> report is being made pursuant to 10 CFR 50.72(b)(3)(v). On 10/25/2007 at 1930 CDT Point Bea Plant (PBNP) Unit 1 and Unit 2 low temperature overpressure protection systems (LTOP) were declared inope result of the determination that the current LTOP actuation setpoint was non-conservative based on updated calculations. Specifically, "1) The mass input from the Safety Injection Pumps has significantly increased based on the use of a Point B Nuclear Plant specific system flow model.

"2) The setpoint calculation does not consider instrument delay times during (PORV) Pilot Operated Relief Va actuation.

"3) The updated Calculation changes instrument uncertainties.

"LCO 3.4.12 for the LTOP system is not applicable at this time for either unit (both units in Mode 1/100% pow 3.4.12 is only applicable in Mode 5, Mode 6 when the reactor vessel head is on, and Mode 4 when any cold le temperature is at or below the temperature specified in the Pressure Temperature Limits Report (270 deg F).

"Changes to operating procedures to delineate operation of reactor coolant pumps and charging pumps durin temperature conditions are in progress. Implementation of these procedure changes will permit LTOP to be re service."

The licensee stated that this issue was discovered as part of the on going calculation reconstitution initiative plant.

The licensee notified the NRC Resident Inspector.

• *

• UPDATE PROVIDED BY RYAN RODE TO JASON KOZAL AT 2135 ON 10/26/07 * * *

"The following is an update to the 8 hr report made to the NRC via EN#43750:

"On 10/26/07 at 17:51 procedure changes which identify requirements for operation of reactor coolant pump charging pumps during low temperature conditions have been made. These procedures provide the guidance to ensure that the current LTOP setpoints remain conservative. Based on the issuance of these procedures w required guidance, LTOP is returned to service for both Unit-1 and Unit-2."

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

Power Reactor Event Number: 43752 Facility: FITZPATRICK Notification Date: 10/28/2007 Region: 1 State: NY Notification Time: 03:24 [ET]

Unit: [1] [ ] [ ] Event Date: 10/28/2007 RX Type: [1] GE-4 Event Time: 00:59 [EDT]

NRC Notified By: DAVE RICHARDSON Last Update Date: 10/28/2007 HQ OPS Officer: JEFF ROTTON Emergency Class: NON EMERGENCY Person (Organization):

file://c:\temp\CTXH7XGU.htm 11/1/2007

Page 7 of 8 10 CFR Section: JOHN CARUSO (R1) 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION SCRAM Current Unit Code RX CRIT Initial PWR Initial RX Mode PWR Current RX 1 M/R Y 100 Power Operation 0 Hot Shutd Event Text MANUAL SCRAM DUE TO LOWERING INTAKE LEVEL "High winds (in excess of 40 MPH) resulted in significant debris at the plant intake. Traveling screens had bee in 'Fast' speed and continuous wash on the previous shift in anticipation of predicted high wind conditions. As entered the intake, high traveling screen differential pressure and lowering intake level prompted the operati enter the appropriate Abnormal Operating Procedure (AOP).

"Efforts to manually clean the screens were ineffective, and at 0059 hours6.828704e-4 days <br />0.0164 hours <br />9.755291e-5 weeks <br />2.24495e-5 months <br />, the crew inserted a manual scram directed by procedure at 240 foot intake level.

"On scram, as expected, reactor vessel level lowered to the low level scram setpoint (177 inches above top o fuel). At this point, as expected, an automatic Reactor Protection System (RPS) actuation, and a Group 2 Prim Containment Isolation System (PCIS) isolation occurred with no anomalies noted.

"During plant cooldown reactor level lowered to 177 inches above TAF. This resulted in a valid RPS actuation Group 2 isolation signal. All systems responded as expected.

"Operators were able to maintain reactor vessel level above the actuation setpoint for High Pressure Coolant (HPCI) and Reactor Core Isolation Cooling (RCIC) systems, and these systems were not required to operate.

"The cause of the failure of the traveling screens to maintain intake level is under investigation.

"All control rods are fully inserted and the plant is stable in Mode 3, Hot Shutdown."

Decay heat is being removed via the turbine bypass valves to the main condenser. No SRVs lifted during the The plant is in a normal shutdown electric plant lineup.

The licensee notified the NRC Resident Inspector and the New York Public Service Commission.

Power Reactor Event Number: 43753 Facility: HOPE CREEK Notification Date: 10/29/2007 Region: 1 State: NJ Notification Time: 02:12 [ET]

Unit: [1] [ ] [ ] Event Date: 10/28/2007 RX Type: [1] GE-4 Event Time: 22:03 [EDT]

NRC Notified By: BERNIE LITKETT Last Update Date: 10/29/2007 HQ OPS Officer: JEFF ROTTON Emergency Class: NON EMERGENCY Person (Organization):

10 CFR Section: JOHN CARUSO (R1) 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION SCRAM Current Unit Code RX CRIT Initial PWR Initial RX Mode PWR Current RX 1 N N 0 Refueling 0 Refuelin Event Text REFUEL FLOOR EXHAUST HI-HI RADIATION ALARMS DURING REACTOR REASSEMBLY "On 10/28/07 at 2203 in Operational Condition 5, two of three Refuel Floor Exhaust Radiation Monitors actua file://c:\temp\CTXH7XGU.htm 11/1/2007

Page 8 of 8 HI Radiation during the Moisture Separator lift for Reactor Pressure Vessel Reassembly. Reactor Building Ven was procedurally secured at the time of the actuation to minimize the potential for airborne contamination. T of the elevated radiation levels at the Refuel Floor Exhaust Radiation Monitors is currently attributed to the lif Moisture Separator closer to the surface of the water to obtain an unobstructed underwater path to the React Pressure Vessel. The resulting ESF signal yielded an automatic start of the 'A' and 'D' Station Service Water P Filtration Recirculation and Ventilation System, and load-shed of non-1E breaker loads. All systems responde expected. Systems and components actuated by the condition have been restored to a normal stand-by align required. No other systems were affected and the plant is stable in Operational Condition 5."

The licensee will notify the NRC Resident Inspector. The licensee notified the Lower Alloways Creek Township Privacy Policy l Site Disclaimer Monday, October 29, 2007 file://c:\temp\CTXH7XGU.htm 11/1/2007