ML073110629: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(Created page by program invented by StriderTol)
 
Line 15: Line 15:


=Text=
=Text=
{{#Wiki_filter:Event Text NRC Notified By: ROBERT BROCK HQ OPS Officer: JASON KOZAL Last Update Date: 10/26/2007 Emergency Class: NON EMERGENCY 10 CFR Section:
{{#Wiki_filter: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):
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION 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 hour 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.
DAVID HILLS (R3) UnitSCRAM Code RX CRITInitial PWR Initial RX ModeCurrent PWRCurrent RX 1 N Y 100Power Operation 100 Power Ope 2 N Y 100Power Operation 100 Power OpeBOTH LOW TEMPERATURE OVERPRESSURE PROTECTION SYSTEMS OUT OF SERVICE
  "2) The setpoint calculation does not consider instrument delay times during (PORV) Pilot Operated Relief Va actuation.
 
  "3) The updated Calculation changes instrument uncertainties.
"This 8 hour report is being made pursuant to 10 CFR 50.72(b)(3)(v). On 10/25/2007 at 1930 CDT Point Be aPlant (PBNP) Unit 1 and Unit 2 low temperature overpressure protection systems (LTOP) were declared inop eresult 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 BNuclear Plant specific system flow model.
  "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."
"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%
po w3.4.12 is only applicable in Mode 5, Mode 6 when the reactor vessel head is on, and Mode 4 when any cold l etemperature 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 duri ntemperature conditions are in progress. Implementation of these procedure changes will permit LTOP to be r e service."
 
The licensee stated that this issue was discovered as part of the on going calculation reconstitution initiative plant.
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.
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).
* UPDATE PROVIDED BY RYAN RODE TO JASON KOZAL AT 2135 ON 10/26/07 * * * 
  "Efforts to manually clean the screens were ineffective, and at 0059 hours, 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


"The following is an update to the 8 hr report made to the NRC via EN#43750: 
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}}
"On 10/26/07 at 17:51 procedure changes which identify requirements for operation of reactor coolant pum pcharging pumps during low temperature conditions have been made. These procedures provide the guidanceto ensure that the current LTOP setpoints remain conservative. Based on the issuance of these procedures wrequired guidance, LTOP is returned to service for both Unit-1 and Unit-2."
The licensee notified the NRC Resident Inspector. Notified R3DO (Hills).Power ReactorEvent Number: 43752Facility: FITZPATRICK Region: 1 State: NY Unit: [1] [ ] [ ]
RX Type: [1] GE-4 NRC Notified By: DAVE RICHARDSON HQ OPS Officer: JEFF ROTTON Notification Date: 10/28/2007 Notification Time: 03:24 [ET] Event Date: 10/28/2007 Event Time: 00:59 [EDT] Last Update Date: 10/28/2007 Emergency Class: NON EMERGENCY Person (Organization):
Pa ge 6of 8 11/1/2007 file://c:\tem p\CTXH7XGU.htm Event Text Event Text 10 CFR Section:  50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION JOHN CARUSO (R1) UnitSCRAM Code RX CRITInitial PWR Initial RX ModeCurrent PWRCurrent RX 1 M/R Y 100Power Operation 0Hot Shut dMANUAL SCRAM DUE TO LOWERING INTAKE LEVEL 
 
"High winds (in excess of 40 MPH) resulted in significant debris at the plant intake. Traveling screens had be ein 'Fast' speed and continuous wash on the previous shift in anticipation of predicted high wind conditions. A s entered the intake, high traveling screen differential pressure and lowering intake level prompted the operat ienter the appropriate Abnormal Operating Procedure (AOP). 
"Efforts to manually clean the screens were ineffective, and at 0059 hours, the crew inserted a manual scra mdirected 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 ofuel). At this point, as expected, an automatic Reactor Protection System (RPS) actuation, and a Group 2 Pri mContainment 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 ReactorEvent Number: 43753Facility: HOPE CREEK Region: 1 State: NJ Unit: [1] [ ] [ ]
RX Type: [1] GE-4 NRC Notified By: BERNIE LITKETT HQ OPS Officer: JEFF ROTTON Notification Date: 10/29/2007 Notification Time: 02:12 [ET] Event Date: 10/28/2007 Event Time: 22:03 [EDT] Last Update Date: 10/29/2007 Emergency Class: NON EMERGENCY 10 CFR Section:  50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION Person (Organization):  JOHN CARUSO (R1) UnitSCRAM Code RX CRITInitial PWR Initial RX ModeCurrent PWRCurrent RX 1 N N 0 Refueling 0 Refueli nREFUEL 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 actu a Pa ge 7of 8 11/1/2007 file://c:\tem p\CTXH7XGU.htm HI Radiation during the Moisture Separator lift for Reactor Pressure Vessel Reassembly. Reactor Building Ve nwas procedurally secured at the time of the actuation to minimize the potential for airborne contamination.
Tof the elevated radiation levels at the Refuel Floor Exhaust Radiation Monitors is currently attributed to the li fMoisture Separator closer to the surface of the water to obtain an unobstructed underwater path to the Reac tPressure Vessel. The resulting ESF signal yielded an automatic start of the 'A' and 'D' Station Service Water PFiltration Recirculation and Ventilation System, and load-shed of non-1E breaker loads. All systems respond eexpected. Systems and components actuated by the condition have been restored to a normal stand-by alig nrequired. 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 Townshi p Privacy Policy l Site Disclaimer Monday, October 29, 2007 Pa ge 8of 8 11/1/2007 file://c:\tem p\CTXH7XGU.htm}}

Latest revision as of 01:52, 23 November 2019

Manual Scram Due to Lowering Intake Level
ML073110629
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 10/29/2007
From:
- No Known Affiliation
To:
Office of Nuclear Reactor Regulation
References
Download: ML073110629 (3)
v • d • e


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

Retrieved from "https://kanterella.com/w/index.php?title=ML073110629&oldid=2171099"