ML060880290
| ML060880290 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/06/2006 |
| From: | Bailey R Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| Download: ML060880290 (43) | |
Text
Page 1 of 10 N06-SRO-a TITLE Review Completed SDM Calculation REVISION 0
PROGRAM Initial Licensed Operator (ILT)
TIME 20 Minutes SCOPE OF REVISION: Bank JPM No. SRO-N005 DATE:
Name:
Max Bailey AUTHOR Signature:
Name:
FACILITY REVIEWER Signature:
Facility Supervisor / Manager
COURSE NUMBER AND TITLE:
N06-SRO-a Review Completed SDM Calculation REVISION: 0 Page 2 of 10 REFERENCES Unit 1 Technical Data Book Cycle 20 01-OHP-4021-001-012, Rev 20 Determination of Reactor Shutdown Margin TASK TASK ID:
ADM0370302 Verify Limiting Conditions for Operations are met in accordance with Technical Specifications K/A Statement:
2.1.25 Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data.
K/A Importance:
RO:
2.8 SRO: 3.1 K/A Statement:
2.1.32 Ability to explain and apply all system limits and precautions.
K/A Importance:
RO:
3.4 SRO: 3.8 EVALUATION SETTING Classroom HANDOUTS Completed Attachment 1 of 01-OHP-4020-001-012 Tech Data Book Figures 1.3b and 13.1 Calculator ATTACHMENTS None SIMULATOR SETUP None
COURSE NUMBER AND TITLE:
N06-SRO-a Review Completed SDM Calculation REVISION: 0 Page 3 of 10 TASK OBJECTIVES/STANDARDS Review and verify the accuracy of a manual Shutdown Margin Calculation for MODE 1 or 2.
EVALUATOR INSTRUCTIONS Provide the operator with a completed copy of Attachment 1 of 01-OHP-4020-001-012 and Tech Data Book Figures TASK BREIFING You are the Unit Supervisor on Unit 1.
Per your direction, the extra Control Room Operator completed Attachment 2 of 01-OHP-4021-001-012, Determination of Reactor Shutdown Margin.
Unit 1 conditions are as follows:
- PPC point U0035 indicates 12,135 MWD/MTU
- Reactor power is at 100% steady state.
- Control Bank D step counter indicates 219 steps.
- Individual rod positions for the Control Bank D rods are as follows:
D-4 at 211 steps D-8 at 203 steps D-12 at 218 steps H-4 at 216 steps H-8 at 218 steps H-12 at 220 steps M-4 at 216 steps M-8 at 210 steps M-12 at 209 steps
- NO control rods are known to be unmovable or untrippable.
Perform the SRO review of the completed Attachment 2.
COURSE NUMBER AND TITLE:
N06-SRO-a Review Completed SDM Calculation REVISION: 0 Page 4 of 10 Operator initiates review of Attachment 2.
COURSE NUMBER AND TITLE:
N06-SRO-a Review Completed SDM Calculation REVISION: 0 Page 5 of 10 CT: Operator determines that NO rods are misaligned or below the RIL. Rod D-8 is NOT misaligned. TBD-1-FIG-13.1 allows
+ 18 steps. Rod D-8 is at -16 steps.
COURSE NUMBER AND TITLE:
N06-SRO-a Review Completed SDM Calculation REVISION: 0 Page 6 of 10 Operator should identify the second bullet of Step 4.3 as N/A with initial and date required.
COURSE NUMBER AND TITLE:
N06-SRO-a Review Completed SDM Calculation REVISION: 0 Page 7 of 10 Operator should identify Step 4.5.2 is N/A with initial and date required.
NO stuck rod has been identified.
CT: Operator shall identify NO misaligned rod exist. Refer to Step 4.2.2 which identified rod D-8 as misaligned.
COURSE NUMBER AND TITLE:
N06-SRO-a Review Completed SDM Calculation REVISION: 0 Page 8 of 10 CT: Operator shall identify error carried forward. NO misaligned rod exist. Refer to Step 4.2.2 which identified rod D-8 as misaligned.
Operator identifies both bulleted items of Step 4.8 under OR should be N/A with initial and date required.
