Text

CP-2012-06 Draft Ops Test SRO Admin Jpms, Determine Loss of RHR Time Limitations.
	ML12158A557
Person / Time
Site:	Comanche Peak
Issue date:	06/11/2012
From:	; NRC Region 4
To:	; Luminant Generation Co
References
	Download: ML12158A557 (164)
	v • d • e

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SA1 Task # SO1002 K/A # 2.1.25 3.9 / 4.2

Title:

Determine Loss of RHR Time Limitations Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

JPM Cue Sheet #1 Unit 1 is in MODE 5 with water level in the Reactor Vessel at 53 above the top of the Upper Core Plate.

All Pressurizer Safety Valves have been removed.

Reactor Coolant System temperature is 100°F.

The Reactor was shut down 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months ago.

A Loss of Residual Heat Removal cooling has just occurred.

Initiating Cue: The Shift Manager directs you to PERFORM the following:

JPM Cue Sheet #1 CALCULATE per ABN-104, Residual Heat Removal System Malfunction, Attachment 5, Time to Saturation for Loss of All RHR with the RCS at Reduced Inventory and Attachment 19, Available Time for Containment Closure:

DETERMINE Time to Saturation. ________

DETERMINE most limiting Containment Closure Time. ________

Initial Conditions: Given the following conditions:

JPM Cue Sheet #2 Unit 1 is in MODE 5 with water level in the Reactor Vessel at 53 above the top of the Upper Core Plate.

Reactor Coolant System Loops are NOT filled.

The Containment Equipment Hatch is removed.

IPO-010A, Reactor Coolant System Reduced Inventory Operations, Attachment 1, Shiftly Checklist is complete.

Safeguards Bus 1EA1 was lost on an 86-1 Lockout Relay actuation.

Train B Residual Heat Removal Pump will NOT start.

Containment Equipment Hatch closure has been initiated.

Page 1 of 8 CPNPP NRC 2012 JPM SA1 Rev d.docx

Appendix C JPM WORKSHEET Form ES-C-1 Initiating Cue: Based on the Initial Conditions, contingencies were verified in place due to the JPM Cue Sheet #2 Containment Equipment Hatch being removed prior to the loss of Safeguards Bus 1EA1 and the failure of RHR Pump 1-02 to start.

IDENTIFY the Reactor Coolant System Reduced Inventory contingencies regarding the Containment Equipment Hatch being removed.

Task Standard: Utilizing ABN-104, determined Time to Saturation and most limiting Containment Closure Time following a Loss of the Residual Heat Removal System.

Utilizing IPO-010A, Attachment 1, identified contingencies required with Containment Equipment Hatch removed while the Reactor Coolant System is at Reduced Inventory.

Required Materials: ABN-104, Residual Heat Removal System Malfunction, Rev. 8-10.

IPO-010A, Reactor Coolant System Reduced Inventory Operations, Rev 18-2.

Validation Time: 20 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 2 of 8 CPNPP NRC 2012 JPM SA1 Rev d.docx

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of JPM Cue Sheet #1 and the following:

ABN-104, Residual Heat Removal Malfunction.

Attachment 5, Time to Saturation for Loss of All RHR with the RCS at Reduced Inventory.

Attachment 19, Available Time for Containment Closure.

When JPM Cue Sheet #1 is complete, PROVIDE the examinee with a copy of JPM Cue Sheet #2 and MAKE the following available in the classroom:

IPO-010A, Reactor Coolant System Reduced Inventory Operations.

Page 3 of 8 CPNPP NRC 2012 JPM SA1 Rev d.docx

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: Provide the examinee with copy of JPM Cue Sheet #1.

Examiner Note: The following steps are from ABN-104, Attachment 5.

Perform Step: 1 Determine Time to Saturation:

Find Time to Saturation from Attachment 5, Page 1.

Standard: REFERRED to Page 1 of Attachment 5 and PLOTTED the intersection of Time After Shutdown (336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months ) and Initial Temp (100ºF) and DETERMINED: TIME TO SATURATION = 22 +/- 1 minutes.

Comment: SAT UNSAT Examiner Note: The following step is from ABN-104, Attachment 19.

Perform Step: 2 Determine most limiting Containment Closure time:

Find Containment Closure Time from Attachment 19:

Radiological Environment Limiting Curve.

Thermal Environment Limiting Curve.

Standard: REFERRED to Attachment 19 and PLOTTED the intersection of Time After Shutdown (336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months ) and DETERMINED: Radiological Environment Limiting Containment Closure Time is most limiting =

75 +/- 3 minutes.

Comment: SAT UNSAT Examiner Note: Provide the examinee with copy of JPM Cue Sheet #2.

Examiner Note: The following steps are from IPO-010A, Attachment 1.

Perform Step: 3 IDENTIFY the Reactor Coolant System Reduced Inventory 2.0.A.1) contingencies regarding the Containment Equipment Hatch being removed.

Standard: IDENTIFIED the following contingencies for Containment Equipment Hatch removal with the RCS at Reduced Inventory:

VERIFY the four swing bolts are in place with nuts and washers installed.

Comment: SAT UNSAT Page 4 of 8 CPNPP NRC 2012 JPM SA1 Rev d.docx

Appendix C JPM STEPS Form ES-C-1 Perform Step: 4 IDENTIFY the Reactor Coolant System Reduced Inventory 2.0.A.2) contingencies regarding the Containment Equipment Hatch being removed.

Standard: IDENTIFIED the following contingencies for Containment Equipment Hatch removal with the RCS at Reduced Inventory:

VERIFY the gasket is in place or is available.

Comment: SAT UNSAT Perform Step: 5 IDENTIFY the Reactor Coolant System Reduced Inventory 2.0.A.3) contingencies regarding the Containment Equipment Hatch being removed.

Standard: IDENTIFIED the following contingencies for Containment Equipment Hatch removal with the RCS at Reduced Inventory:

VERIFY that the equipment door handling device or hoists are available for re-positioning the door.

Comment: SAT UNSAT Perform Step: 6 IDENTIFY the Reactor Coolant System Reduced Inventory 2.0.A.4) contingencies regarding the Containment Equipment Hatch being removed.

Standard: IDENTIFIED the following contingencies for Containment Equipment Hatch removal with the RCS at Reduced Inventory:

VERIFY that all lines penetrating Containment through the open equipment hatch have isolation and disconnect capability.

Comment: SAT UNSAT Perform Step: 7 IDENTIFY the Reactor Coolant System Reduced Inventory 2.0.A.5) contingencies regarding the Containment Equipment Hatch being removed.

Standard: IDENTIFIED the following contingencies for Containment Equipment Hatch removal with the RCS at Reduced Inventory:

RECORD the name and telephone extension of the Maintenance Supervisor/ Containment Coordinator responsible for emergency equipment hatch installation.

Comment: SAT UNSAT Page 5 of 8 CPNPP NRC 2012 JPM SA1 Rev d.docx

Appendix C JPM STEPS Form ES-C-1 Perform Step: 8 IDENTIFY the Reactor Coolant System Reduced Inventory 2.0.A.6) contingencies regarding the Containment Equipment Hatch being removed.

Standard: IDENTIFIED the following contingencies for Containment Equipment Hatch removal with the RCS at Reduced Inventory:

ENSURE a phone check has been conducted within the previous 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Comment: SAT UNSAT Perform Step: 9 IDENTIFY the Reactor Coolant System Reduced Inventory 2.0.A.7) contingencies regarding the Containment Equipment Hatch being removed.

Standard: IDENTIFIED the following contingencies for Containment Equipment Hatch removal with the RCS at Reduced Inventory:

VERIFY scaffolding is in place, as necessary, for hatch installation.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 6 of 8 CPNPP NRC 2012 JPM SA1 Rev d.docx

Appendix C JPM CUE SHEET #1 Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

Unit 1 is in MODE 5 with water level in the Reactor Vessel at 53 above the top of the Upper Core Plate.