COURSE NUMBER AND TITLE:
N06-SRO-a Review Completed SDM Calculation REVISION: 0 Page 9 of 10 CT: Operator shall identify the incorrect use of rod D-8 misalignment data in the calculation. Although the SDM calcualtion is conservative, the calculated value is incorrect and the SRO should not sign this Attachment until the necessary corrections are made.
THIS JPM IS COMPLETE
N06-SRO-a Page 10 of 10 Task Briefing You are the Unit Supervisor on Unit 1.
Per your direction, the extra Control Room Operator completed Attachment 2 of 01-OHP-4021-001-012, Determination of Reactor Shutdown Margin.
Unit 1 conditions are as follows:
- PPC point U0035 indicates 12,135 MWD/MTU
- Reactor power is at 100% steady state.
- Control Bank D step counter indicates 219 steps.
- Individual rod positions for the Control Bank D rods are as follows:
D-4 at 211 steps D-8 at 203 steps D-12 at 218 steps H-4 at 216 steps H-8 at 218 steps H-12 at 220 steps M-4 at 216 steps M-8 at 210 steps M-12 at 209 steps
- NO control rods are known to be unmovable or untrippable.
Perform the SRO review of the completed Attachment 2.
Page 1 of 7 N06-SRO-b TITLE Review AFD Log REVISION 0
PROGRAM Initial License Training (ILT)
TIME 15 Minutes SCOPE OF REVISION: New Issue from SR-O-ADM10 Rev. 0 DATE:
Name:
Max Bailey AUTHOR Signature:
Name:
FACILITY REVIEWER Signature:
Facility Supervisor / Manager
COURSE NUMBER AND TITLE:
N06-SRO-b Review AFD Log REVISION: 0 Page 2 of 7 REFERENCES 01-OHP-4024-110, Drop 44, Rev. 12 Tech Data Book 1-Figure 13.1 Unit 1 Cycle 20 TASK TASK ID:
ADM0370302 Verify Limiting Conditions for Operations are met in accordance with Technical Specifications K/A Statement:
2.1.12 Ability to apply technical specifications for a system.
K/A Importance: RO: 2.9 SRO: 4.0 EVALUATION SETTING Classroom HANDOUTS Completed Attachment A of 01-OHP-4024-110 Drop 44.
Tech Data Book 1-Figure 13.1 Unit 1 Cycle 20 ATTACHMENTS None SIMULATOR SETUP None
COURSE NUMBER AND TITLE:
N06-SRO-b Review AFD Log REVISION: 0 Page 3 of 7 TASK OBJECTIVES/STANDARDS Review a completed AFD Log for correctness and compliance.
EVALUATOR INSTRUCTIONS Provide student with a completed copy 01-OHP-4024-110 Drop 44, Attachment A.
Provide 1-Figure 13.1 Unit 1 Cycle 20 TASK BRIEFING Unit 1 is at 100% power. A Xenon oscillation is in progress and as a result the Control Rods have been moved in an effort to dampen out the oscillation. The AFD Monitor Alarm was declared Inoperable at 0545 hrs this morning due to a bad input to the PPC. A Reactor Operator has recorded the AFD readings during the shift per 01-OHP-4024-110 Drop 44 Attachment A.
You are the Unit 1 Unit Supervisor.
The AFD Monitor Alarm was declared Operable at 1500 hrs. The Reactor Operator has stopped taking AFD data and turned in the completed Attachment A.
You are to review the completed 01-OHP-4024-110, Attachment A, for correctness and compliance.
COURSE NUMBER AND TITLE:
N06-SRO-b Review AFD Log REVISION: 0 Page 4 of 7 C.T. Identifies AFD Target Band Limit is +4.2.
COURSE NUMBER AND TITLE:
N06-SRO-b Review AFD Log REVISION: 0 Page 5 of 7 C.T. Identifies AFD outside the Target Band (2/4 >+4.2)
Cue: Once AFD is identified as outside the Target Band, ask how long it has been outside the Target Band.
C.T. Identifies AFD outside the Target Band for at least 30 minutes.
Reference LCO 3.2.3 Condition C. The logged values of the indicated AFD shall be assumed to exist during the interval preceding each logging.
Cue: (If SRO is concerned about T.S. required Thermal Power reduction) Inform him/her the Senior License Holder is reviewing this issue and that the SRO is only responsible for the surveillance review.
COURSE NUMBER AND TITLE:
N06-SRO-b Review AFD Log REVISION: 0 Page 6 of 7 Cue: Ask the SRO if any additional surveillance requirements are necessary after the AFD Alarm Monitor was declared Operable at 1500 hrs.
C.T. Identifies log taking must continue to occur every 30 minutes for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after restoring the AFD Monitor Alarm to Operable status if the AFD has been outside the target band for any period of time in the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of operation.
Reference LCO. 3.2.3 and step 3.8.
THIS JPM IS COMPLETE
N06-SRO-b Page 7 of 7 Task Briefing Unit 1 is at 100% power. A Xenon oscillation is in progress and as a result the Control Rods have been moved in an effort to dampen out the oscillation. The AFD Monitor Alarm was declared Inoperable at 0545 hrs this morning due to a bad input to the PPC.
A Reactor Operator has recorded the AFD readings during the shift per 01-OHP-4024-110 Drop 44 Attachment A.
You are the Unit 1 Unit Supervisor.
The AFD Monitor Alarm was declared Operable at 1500 hrs. The Reactor Operator has stopped taking AFD data and turned in the completed Attachment A.
You are to review the completed 01-OHP-4024-110, Attachment A, for correctness and compliance.
Page 1 of 7 N06-SRO-c TITLE Verify a Clearance Permit for East ESW Pump REVISION 0
PROGRAM Initial Licensed Operator (ILT)
TIME 20 Minutes SCOPE OF REVISION: NEW ISSUE DATE:
Name:
Max Bailey AUTHOR Signature:
Name:
FACILITY REVIEWER Signature:
Facility Supervisor / Manager
COURSE NUMBER AND TITLE:
N06-SRO-c Verify a Clearance Permit for the East ESW Pump REVISION: 0 Page 2 of 7 REFERENCES 12-OHP-2110-CPS-001, Rev 14 Clearance Permit System TASK TASK ID:
3000040201 Verify/Approve a Clearance Permit.
K/A
REFERENCE:
2.2.13 Knowledge of tagging and clearance procedures.
K/A IMPORTANCE:
RO 3.6 SRO 3.8 EVALUATION SETTILNG Classroom HANDOUTS Task Briefing Clearance Package (Forms, Cards ( ), & Prints OP-1-5113-87, OP-1-98415-45)
Copy of 12-OHP-2110-CPS-001, Attachment 1 ATTACHMENTS None SIMULATOR SETUP None
COURSE NUMBER AND TITLE:
N06-SRO-c Verify a Clearance Permit for the East ESW Pump REVISION: 0 Page 3 of 7 Task Standards The operator performs a review per 12-OHP-2110-CPS-001 and determines that the clearance is improperly sequenced, and that tags are required for the control power fuses and that the strainer power supply should be off.
Task Briefing You are an extra SRO.
The Work Control Center-SRO directs you to verify the Unit 1 East Essential Service Water (PP-7E) Pump clearance is ready to hang per 12-OHP-2110-CPS-001, Attachment 1.
- The clearance was written to protect workers/equipment during a ESW motor/pump and strainer basket inspection.
- The Clearance was written from a Clearance Request.
- The Clearance was not written from a Standard Clearance.
- The Clearance does not fit into the boundaries of an existing Clearance.
COURSE NUMBER AND TITLE:
N06-SRO-c Verify a Clearance Permit for the East ESW Pump REVISION: 0 Page 4 of 7 CT - Identifies 1-T11D10-Fuses have NO TAG associated. (Fuses Should be Tagged)
Identifies 1-T11D10-Fuses are sequenced after 1-T11D10 Breaker (Fuses Should be Pulled &Tagged before breaker is taken to DISC)
COURSE NUMBER AND TITLE:
N06-SRO-c Verify a Clearance Permit for the East ESW Pump REVISION: 0 Page 5 of 7 CT - Identifies that the Position listed for 1-PS-D-3C (Strainer Power Supply Breaker) is ON (Should be tagged off)
Identifies that Restoration Configuration position for 1-PS-D-3C (Strainer Power Supply Breaker) is OFF (Should be ON)
COURSE NUMBER AND TITLE:
N06-SRO-c Verify a Clearance Permit for the East ESW Pump REVISION: 0 Page 6 of 7 THIS JPM IS COMPLETE.