All Pressurizer Safety Valves have been removed.

Reactor Coolant System temperature is 100°F.

The Reactor was shut down 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months ago.

A Loss of Residual Heat Removal cooling has just occurred.

INITIATING CUE: The Shift Manager directs you to PERFORM the following:

CALCULATE per ABN-104, Residual Heat Removal System Malfunction, Attachment 5, Time to Saturation for Loss of All RHR with the RCS at Reduced Inventory and Attachment 19, Available Time for Containment Closure:

DETERMINE Time to Saturation. ________

DETERMINE most limiting Containment Closure Time. ________

Page 7 of 8 CPNPP NRC 2012 JPM SA1 Rev d.docx

Appendix C JPM CUE SHEET #2 Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

Unit 1 is in MODE 5 with water level in the Reactor Vessel at 53 above the top of the Upper Core Plate.

Reactor Coolant System Loops are NOT filled.

The Containment Equipment Hatch is removed.

IPO-010A, Reactor Coolant System Reduced Inventory Operations, Attachment 1, Shiftly Checklist is complete.

Safeguards Bus 1EA1 was lost on an 86-1 Lockout Relay actuation.

Train B Residual Heat Removal Pump will NOT start.

Containment Equipment Hatch closure has been initiated.

INITIATING CUE: Based on the Initial Conditions, contingencies were verified in place due to the Containment Equipment Hatch being removed prior to the loss of Safeguards Bus 1EA1 and the failure of RHR Pump 1-02 to start.

IDENTIFY the Reactor Coolant System Reduced Inventory contingencies regarding the Containment Equipment Hatch being removed.

Page 8 of 8 CPNPP NRC 2012 JPM SA1 Rev d.docx

CPNPP NRC 2012 JPM SA1 Answer Key 1 Rev d CPSES PROCEDURE NO.

ABNORMAL CONDITIONS PROCEDURES MANUAL UNIT 1 AND 2 ABN-104 RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTION REVISION NO. 8 PAGE 58 OF 102 ATTACHMENT 5 PAGE 1 OF 2

[C] TIME TO SATURATION FOR LOSS OF ALL RHR WITH THE RCS AT REDUCED INVENTORY (assuming no makeup)

Attachment 5 CPNPP NRC 2012 JPM SA1 Answer Key 1 Rev d

CPNPP NRC 2012 JPM SA1 Answer Key 1 Rev d CPSES PROCEDURE NO.

ABNORMAL CONDITIONS PROCEDURES MANUAL UNIT 1 AND 2 ABN-104 RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTION REVISION NO. 8 PAGE 99 OF 102 ATTACHMENT 19 PAGE 1 OF 1

[C] AVAILABLE TIME FOR CONTAINMENT CLOSURE Attachment 19 CPNPP NRC 2012 JPM SA1 Answer Key 1 Rev d

CPNPP NRC 2012 JPM SA1 Answer Key 2 Rev d

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,QLWLDOV'DWH CPNPP NRC 2012 JPM SA1 Answer Key 2 Rev d

CPNPP NRC 2012 JPM SA1 Procedure 1 Rev d CPSES PROCEDURE NO.

ABNORMAL CONDITIONS PROCEDURES MANUAL UNIT 1 AND 2 ABN-104 RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTION REVISION NO. 8 PAGE 58 OF 102 ATTACHMENT 5 PAGE 1 OF 2

[C] TIME TO SATURATION FOR LOSS OF ALL RHR WITH THE RCS AT REDUCED INVENTORY (assuming no makeup)

Attachment 5 CPNPP NRC 2012 JPM SA1 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA1 Procedure 1 Rev d CPSES PROCEDURE NO.

ABNORMAL CONDITIONS PROCEDURES MANUAL UNIT 1 AND 2 ABN-104 RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTION REVISION NO. 8 PAGE 59 OF 102 ATTACHMENT 5 PAGE 2 OF 2 TIME TO CORE UNCOVERY FOR LOSS OF ALL RHR WITH THE RCS AT REDUCED INVENTORY (assuming no makeup)

Attachment 5 CPNPP NRC 2012 JPM SA1 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA1 Procedure 1 Rev d CPSES PROCEDURE NO.

ABNORMAL CONDITIONS PROCEDURES MANUAL UNIT 1 AND 2 ABN-104 RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTION REVISION NO. 8 PAGE 99 OF 102 ATTACHMENT 19 PAGE 1 OF 1

[C] AVAILABLE TIME FOR CONTAINMENT CLOSURE Attachment 19 CPNPP NRC 2012 JPM SA1 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA1 Procedure 2 Rev d CPNPP PROCEDURE NO.

INTEGRATED PLANT OPERATING PROCEDURES MANUAL UNIT 1 IPO-010A REACTOR COOLANT SYSTEM REVISION NO. 18 REDUCED INVENTORY OPERATIONS PAGE 124 OF 195 CONTINUOUS USE ATTACHMENT 1 PAGE 1 OF 12

[C] SHIFTLY CHECKLIST NOTE: ! Reduced inventory operation is defined as #80 inches above the core plate (829'8").

! This Attachment will require a dedicated Plant Equipment Operator coordinating with a dedicated Control Room Operator to complete.

1.0 Administrative Controls

[C] A. CONDUCT a pre-shift brief to discuss the topics specified by Attachment 11. /

Initials Date NOTE: Sections 2.0 and 3.0 identify equipment operability requirements and restrictions on the condition of Containment.

B. REVIEW the documents listed below to identify conditions or activities in progress that could impair the Containment boundary, RHR and support systems or equipment and instrumentation listed in Sections 2.0, 3.0, and 4.0 of this attachment.

! Active Clearances /

Initials Date

! Unit Log (for work or tests in progress) /

Initials Date

! LCO Tracking Log /

Initials Date

! Annunciator / Instrument Out-of-Service Log /

Initials Date

! Temporary Modification Log /

Initials Date

! Locked Valve Deviation Log /

Initials Date CPNPP NRC 2012 JPM SA1 Procedure 2 Rev d

CPNPP NRC 2012 JPM SA1 Procedure 2 Rev d CPNPP PROCEDURE NO.

INTEGRATED PLANT OPERATING PROCEDURES MANUAL UNIT 1 IPO-010A REACTOR COOLANT SYSTEM REVISION NO. 18 REDUCED INVENTORY OPERATIONS PAGE 125 OF 195 CONTINUOUS USE ATTACHMENT 1 PAGE 2 OF 12

[C] SHIFTLY CHECKLIST CAUTION: All applicable restrictions, conditions and time after shutdown criteria specified in Attachment 15 must be met to satisfy the following requirement.

1.0 C. IF an Open RCS Cold Leg Penetration exists OR a Temporary Seal is installed on any RCS component, THEN ENSURE an adequate hot leg vent path exists per Attachment 15.

! Reactor Vessel Head detensioned or Removed (for Temporary Seals ONLY) /

Initials Date

! Pressurizer manway removed /

Initials Date

! All the Pressurizer safeties removed /

Initials Date

! One Steam Generator hot leg manway and manway diaphragm removed with its associated nozzle dam NOT installed. /

Initials Date 2.0 Containment Closure NOTE: ! Containment hatches should either be closed or capable of being closed prior to core boiling following a loss of RHR.

! Information on time to boil and time required to close the Equipment Hatch can be obtained from the Outage Control Center.

[C] A. IF the equipment hatch is removed, THEN PERFORM the following steps:

1) VERIFY the four swing bolts are in place with nuts and washers installed. /

Initials Date

2) VERIFY the gasket is in place or is available. /

Initials Date

3) VERIFY that the equipment door handling device or hoists are available for re-positioning the door, if required. /

Initials Date CPNPP NRC 2012 JPM SA1 Procedure 2 Rev d

CPNPP NRC 2012 JPM SA1 Procedure 2 Rev d CPNPP PROCEDURE NO.

INTEGRATED PLANT OPERATING PROCEDURES MANUAL UNIT 1 IPO-010A REACTOR COOLANT SYSTEM REVISION NO. 18 REDUCED INVENTORY OPERATIONS PAGE 126 OF 195 CONTINUOUS USE ATTACHMENT 1 PAGE 3 OF 12

[C] SHIFTLY CHECKLIST 2.0 A.

[C] 4) VERIFY that all lines penetrating Containment through the open equipment hatch have isolation and disconnect capability. /

Initials Date

5) RECORD the name and telephone extension of the Maintenance Supervisor/Containment Coordinator responsible for emergency equipment hatch installation.

/ /

Maintenance Supervisor/Containment Coordinator Name Ext. Initials Date

6) ENSURE a phone check has been conducted within the previous 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . /

Initials Date

7) VERIFY scaffolding is in place, as necessary, for hatch installation. /

Initials Date NOTE: ! A Containment penetration should be considered impaired if a breach exists between Containment atmosphere and outside atmosphere. Examples of impaired Containment penetrations may include:

Containment isolation valves disassembled or removed Open test connections or vents between Containment isolation valves and Containment Electrical penetrations disassembled or removed Blank flanges removed from spare penetrations Work in progress which disables the actuator for any open Containment Ventilation Isolation Valve

! The intent of this section of Attachment 1 is to ensure that Containment closure can be achieved within applicable time limits following a loss of RHR cooling. It is NOT intended that Containment operability be established, but status of the penetrations should be documented to ensure Containment operability can be established in the event of a Loss of RHR cooling.

! OPT-408A contains diagrams of all Containment penetrations. The OPT may be used as a reference when determining penetration status.

2.0 B. Containment penetrations are sealed or closed. /

Initials Date CPNPP NRC 2012 JPM SA1 Procedure 2 Rev d

CPNPP NRC 2012 JPM SA1 Procedure 2 Rev d CPNPP PROCEDURE NO.

INTEGRATED PLANT OPERATING PROCEDURES MANUAL UNIT 1 IPO-010A REACTOR COOLANT SYSTEM REVISION NO. 18 REDUCED INVENTORY OPERATIONS PAGE 127 OF 195 CONTINUOUS USE ATTACHMENT 1 PAGE 4 OF 12

[C] SHIFTLY CHECKLIST C. IF work is in progress on any Containment penetration, THEN PERFORM the following steps:

1) REVIEW penetrations being tracked per LCO 3.9.4 and RECORD or VERIFY the required information is entered on the log. /

Initials Date

[C] 2) REVIEW the work package and VERIFY that any required means for quickly sealing the penetration are available at the work site (i.e. temporary flanges).

Temporary seals must be capable of being installed within the time limits of Attachment 7. /

Initials Date CAUTION: DO NOT enter reduced inventory operations with fuel in the Reactor Vessel if more than ten penetrations are impaired and not sealed.

3) VERIFY that ten or fewer penetrations are impaired. /

Initials Date D. VERIFY that at least one door in each airlock is operable. /

Initials Date E. VERIFY 1-ALB-2B, 1.11, EMER AIRLOCK OPEN is OFF. /

Initials Date CPNPP NRC 2012 JPM SA1 Procedure 2 Rev d

CPNPP NRC 2012 JPM SA1 Procedure 2 Rev d CPNPP PROCEDURE NO.

INTEGRATED PLANT OPERATING PROCEDURES MANUAL UNIT 1 IPO-010A REACTOR COOLANT SYSTEM REVISION NO. 18 REDUCED INVENTORY OPERATIONS PAGE 128 OF 195 CONTINUOUS USE ATTACHMENT 1 PAGE 5 OF 12

[C] SHIFTLY CHECKLIST 3.0 Equipment Operability / Availability

[C] A. VERIFY the RHR heat exchanger inlet temperature <72°F above the outlet temperature for the inservice heat exchanger.

! 1-TR-612, RHR HX 1 IN TEMP/RHR HX 1 OUT TEMP /

Initials Date

! 1-TR-613, RHR HX 2 IN TEMP/RHR HX 2 OUT TEMP /

Initials Date CAUTION: ! The 6.9 KV feeder breakers for the SIPs shall remain racked out with the Reactor Vessel Head on.

! Aligning a flowpath from the RWST to the RCS may result in a level increase in the RCS due to gravity drain.

NOTE: The safety injection train is considered available even though the 6.9 KV supply breaker for the pump will remain racked out and will only be racked in if needed for emergency make-up.

[C] B. ENSURE that one train of Safety Injection is available by performing the following steps:

1) VERIFY no work in progress or active clearances associated with work activities affect the selected train availability. /

Initials Date

2) VERIFY that the 6.9 KV bus supplying the selected pump is energized. /

Initials Date

3) VERIFY that service water is available to cool the selected pump lube oil cooler. /

Initials Date CPNPP NRC 2012 JPM SA1 Procedure 2 Rev d

CPNPP NRC 2012 JPM SA1 Procedure 2 Rev d CPNPP PROCEDURE NO.

INTEGRATED PLANT OPERATING PROCEDURES MANUAL UNIT 1 IPO-010A REACTOR COOLANT SYSTEM REVISION NO. 18 REDUCED INVENTORY OPERATIONS PAGE 129 OF 195 CONTINUOUS USE ATTACHMENT 1 PAGE 6 OF 12

[C] SHIFTLY CHECKLIST 3.0 B 4) ENSURE the following conditions for valves on the selected SI train(s):

Train A

! 1/1-8821A, SIP 1 XTIE VLV OPEN OR CLOSED WITH Power Available /

Initials Date

! 1/1-8802A, SI TO HL 2 & 3 INJ CLOSED ISOL VLV WITH Power Available /

Initials Date

! 1/1-8835, SI TO CL 1!4 INJ CLOSED ISOL VLV WITH Power Available /

Initials Date Train B

! 1/1-8821B, SIP 2 XTIE VLV OPEN OR CLOSED WITH Power Available /

Initials Date

! 1/1-8802B, SI TO HL 1 & 4 INJ CLOSED ISOL VLV WITH Power Available /

Initials Date

! 1/1-8835, SI TO CL 1!4 INJ CLOSED ISOL VLV WITH Power Available /

Initials Date NOTE: Following an initial system lineup, the following check may be satisfied by reviewing the Unit Log, clearances and the system status deviation log for changes in system alignment.

5) ENSURE the remaining system valves, control switches and power supplies (except for the 6.9KV feeder breaker) are aligned for normal operation per SOP-201A. /

Initials Date CPNPP NRC 2012 JPM SA1 Procedure 2 Rev d

CPNPP NRC 2012 JPM SA1 Procedure 2 Rev d CPNPP PROCEDURE NO.

INTEGRATED PLANT OPERATING PROCEDURES MANUAL UNIT 1 IPO-010A REACTOR COOLANT SYSTEM REVISION NO. 18 REDUCED INVENTORY OPERATIONS PAGE 130 OF 195 CONTINUOUS USE ATTACHMENT 1 PAGE 7 OF 12

[C] SHIFTLY CHECKLIST NOTE: Gravity feed make-up capability from the RWST to the RCS through RHR may be used in lieu of the charging pump required by Step 3.0 C. if the availability of the flow path is documented.

3.0

[C] C. ENSURE that one centrifugal charging pump is available for emergency RCS make-up.