N06-SRO-c N06-SRO-c.doc Page 7 of 7 Task Briefing You are an extra SRO.
The Work Control Center-SRO directs you to verify the Unit 1 East Essential Service Water (PP-7E)
Pump clearance is ready to hang per 12-OHP-2110-CPS-001, Attachment 1.
- The clearance was written to protect workers/equipment during a ESW motor/pump and strainer basket inspection.
- The Clearance was written from a Clearance Request.
- The Clearance was not written from a Standard Clearance.
- The Clearance does not fit into the boundaries of an existing Clearance.
Page 1 of 7 N06-SRO-d TITLE Respond to a High SJAE Radiation Alarm REVISION 0
PROGRAM Initial License Training (ILT)
TIME 15 Minutes SCOPE OF REVISION: New Issue DATE:
Name:
Max Bailey AUTHOR Signature:
Name:
FACILITY REVIEWER Signature:
Facility Supervisor / Manager
COURSE NUMBER AND TITLE:
N06-SRO-d Respond to a High SJAE Radiation Alarm REVISION: 0 Page 2 of 7 REFERENCES 12-OHP-4024-139, Drop 25, Rev. 11 Steam Jet Air Ejector Tech Data Book Figures:
- 2-Figure-19.19a, Rev 3 Primary to Secondary Leak Rate (Unit 2 at 5 SCFM)
- 2-Figure-19.19b, Rev 2 Primary to Secondary Leak Rate (Unit 2 at 10 SCFM)
- 2-Figure-19.19c, Rev 2 Primary to Secondary Leak Rate (Unit 2 at 15 SCFM)
- 2-Figure-19.19e, Rev 0 Primary to Secondary Leak Rate (Unit 2 at 20 SCFM)
TASK TASK ID:
ADM0420302 Verify Limiting Conditions for Operations are met in accordance with Offsite Dose Calculation Manual (ODCM)
K/A Statement:
2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.
K/A Importance:
RO:
2.9 SRO: 3.3 EVALUATION SETTING Classroom HANDOUTS Completed Data Sheet 1 of 12-OHP-4024-139 Drop 25.
Tech Data Book Figures:
- 2-Figure-19.19a
- 2-Figure 19.19b
- 2-Figure-19.19c
- 2-Figure-19.19e ATTACHMENTS None SIMULATOR SETUP None
COURSE NUMBER AND TITLE:
N06-SRO-d Respond to a High SJAE Radiation Alarm REVISION: 0 Page 3 of 7 TASK OBJECTIVES/STANDARDS Review a completed Data Sheet 1 of 12-OHP-4024-139 Drop 25 for accuracy and determine required actions based upon that data.
EVALUATOR INSTRUCTIONS Provide student with a completed copy Data Sheet 1 of 12-OHP-4024-139 Drop 25.
Provide a copy of 2-Figure 19.19a, 2-Figure 19.19b, 2-Figure 19.19c, and 2-Figure 19.19e.
TASK BREIFING Unit 2 is at 100% power. Radiation Monitoring Panel Alert alarm was received on SRA 2900. A RCS to Steam Generator Tube Leak is suspected. The BOP has taken initial action per 12-OHP-4024-139, Drop 25 to record SRA-2905 activity and leak rate on Data Sheet 1 at 15 minute intervals.
Your are the extra SRO.
The US directs you to plot the data and determine the total leak rate in accordance with 12-OHP-4024-139, Drop 25. Report your results and any operational limitations required per 12-OHP-4024-139, Drop 25.
COURSE NUMBER AND TITLE:
S N06-SRO-d Respond to a High SJAE Radiation Alarm REVISION: 0 Page 4 of 7 Operator determines that SJAE graph for 10 scfm (7 scfm actual) should be used for graphing radiation reading.
COURSE NUMBER AND TITLE:
S N06-SRO-d Respond to a High SJAE Radiation Alarm REVISION: 0 Page 5 of 7 CT: Operator graphs the radiation monitor data as indicated. Slope of curve indicated leakrate exceeds 30 GPD.
COURSE NUMBER AND TITLE:
S N06-SRO-d Respond to a High SJAE Radiation Alarm REVISION: 0 Page 6 of 7 CT: Operator determines the leakrate to be greater than 30 GPD.