1) VERIFY control power is available to the RWST suction isolation valves 1/1-LCV-112D and 1/1-LCV-112E. /

Initials Date

2) VERIFY ONE of the following conditions:

! At least one CCP in operation /

Initials Date OR

! At least one CCP has been aligned for normal operation per SOP-103A. /

Initials Date D. IF an Open RCS Cold Leg Penetration Hot Leg Vent Path has been established per Attachment 15, THEN the following gravity feed flowpath may be used in lieu of the charging pump of Step 3.0 C:

1) VERIFY power is available to the following valves:

! 1/1-8812A RWST TO RHRP 1 SUCT VLV /

Initials Date

! 1/1-8812B RWST TO RHRP 2 SUCT VLV /

Initials Date

2) RWST level $55%. /

Initials Date CPNPP NRC 2012 JPM SA1 Procedure 2 Rev d

CPNPP NRC 2012 JPM SA1 Procedure 2 Rev d CPNPP PROCEDURE NO.

INTEGRATED PLANT OPERATING PROCEDURES MANUAL UNIT 1 IPO-010A REACTOR COOLANT SYSTEM REVISION NO. 18 REDUCED INVENTORY OPERATIONS PAGE 131 OF 195 CONTINUOUS USE ATTACHMENT 1 PAGE 8 OF 12

[C] SHIFTLY CHECKLIST NOTE: Step 3.0 E is not applicable when all RCS cold leg temperatures are >320°F and the following conditions are met:

! At least one reactor coolant pump is in operation, and

! Pressurizer level is # 92%, and

! The plant heatup rate is limited to 60°F in any one hour period.

3.0 E. VERIFY each accumulator is isolated when accumulator pressure is $ the maximum RCS pressure for the existing RCS cold leg temperature allowed by the P/T limit curves provided in the PTLR. (TS SR 3.4.12.3) /

Initials Date NOTE: At least two SI Accumulators should be available to inject into the RCS upon loss of RHR and potential pressurization of the RCS.

F. VERIFY at least two Safety Injection Accumulators are aligned as follows:

1) VERIFY no work in progress or active clearances associated with work activities affect the selected accumulator availability. /

Initials Date

2) Accumulator pressure between 50 psig and 100 psig and water volume available (within the indicating range):

SI ACC PRESS psig SI ACC LEVEL % /

Initials Date SI ACC PRESS psig SI ACC LEVEL % /

Initials Date CPNPP NRC 2012 JPM SA1 Procedure 2 Rev d

CPNPP NRC 2012 JPM SA1 Procedure 2 Rev d CPNPP PROCEDURE NO.

INTEGRATED PLANT OPERATING PROCEDURES MANUAL UNIT 1 IPO-010A REACTOR COOLANT SYSTEM REVISION NO. 18 REDUCED INVENTORY OPERATIONS PAGE 132 OF 195 CONTINUOUS USE ATTACHMENT 1 PAGE 9 OF 12

[C] SHIFTLY CHECKLIST 4.0 Instrumentation NOTE: When the RV Head is installed, at least two CETs should remain in service while the RCS is at reduced inventory (indicated level #80 inches above the core plate - 829'8").

The dedicated CETS may be temporarily (less than 30 minutes) disconnected as required to support RV Head disassembly and re-assembly, however, the out of service time should be minimized as much as practical. IF the RV Head has been removed, THEN Step 4.0 A. need not be performed.

[C] A. VERIFY at least one Core Exit Thermocouple from each train is in service and set up to provide alarm and indication by performing the following steps.

1) SELECT at least one CET from each train to monitor. (Circle the selected CETs.) /

Initials Date CET CORE LOCATION PLANT COMPUTER TRAIN A 1-TE-43 L-6 T7443A 1-TE-20 L-12 T7420A 1-TE-44 L-10 T7444A 1-TE-47 N-8 T7447A 1-TE-48 N-12 T7448A 1-TE-49 R-6 T7449A TRAIN B 1-TE-18 L-4 T7418A 1-TE-19 L-8 T7419A 1-TE-22 N-6 T7422A 1-TE-24 N-14 T7424A 1-TE-50 R-10 T7450A 1-TE-23 N-10 T7423A 1-TE-25 R-8 T7425A

2) SET UP or VERIFY a group trend on the Plant Computer for the selected in-service channels. /

Initials Date

3) VERIFY the Plant Computer is operable and capable of displaying selected address point numbers. /

Initials Date

4) ENSURE the high alarm for selected CETs is reset to 10°F above stable RCS temperature on the Plant Computer for the inservice thermocouples.

/ /

Technician Date Initials Date CPNPP NRC 2012 JPM SA1 Procedure 2 Rev d

CPNPP NRC 2012 JPM SA1 Procedure 2 Rev d CPNPP PROCEDURE NO.

INTEGRATED PLANT OPERATING PROCEDURES MANUAL UNIT 1 IPO-010A REACTOR COOLANT SYSTEM REVISION NO. 18 REDUCED INVENTORY OPERATIONS PAGE 133 OF 195 CONTINUOUS USE ATTACHMENT 1 PAGE 10 OF 12

[C] SHIFTLY CHECKLIST

5) VERIFY the selected CETs are within 10°F of the active RHR heat exchanger inlet temperature and all indicate less than 150°F.

! 1-TR-612, RHR HX 1 IN/OUT TEMP /

Initials Date

! 1-TR-613, RHR HX 2 IN/OUT TEMP /

Initials Date CPNPP NRC 2012 JPM SA1 Procedure 2 Rev d

CPNPP NRC 2012 JPM SA1 Procedure 2 Rev d CPNPP PROCEDURE NO.

INTEGRATED PLANT OPERATING PROCEDURES MANUAL UNIT 1 IPO-010A REACTOR COOLANT SYSTEM REVISION NO. 18 REDUCED INVENTORY OPERATIONS PAGE 134 OF 195 CONTINUOUS USE ATTACHMENT 1 PAGE 11 OF 12

[C] SHIFTLY CHECKLIST 4.0 B. VERIFY the following instruments are in-service with operable control room indication and alarm.

Indication Alarm Window Q 1) 1-FI-618, RHR TO CL 1&2 INJ FLO 1-ALB-4B, 4.4 Q 2) 1-FI-619, RHR TO CL 3&4 INJ FLO 1-ALB-4B, 4.4 Q 3) 1-PI-614, RHRP 1 DISCH PRESS 1-ALB-4B, 3.4 Q 4) 1-PI-615, RHRP 2 DISCH PRESS 1-ALB-4B, 3.4 Q 5) 1-TR-612, RHR HX 1 IN TEMP/RHR HX 1 OUT TEMP N/A Q 6) 1-TR-613, RHR HX 2 IN TEMP/RHR HX 2 OUT TEMP N/A Q 7) 1-LI-3615A, RX VSL LVL (NR) N/A Q 8) 1-LI-3615B, RX VSL LVL (WR) N/A Q 9) 1-TI-413A, HL 1 TEMP (WR) N/A Q 10) 1-TR-433A/43A, HL 4 TEMP (WR) N/A Q 11) EMER AIRLOCK OPEN 1-ALB-2B, 1.11 Q 12) RHRP 1/2 MOT CURRENT FLUCTUATION 1-ALB-4B, 2.2 Q 13) RHRP 1/2 RWST & HL SUCT XTIED 1-ALB-4B, 2.5 Q 14) RCS MID LOOP LVL LO 1-ALB-4B, 2.8 Q 15) RHRP 1/2 SUCT PRESS LO 1-ALB-4B, 3.2 Q 16) RHR PUMP 1 SUCTION VALVES NOT FULLY OPEN 1-ALB-4B, 3.8 Q 17) RHR PUMP 2 SUCTION VALVES NOT FULLY OPEN 1-ALB-4B, 4.8 Q 18) 1-PI-601A RHRP 1 SUCT PRESS N/A Q 19) 1-PI-602A RHRP 2 SUCT PRESS N/A Q 20) 1-LI-3615C, RX VSL LVL (EWR) Plant Computer Instruments verified /

Initials Date CPNPP NRC 2012 JPM SA1 Procedure 2 Rev d

CPNPP NRC 2012 JPM SA1 Procedure 2 Rev d CPNPP PROCEDURE NO.

INTEGRATED PLANT OPERATING PROCEDURES MANUAL UNIT 1 IPO-010A REACTOR COOLANT SYSTEM REVISION NO. 18 REDUCED INVENTORY OPERATIONS PAGE 135 OF 195 CONTINUOUS USE ATTACHMENT 1 PAGE 12 OF 12

[C] SHIFTLY CHECKLIST 4.0 C. DETERMINE the RCS heat-up rate and time to saturation from Attachment 8 prior to reload (after reload the chart will not be accurate) or the OCC and RECORD below.

ESTIMATED HEAT-UP RATE TIME TO SATURATION TIME/DATE °F/min minutes

/

Initials Date Attachment 1 Completed and Reviewed: / /

Shift Manager Date Time CPNPP NRC 2012 JPM SA1 Procedure 2 Rev d

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SA2 Task # SO1058 K/A # 2.1.23 4.3 / 4.4

Title:

Perform a Calorimetric Heat Balance and Evaluate Technical Specifications Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

A Unit 1 Calorimetric is required.

The Plant Computer is unavailable for use.

All Prerequisites have been completed.

OPT-309-2, Calorimetric Data Reduction Worksheet, has been completed through Step 8.2.2.8 by a Reactor Operator.

An additional Reactor Operator has performed an independent review of all data and calculations and confirmed the calculation is correct.

Initiating Cue: The Shift Manager directs you to PERFORM the following:

COMPLETE OPT-309, Calorimetric Heat Balance, Section 8.2, Manual Calorimetric Calculation, using OPT-309-2, Calorimetric Data Reduction Worksheet.

START at Step 8.2.2.9.

When completed, IDENTIFY any Technical Specification Surveillance Requirements and RECORD in the Comments Section of OPT-309-2, Calorimetric Data Reduction Worksheet.

Task Standard: Utilizing OPT-309, OPT-309-2, and OPT-309-11 calculated a Unit 1 calorimetric.

Utilizing Technical Specifications, identified and recorded LCO 3.3.1 Surveillance Requirement 3.3.1.2.

Required Materials: OPT-309, Unit Calorimetric, Rev 14.

OPT-309-2, Calorimetric Data Reduction Worksheet, Rev 8.

OPT-309-11, Unit 1 Calorimetric Data Sheet, Rev 6.

Unit 1 Technical Specifications, Amendment 154.

Validation Time: 25 minutes Completion Time: ________ minutes Page 1 of 7 CPNPP NRC 2012 JPM SA2 Rev d.docx

Appendix C JPM WORKSHEET Form ES-C-1 Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 2 of 7 CPNPP NRC 2012 JPM SA2 Rev d.docx

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of:

OPT-309, Unit Calorimetric, completed through Step 8.2.2.8.

OPT-309-2, Calorimetric Data Reduction Worksheet, completed through Step 8.2.2.8.

OPT-309-11, Unit 1 Calorimetric Data Sheet with data entered.

Unit 1 Technical Specifications.

Steam Tables.

Calculator.

Page 3 of 7 CPNPP NRC 2012 JPM SA2 Rev d.docx

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from OPT-309, Section 8.2.

Perform Step: 1 Perform Steam Generator Enthalpy Rise Calculation as follows:

8.2.2.9, 8.2.2.9.A, & Enter corrected steam pressures given in column 5 of Step 8.2.2.9.B 8.2.2.5, in column 2.

Using Steam Tables obtain the steam enthalpies AND enter results in column 3.

Standard: CALCULATED Steam Generator Enthalpy Rise using corrected steam pressures (PSIA) then CALCULATED associated steam enthalpy values using Steam Tables and ENTERED data on OPT-309-2.

Comment: SAT UNSAT Perform Step: 2 Perform Steam Generator Enthalpy Rise Calculation as follows:

8.2.2.9, 8.2.2.9.C, Enter feedwater enthalpy from one of the following sources:

8.2.2.9.C 2nd bullet, &

8.2.2.9.D IF Steam Generator Blowdown NOT isolated, THEN enter value given in column 2 of Step 8.2.2.8 into column 3, or Using Steam Tables obtain the enthalpy of the feedwater liquid AND enter result in column 4.

Subtract the value in column 4 from values in column 3 AND enter the results in column 5.

Standard: CALCULATED Feedwater Enthalpy using Steam Tables then SUBTRACTED value in column 4 from values in column 3 and ENTERED data on OPT-309-2.

Comment: SAT UNSAT Page 4 of 7 CPNPP NRC 2012 JPM SA2 Rev d.docx

Appendix C JPM STEPS Form ES-C-1 Perform Step: 3 Perform Steam Generator Heat Gain Calculation as follows:

8.2.2.10, 8.2.2.10.A, Enter the enthalpy rise for each Steam Generator given in column 8.2.2.10.B, 8.2.2.10.C, 5 of Step 8.2.2.9, into column 2.

& 8.2.2.10.D Calculate steam flow for each Steam Generator by using the formula given in the heading of column 3. Use data for Feedwater flow given in column 4 of Step 8.2.2.4 AND blowdown flow given in column 3 of Step 8.2.2.7. Enter results in column 3.

Multiply the entries in column 2 by entries in column 3, AND enter results in column 4.

Total the entries of column 4 and enter result at the base of this column.

Standard: CALCULATED Steam Generator Heat Gain; RECORDED enthalpy rise for each Steam Generator then RECORDED steam flow for each Steam Generator then MULTIPLIED the entries in column 2 by entries in column 3, and ENTERED results in column 4 then TOTALED the entries and ENTERED data on OPT-309-2.

Comment: SAT UNSAT Perform Step: 4 Perform Percent Rated Thermal Power Calculation as follows:

8.2.2.11, 8.2.2.11.A, Enter the Steam Generator Heat Gain given in space at the base 8.2.2.11.B, 8.2.2.11.C, of column 4 from Step 8.2.2.10, in column 1.

& 8.2.2.11.D IF Steam Generator Blowdown NOT isolated, THEN enter the Blowdown Heat Loss given in column 3 of Step 8.2.2.8, in column 2.

Calculate Net Reactor Power by using the formula given in the heading of column 4 AND the data given in columns 1, 2 and 3.

Enter results in column 4.

Substitute values from column 4 and column 5 into the formula in the heading of column 6 AND calculate Percent Rated Thermal Power. Enter the result in column 6.

Standard: CALCULATED Percent Rated Thermal Power using Steam Generator Heat Gain then CALCULATED Net Reactor Power value then SUBSTITUTED values and CALCULATED Percent Rated Thermal Power and ENTERED data on OPT-309-2.

CALCULATED a Percent Rated Thermal Power of 94 +/- 1.0%.

Comment: SAT UNSAT Page 5 of 7 CPNPP NRC 2012 JPM SA2 Rev d.docx

Appendix C JPM STEPS Form ES-C-1 Examiner Note: The following step is from Technical Specification LCO 3.3.1.

Perform Step: 5 IDENTIFY any Technical Specification Surveillance Requirements and RECORD in the Comments Section of OPT-309-2, Calorimetric Data Reduction Worksheet.

Standard: REVIEWED OPT-309-11, Unit 1 Calorimetric Data Sheet and IDENTIFIED Technical Specification LCO 3.3.1 Surveillance Requirement 3.3.1.2 and RECORDED the following in the Comments Section of OPT-309-2, Calorimetric Data Reduction Worksheet:

Adjust NIS Power Range channel outputs if calorimetric heat balance calculation exceeds NIS Power Range channel outputs by more than +2% RTP within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 6 of 7 CPNPP NRC 2012 JPM SA2 Rev d.docx

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

A Unit 1 Calorimetric is required.

The Plant Computer is unavailable for use.

All Prerequisites have been completed.