The final leakrate is 103 GPD (100 to 105)
Operator reports leakrate of 103 GPD, and the need to reduce power to less than 50% within one hour and be in MODE 3 within the next two hours.
CUE: US acknowledges leakrate and need to commence power reduction.
THIS JPM IS COMPLETE
N06-SRO-d Page 7 of 7 Task Briefing Unit 2 is at 100% power. Radiation Monitoring Panel Alert alarm was received on SRA 2900. A RCS to Steam Generator Tube Leak is suspected. The BOP has taken initial action per 12-OHP-4024-139, Drop 25 to record SRA-2905 activity and leak rate on Data Sheet 1 at 15 minute intervals.
Your are the extra SRO.
The US directs you to plot the data and determine the total leak rate in accordance with 12-OHP-4024-139, Drop 25. Report your results and any operational limitations required per 12-OHP-4024-139, Drop 25.
Steam Jet Air Ejector Radiation Readings TIME RMS Reading 0
3.20E-06
+15 3.70E-06
+30 4.20E-06
+45 5.10E-06
+60 5.80E-06
+75 8.20E-06
+90 1.12E-05
+105 1.30E-05
+120 1.31E-05 SJAE flow rate = 7.0 scfm
Page 1 of 12 N06-SRO-e TITLE Prepare Prompt NRC Notification Worksheet REVISION 0
PROGRAM Initial Licensed Operator (ILT)
TIME 10 Minutes SCOPE OF REVISION: New Issue DATE:
Name:
Max Bailey AUTHOR Signature:
Name:
FACILITY REVIEWER Signature:
Facility Supervisor / Manager
COURSE NUMBER AND TITLE:
N06-SRO-e Prepare Prompt NRC Notification Worksheet REVISION: 0 Page 2 of 12 REFERENCES PMP-7030-001-001, Rev 8 Prompt NRC Notification 10 CFR 50.72, Notification of NRC NUREG-1022, Revent Reporting Guidelines TASK TASK ID:
ADM1250304 Make a prompt NRC notification K/A Statement:
2.4.30 Knowledge of which events related to system operations/status should be reported to outside agencies.
K/A Importance:
RO:
2.2 SRO: 3.6 EVALUATION SETTING Classroom HANDOUTS Task Briefing Sheet Copy of procedure PMP-7030-001-001 ATTACHMENTS None SIMULATOR SETUP None
COURSE NUMBER AND TITLE:
N06-SRO-e Prepare Prompt NRC Notification Worksheet REVISION: 0 Page 3 of 12 TASK OBJECTIVES/STANDARDS Determine NRC notification requirements and prepare an event notification worksheet.
EVALUATOR INSTRUCTIONS Brief the student by providing the student with a task briefing sheet to read. Provide a copy of PMP-7030-001-001 for reference use.
TASK BRIEFING You are the extra SRO.
The Shift Manager directs you to determine the NRC notification requirements and prepare an event notification worksheet (Data Sheet 1) for prompt NRC NOTIFICATION in accordance with PMP-7030-001-001.
The following plant conditions exist as noted.
- Current time is 1400
- DC Cook Units 1 & 2 were both operating at 100% steady state power.
- At 1325 today, Unit 1 tripped from 100% power.
- The reason for the reactor trip was a steam-flow/feed-flow mismatch with low SG level in #11 SG which was caused by the #11 SG Feed. Reg. Valve (FRV-110) failing closed.
- Steam Generator #12 Safety Valve has opened and did not reseat (remains partially open).
- The Unit 1 operation crew manually initiated Safety Injection due to uncontrolled lowering of RCS temperature / pressure, and Steam Generator #12 pressure continues to lower.
- The Unit 1 operating crew has completed E-0, Reactor Trip and Safety Injection, E-2 Faulted Steam Generator Isolation, and is currently in ES-1.1, SI Termination. SI flow has been terminated per ES-1.1.
- Present RCS conditions: RCS is stable in Mode 3; level in SG #12 is at 5% WR and slowly lowering; all other SGs are being maintained between 26% and 50% NR on auxiliary feedwater; and there is no detectable radiation release in progress.
- All other plant systems responded normally to the trip.
- The SM has determined that NO Emergency Classification is required per PMP-2080-EPP-101.