OPT-309-2, Calorimetric Data Reduction Worksheet, has been completed through Step 8.2.2.8 by a Reactor Operator.

An additional Reactor Operator has performed an independent review of all data and calculations and confirmed the calculation is correct.

INITIATING CUE: The Shift Manager directs you to PERFORM the following:

COMPLETE OPT-309, Calorimetric Heat Balance, Section 8.2, Manual Calorimetric Calculation, using OPT-309-2, Calorimetric Data Reduction Worksheet.

START at Step 8.2.2.9.

When completed, IDENTIFY any Technical Specification Surveillance Requirements and RECORD in the Comments Section of OPT-309-2, Calorimetric Data Reduction Worksheet.

Page 7 of 7 CPNPP NRC 2012 JPM SA2 Rev d.docx

CPNPP NRC 2012 JPM SA2 Answer Key Rev d CALORIMETRIC DATA REDUCTION WORKSHEET Unit 1 Date Today 8.2.2.2 - Feedwater Average Temperature Parameter Average Value of Overall Data Sets Average

(°F) (°F)

S/G 1 Feedwater Temperature 440 S/G 2 Feedwater Temperature 440 440 S/G 3 Feedwater Temperature 440 S/G 4 Feedwater Temperature 440 8.2.2.3 Feedwater Average Pressure Parameter Average of Data Sets Corrected Pressure Overall Average (PSIG) (PSIG + 14.7 = PSIA) (PSIA)

S/G 1 Feedwater Pressure 1160 1175 S/G 2 Feedwater Pressure 1160 1175 1175 S/G 3 Feedwater Pressure 1160 1175 S/G 4 Feedwater Pressure 1160 1175 8.2.2.4 - Feedwater Flow Averages Parameter Average Value of Correction Factor Corrected Value (WF) Data Sets (CF) LB/HR x CF (LB/HR) (NOTE 1) (LB/HR)

S/G 1 Feedwater Flow 3.8xE6 1.0 3.8xE6 S/G 2 Feedwater Flow 3.8xE6 1.0 3.8xE6 S/G 3 Feedwater Flow 3.8xE6 1.0 3.8xE6 S/G 4 Feedwater Flow 3.8xE6 1.0 3.8xE6 8.2.2.5 - Corrected Steam Generator Steam Pressure Averages Parameter Average of Corrected Pressure Pressure Drop Due to Corrected Overall Data Sets Line Loss (PSIA) Pressure Average (PSIG) (PSIG+14.7 = PSIA) (NOTE 2) (PSIA) (PSIA)

S/G 1 Steam Pressure 979.7 994.4 5.55 999.95 979.4 994.1 999.98 1000 S/G 2 Steam Pressure 5.88 S/G 3 Steam Pressure 978.4 993.1 7.04 1000.14 S/G 4 Steam Pressure 979.1 993.8 6.13 999.93 NOTE 1: Correction Factor is 1 when LEFM data is used. When other Feedwater Flow data is used, Correction Factor is from Attachment 10.1 using Feedwater Temperature for the associated SG calculated in Step 8.2.2.2 (Column 2).

NOTE 2: The steam line pressure drops are the same for both Units.

OPT-309-2 CPNPP NRC 2012 JPM SA2 Answer Key Rev d REV. 8 PAGE 1 OF 3

CPNPP NRC 2012 JPM SA2 Answer Key Rev d CALORIMETRIC DATA REDUCTION WORKSHEET 8.2.2.6 - Steam Generator Blowdown Average Values Parameter Average Value of Data Sets SG Blowdown Flow (GPM) 335 SG Blowdown Hx Out Temp (°F) 250 8.2.2.7 - Blowdown Flow Conversion Average Specific Blowdown Flow, Fbd Blowdown Volume, V Flow, F (GPM) FT3/lbm (LBM/HR) 335 0.0170 161967 8.2.2.8 - Blowdown Heat Loss Calculation Blowdown Enthalpy, Feedwater Enthalpy, Blowdown Heat Loss, Qbd (BTU/LBM) (BTU/LBM) (BTU/HR) 542.6 419.9 19873351 8.2.2.9 - S/G Enthalpy Rise Calculation SG No. Corrected Steam Feedwater Enthalpy Steam Enthalpy, Enthalpy, Rise Pressure (PSIA)

(BTU/LBM) (BTU/LBM) (BTU/LBM) 1 1000 1192.9 773 2 1000 1192.9 773 419.9 3 1000 1192.9 773 4 1000 1192.9 773 OPT-309-2 CPNPP NRC 2012 JPM SA2 Answer Key Rev d REV. 8 PAGE 2 OF 3

CPNPP NRC 2012 JPM SA2 Answer Key Rev d CALORIMETRIC DATA REDUCTION WORKSHEET 8.2.2.10 - SG Heat Gain Calculation SG No. Enthalpy Rise, Steam Flow S/G Heat Gain, (BTU/LBM) (LBM/HR) (BTU/HR) 1 773 3,759,508 2,906,099,877 2 773 3,759,508 2,906,099,877 3 773 3,759,508 2,906,099,877 4 773 3,759,508 2,906,099,877 1.1624xE10 8.2.2.11 - Percent Rated Thermal Power Calculation SG Blowdown Non-Reactor Net Reactor Rated Percent Rated Heat Heat Loss, Heat Gains, Power, Thermal Thermal Power Gain Power, (BTU/HR) (BTU/HR) (BTU/HR) (BTU/HR) (BTU/HR) (%)

1.1624xE10 19873351 5.4 X 107 1.1590xE10 1.2328 x10 10 94.02 Comments: Adjust NIS Power Range channel outputs if calorimetric heat balance calculation exceeds NIS Power Range channel outputs by more

+2% RTP within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Performed By: Date:

Reviewed By: Date:

OPT-309-2 CPNPP NRC 2012 JPM SA2 Answer Key Rev d REV. 8 PAGE 3 OF 3

CPNPP NRC 2012 JPM SA2 Form 1 Rev d CPNPP NRC 2012 JPM SA2 Form 1 Rev d

CPNPP NRC JPM SA2 Procedure Rev d CPNPP NRC JPM SA2 Procedure Rev d

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SA3 Task # SO1202 K/A # 2.2.12 3.7 / 4.1

Title:

Perform Control Room Air Conditioning System Surveillance Data and Evaluate Technical Specifications Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

Both Units are operating at 100% power with all controls in Automatic.

Train B Control Room Air Conditioning System is being tested per OPT-116, CR AC SYSTEM.

The 30 minute run time since completion of the Prerequisites is complete.

The following parameters are observed:

CR A/C UNIT 03- X-PI-3585A reads 150 psig and is operating 50%

unloaded.

CR A/C UNIT 04 -X-PI-3586A reads 160 psig and is operating 0%

unloaded.

X-TR-4123 reads 80°F.

X-TI-5933 reads 72°F.

X-TI-5734 reads 73°F.

X-TI-5735 reads 73°F.

Initiating Cue: The Shift Manager directs you to PERFORM the following:

COMPLETE the Control Room Air Conditioning System surveillance per OPT-116, CR AC SYSTEM.

RECORD and COMPLETE all data on OPT-116-1, CR AC System Data Sheet.

If required, IDENTIFY any Technical Specification LCO CONDITION, REQUIRED ACTION, and COMPLETION TIME and record in Comments Section of surveillance.

Task Standard: Utilizing OPT-116, recorded collected data on OPT-116-1, plotted air conditioning unit cooling capacity, and determined Acceptance Criteria NOT met. Identified Technical Specification LCO 3.7.11 CONDITION, REQUIRED ACTION, and COMPLETION TIME and recorded in Comments Section of surveillance.

Page 1 of 8 CPNPP NRC 2012 JPM SA3 Rev d.docx

Appendix C JPM WORKSHEET Form ES-C-1 Required Materials: OPT-116, CR AC System, Rev. 4.

OPT-116-1, CR AC System Data Sheet, Rev. 4.

Unit 1 Technical Specifications, Amendment 154.

Validation Time: 30 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 2 of 8 CPNPP NRC 2012 JPM SA3 Rev d.docx

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee with a copy of:

OPT-116, CR AC System.

INITIAL and N/A as appropriate up to Step 8.3.

OPT-116-1, CR AC System Data Sheet.

INITIAL and N/A as appropriate up to Step 8.3 Page 3 of 8 CPNPP NRC 2012 JPM SA3 Rev d.docx

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from OPT-116, Section 8.3.

Perform Step: 1 RECORD the following:

st 8.3 & 1 bullet X-TR-4123, outside temperature (10M PRI) (X-CV-05)

Standard: RECORDED X-TR-4123, outside temperature of 80°F on OPT-116-1 and INITIALED.

Comment: SAT UNSAT Perform Step: 2 RECORD the following:

nd 8.3 & 2 bullet X-TI-5933 ECB EXH TEMP (X-CV-01)

Standard: RECORDED X-TI-5933, ECB EXH TEMP of 72°F, on OPT-116-1 and COMPARED to Required Test Conditions of 60 degrees and INITIALED.

Comment: SAT UNSAT Perform Step: 3 RECORD the following:

8.3 & 3rd bullet X-TI-5734, AB EXH TEMP EL-852' 6" (X-CV-03)

Standard: RECORDED X-TI-5734, AB EXH TEMP of 73°F on OPT-116-1 and COMPARED to Required Test Conditions of 60 degrees and INITIALED.

Comment: SAT UNSAT Perform Step: 4 RECORD the following:

8.3 & 4th bullet X-TI-5735, AB EXH TEMP EL-831' 6" (X-CV-03)

Standard: RECORDED X-TI-5735, AB EXH TEMP of 73°F, on OPT-116-1 and COMPARED to Required Test Conditions of 60 degrees and INITIALED.

Comment: SAT UNSAT Page 4 of 8 CPNPP NRC 2012 JPM SA3 Rev d.docx

Appendix C JPM STEPS Form ES-C-1 Perform Step: 5 RECORD the following:

8.3 & 5th bullet Compressor discharge pressures for operating A/C units.

CR A/C Unit 03 (X-PI-3585A)

Standard: RECORDED CR A/C Unit 03 (X-PI-3585A) pressure of 150 psig on OPT-116-1 and COMPARED to Required Test Conditions of < 170 psig and INITIALED.

Comment: SAT UNSAT Perform Step: 6 RECORD the following:

8.3 & 5th bullet Compressor discharge pressures for operating A/C units CR A/C Unit 04 (X-PI-3586A)

Standard: RECORDED CR A/C Unit 04 (X-PI-3586A) pressure of 160 psig on OPT-116-1 and COMPARED to Required Test Conditions of < 170 psig and INITIALED.

Comment: SAT UNSAT Perform Step: 7 VERIFY the above readings are within the specified limits. If any of the 8.4 above readings are NOT within the specified limits, this test should be terminated and restarted when the above conditions can be met.

Standard: VERIFIED that all readings are within limits and INITIALED.

Comment: SAT UNSAT Perform Step: 8 RECORD % unloaded (lights on A/C Unit Control Panel) for both 8.5 operating A/C units.

A/C UNIT 03 Standard: RECORDED A/C UNIT 03 % unloaded of 50% on OPT-116-1 and INITIALED.

Comment: SAT UNSAT Perform Step: 9 RECORD % unloaded (lights on A/C Unit Control Panel) for both 8.5 operating A/C units.

A/C UNIT 04 Standard: RECORDED A/C UNIT 04 % unloaded of 0% on OPT-116-1 and INITIALED.

Comment: SAT UNSAT Page 5 of 8 CPNPP NRC 2012 JPM SA3 Rev d.docx

Appendix C JPM STEPS Form ES-C-1 Perform Step: 10 CALCULATE the average % unloaded by adding the % unloaded from 8.6 the operating compressors and dividing by 2.

Standard: ADDED 50% and 0% and DIVIDED by 2 to yield an average of 25%;

RECORDED on OPT-116-1 and INITIALED.

Comment: SAT UNSAT Perform Step: 11 Using outside temperature (Step 8.3) and the calculated average 8.7 compressor cooling capacity availability (Step 8.6), VERIFY operation is above the curve (Figure 1) in the data sheet, AND RECORD test results.

Standard: PLOTTED the intersection point for 80°F and 25% on Figure 1 and COMPARED to the acceptability curve.

Comment: SAT UNSAT Perform Step: 12 Using outside temperature (Step 8.3) and the calculated average 8.7 compressor cooling capacity availability (Step 8.6), VERIFY operation is above the curve (Figure 1) in the data sheet, AND RECORD test results.

Standard: VERIFIED plotted point is BELOW the curve on Figure 1 and CIRCLED BELOW then UNSAT on OPT-116-1 and INITIALED.

Comment: SAT UNSAT Page 6 of 8 CPNPP NRC 2012 JPM SA3 Rev d.docx

Appendix C JPM STEPS Form ES-C-1 Examiner Note: The following is from Technical Specification LCO 3.7.11.

Perform Step: 13 RECORD any required Technical Specification CONDITION, REQUIRED ACTION, and COMPLETION TIME in the Comments Section of the Surveillance.

Standard: DETERMINED entry into Technical Specification LCO 3.7.11, Control Room Air Conditioning System (CRACS):

CONDITION A - One CRACS train inoperable; REQUIRED ACTION A.1 - Restore CRACS train to OPERABLE status.

COMPLETION TIME - Within 30 days.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 7 of 8 CPNPP NRC 2012 JPM SA3 Rev d.docx

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

Both Units are operating at 100% power with all controls in Automatic.

Train B Control Room Air Conditioning System is being tested per OPT-116, CR AC SYSTEM.

The 30 minute run time since completion of the Prerequisites is complete.

The following parameters are observed:

CR A/C UNIT 03- X-PI-3585A reads 150 psig and is operating 50% unloaded.

CR A/C UNIT 04 -X-PI-3586A reads 160 psig and is operating 0% unloaded.

X-TR-4123 reads 80°F.

X-TI-5933 reads 72°F.

X-TI-5734 reads 73°F.

X-TI-5735 reads 73°F.

INITIATING CUE: The Shift Manager directs you to PERFORM the following:

COMPLETE the Control Room Air Conditioning System surveillance per OPT-116, CR AC SYSTEM.

RECORD and COMPLETE all data on OPT-116-1, CR AC System Data Sheet.

If required, IDENTIFY any Technical Specification LCO CONDITION, REQUIRED ACTION, and COMPLETION TIME and record in Comments Section of surveillance.

Page 8 of 8 CPNPP NRC 2012 JPM SA3 Rev d.docx

CPNPP NRC 2012 JPM SA3 Answer Key 1 Rev d CR A/C SYSTEM DATA SHEET REQUIRED TEST STEP OBSERVED CONDITIONS INITIALS 6.0 PREREQUISITES MET N/A N/A RB AND TIME/DATE Today @ 0800 N/A RB 8.1 CR A/C UNITS BEING TESTED Units 03 & 04 N/A RB Today @ 0900 $30 MIN RB 8.2 TIME AND DATE PAST STEP 6.0 8.3 RECORD THE FOLLOWING:

! X-TR-4123 OUTSIDE TEMPERATURE 80 F N/A RB

! X-TI-5933 72 F $60°F RB

! 73 F RB X-TI-5734 $60°F

! 73 F RB X-TI-5735 $60°F

! COMPRESSOR DISCHARGE PRESSURES (N/A for shutdown units)

CR A/C UNIT 01 (X-PI-3583A) N/A <170 PSIG N/A CR A/C UNIT 02 (X-PI-3584A)

N/A <170 PSIG N/A CR A/C UNIT 03 150 psig (X-PI-3585A) <170 PSIG RB CR A/C UNIT 04 (X-PI-3586A) 160 psig <170 PSIG RB 8.4 ALL ABOVE REQUIRED TEST CONDITIONS MET N/A NOTE 1 RB NOTE 1: If test conditions are not met, terminate test at this point. Test shall be restarted when conditions can be met.