COURSE NUMBER AND TITLE:
N06-SRO-e Prepare NRC Prompt Notification Worksheet REVISION: 0 Page 4 of 12 CT: Determine from conditions stated that the event is reportable per guidance provided in PMP 7030-001-001 Refers to FIGURE 1 to identify reportability and the reference text section for information and clarification CT: Goes to Data Sheet 1
COURSE NUMBER AND TITLE:
N06-SRO-e Prepare NRC Prompt Notification Worksheet REVISION: 0 Page 5 of 12 NO CRITERIA ON THIS PAGE APPLIY TO THE STATED PLANT CONDITIONS.
COURSE NUMBER AND TITLE:
N06-SRO-e Prepare NRC Prompt Notification Worksheet REVISION: 0 Page 6 of 12 NO CRITERIA ON THIS PAGE APPLIY TO THE STATED PLANT CONDITIONS.
COURSE NUMBER AND TITLE:
N06-SRO-e Prepare NRC Prompt Notification Worksheet REVISION: 0 Page 7 of 12 CT: Identifies that an unplanned ECCS actuation and unplanned reactor trip from a critical condition, both from valid signals requires a report within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
CT: Note the sections in the procedure text that provide information or clarification of this flow chart determination.
COURSE NUMBER AND TITLE:
N06-SRO-e Prepare NRC Prompt Notification Worksheet REVISION: 0 Page 8 of 12 CT: Refers to section in procedure text for information of clarification of flow chart results
COURSE NUMBER AND TITLE:
N06-SRO-e Prepare NRC Prompt Notification Worksheet REVISION: 0 Page 9 of 12 CT: Refers to section in procedure text for information of clarification of flow chart results.
COURSE NUMBER AND TITLE:
N06-SRO-e Prepare NRC Prompt Notification Worksheet REVISION: 0 Page 10 of 12 CT: Fill in applicable data to include:
Notification of Time / Facility or organization Unit / Caller / Call Back Number (Can be any plant extension)
Event Time / Date / mode (Before and After)
CT: 4 hr Classification (TS required SD & ECCS to RCS)
==
Description:==
Reactor Trip due to the Feed Reg Valve closure on SG #11 causing a SF/FF mismatch with low SG level. This was followed by a manual ECCS Actuation on lowering RCS Temp & Pressure from steam release through SG #12 safety valve that opened and failed to reseat. RCS stable in mode three, SI terminated per ES-1.1, SI Termination, SG #12 has blown down and all other SGs are stable at 26% to 50% NR level.
Notifications (NRC)
Other Information
COURSE NUMBER AND TITLE:
N06-SRO-e Prepare NRC Prompt Notification Worksheet REVISION: 0 Page 11 of 12 NO ITEMS ON THIS PAGE ARE APPLICABLE JPM IS COMPLETE
N06-SRO-e Page 12 of 12 Task Briefing You are the extra SRO.
The Shift Manager directs you to determine the NRC notification requirements and prepare an event notification worksheet (Data Sheet 1) for prompt NRC NOTIFICATION in accordance with PMP-7030-001-001.
The following plant conditions exist as noted.
- Current time is 1400
- DC Cook Units 1 & 2 were both operating at 100% steady state power.
- At 1325 today, Unit 1 tripped from 100% power.
- The reason for the reactor trip was a steam-flow/feed-flow mismatch with low SG level in #11 SG which was caused by the #11 SG Feed. Reg. Valve (FRV-110) failing closed.
- Steam Generator #12 Safety Valve has opened and did not reseat (remains partially open).
- The Unit 1 operation crew manually initiated Safety Injection due to uncontrolled lowering of RCS temperature / pressure, and Steam Generator #12 pressure continues to lower.
- The Unit 1 operating crew has completed E-0, Reactor Trip and Safety Injection, E-2 Faulted Steam Generator Isolation, and is currently in ES-1.1, SI Termination. SI flow has been terminated per ES-1.1.
- Present RCS conditions: RCS is stable in Mode 3; level in SG #12 is at 5% WR and slowly lowering; all other SGs are being maintained between 26% and 50% NR on auxiliary feedwater; and there is no detectable radiation release in progress.
- All other plant systems responded normally to the trip.
- The SM has determined that NO Emergency Classification is required per PMP-2080-EPP-101.