CONTINUOUS USE OPT-116-1 PAGE 1 OF 4 R-4 CPNPP NRC 2012 JPM SA3 Answer Key 1 Rev d

CPNPP NRC 2012 JPM SA3 Answer Key 1 Rev d CR A/C SYSTEM DATA SHEET STEP OBSERVED INITIALS 8.5 A/C UNIT % UNLOADED (N/A for shutdown units)

A/C UNIT 01 N/A N/A A/C UNIT 02 N/A N/A A/C UNIT 03 50 RB A/C UNIT 04 0 RB 8.6 CALCULATE AVERAGE A/C UNIT NO. 03 A/C UNIT NO. 04 RB

% UNLOADED 50 + % UNLOADED 0 = 25 2 TRAIN AVERAGE N/A COMPRESSOR COOLING VERIFIED CAPACITY AVAILABILITY 8.7 COMPARE OUTSIDE TEMP (STEP 8.3) AND AVERAGE OPERATION COMPRESSOR COOLING CAPACITY AVAILABILITY ABOVE/BELOW (STEP 8.6) TO CURVE (FIGURE 1) CURVE RB ACCEPTANCE CRITERIA SAT IF OPERATION IS ABOVE CURVE SAT/UNSAT RB CONTINUOUS USE OPT-116-1 PAGE 2 OF 4 R-4 CPNPP NRC 2012 JPM SA3 Answer Key 1 Rev d

CPNPP NRC 2012 JPM SA3 Answer Key 1 Rev d CR A/C SYSTEM DATA SHEET FIGURE 1 OUTSIDE PERCENT UNLOADED TEMPERATURE 16.7 110 24.3 100 32.0 90 39.6 80 47.2 70 51.7 60 54.1 50 56.5 40 58.9 30 61.3 20 CONTROL ROOM HVAC MINIMUM REQUIRED AVAILABILITY THE UNLOADED COMBINED AVERAGE OF THE TWO 50% CONTROL ROOM HVAC UNITS MUST BE ABOVE THE CURVE REPRESENTED BELOW:

COOLING CAPACITY AVAILABLE (%)

70 60 50 40 30 20 10 0

0 10 20 30 40 50 60 70 80 90 100 110 120 OUTSIDE TEMPERATURE (F)

CONTINUOUS USE OPT-116-1 PAGE 3 OF 4 R-4 CPNPP NRC 2012 JPM SA3 Answer Key 1 Rev d

CPNPP NRC 2012 JPM SA3 Answer Key 1 Rev d CR A/C SYSTEM DATA SHEET COMMENTS/DISCREPANCIES:

Technical Specification LCO 3.7.11, Control Room Air Conditioning System (CRACS)

CONDITION A - One CRACS train inoperable

REQUIRED ACTION A.1 - Restore CRACS train to OPERABLE status.

COMPLETION TIME - Within 30 days.

CORRECTIVE ACTIONS:

PERFORMED BY: DATE:

SIGNATURE REVIEWED BY: DATE:

OPERATIONS MANAGEMENT CONTINUOUS USE OPT-116-1 PAGE 4 OF 4 R-4 CPNPP NRC 2012 JPM SA3 Answer Key 1 Rev d

CPNPP NRC 2012 JPM SA3 Answer Key 2 Rev d CRACS 3.7.11 3.7 PLANT SYSTEMS 3.7.11 Control Room Air Conditioning System (CRACS)

LCO 3.7.11 Two CRACS trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, 4, 5, and 6, During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CRACS train A.1 Restore CRACS train to OPERABLE 30 days inoperable. status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not met AND in MODE 1, 2, 3, or 4.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. Required Action and C.1 Place OPERABLE CRACS train in Immediately associated Completion operation.

Time of Condition A not met in MODE 5, or 6, or during OR movement of irradiated fuel assemblies. C.2.1 Suspend CORE ALTERATIONS. Immediately AND C.2.2 Suspend movement of irradiated Immediately fuel assemblies.

COMANCHE PEAK - UNITS 1 AND 2 3.7-26 Amendment No. 150 CPNPP NRC 2012 JPM SA3 Answer Key 2 Rev d

CPNPP NRC 2012 JPM SA3 Form Rev d CPNPP NRC 2012 JPM SA3 Form Rev d

CPNPP NRC 2012 JPM SA3 Procedure Rev d CPNPP NRC 2012 JPM SA3 Procedure Rev d

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SA4 Task # SO1005 K/A # 2.3.13 3.4 / 3.8

Title:

Determine Containment Stay Time Requirements and Event Reportability Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

JPM Cue Sheet #1 A Containment entry is about to be performed by a 4 member team.

The estimated gamma dose rate is 75 mrem/hr.

The estimated neutron dose rate is 10 mrem/hr.

Health Physics has limited the total gamma dose received by the team to 0.5 person-REM.

Health Physics has limited the total neutron dose received by the team to 0.05 person-REM.

The Safety Supervisor has performed a heat stress evaluation and all personnel will be wearing ice vests.

The Heat Stress Action Time has been determined to be 40 minutes.

Initiating Cue: The Work Control Supervisor directs you to PERFORM the following:

JPM Cue Sheet #1 CALCULATE the following:

Gamma dose stay time per team. _____ minutes.

Neutron dose stay time per team. _____ minutes.

Heat Stress Stay Time _____ minutes.

DETERMINE the most limiting allowable time for the Containment entry team based on ALARA and Heat Stress:

Limiting Containment entry time: _____ minutes.

Initial Conditions: Given the following conditions:

JPM Cue Sheet #2 The Shift Manager was notified by Radiation Protection that a member of the Containment entry team was injured and contaminated.

The individual is in route to the hospital.

Initiating Cue: The Shift Manager directs you to PERFORM the following:

JPM Cue Sheet #2 DETERMINE Oral Reportability Requirements, if any.

Oral Reporting Requirement _______________

Page 1 of 7 CPNPP NRC 2012 JPM SA4 Rev d.docx

Appendix C JPM WORKSHEET Form ES-C-1 Task Standard: Utilizing STA-620/655/657/660/674, calculated gamma and neutron dose stay times for the team, Heat Stress Stay Time, and determined limiting Containment entry time.

Utilizing STA-501, determined oral Reporting Requirements for a contaminated injured person.

Required Materials: STA-501, Nonroutine Reporting, Rev. 15-3.

STA-620, Containment Entry, Rev. 13.

STA-655, Exposure Monitoring Program, Rev. 20.

STA-657, ALARA Job Planning/Debriefing, Rev. 14.

STA-660, Control of High Radiation Areas, Rev. 15.

STA-674, Heat Stress Management, Rev. 8.

Validation Time: 25 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 2 of 7 CPNPP NRC 2012 JPM SA4 Rev d.docx

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

PROVIDE the examinee JPM Cue Sheet #1 and MAKE the following available in the classroom:

STA-501, Nonroutine Reporting.

STA-620, Containment Entry.

STA-655, Exposure Monitoring Program.

STA-657, ALARA Job Planning/Debriefing.

STA-660, Control of High Radiation Areas.

STA-674, Heat Stress Management.

ENSURE examinee has a calculator.

When JPM Cue Sheet #1 is completed, PROVIDE JPM Cue Sheet #2.

Page 3 of 7 CPNPP NRC 2012 JPM SA4 Rev d.docx

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: Provide the examinee with copy of JPM Cue Sheet #1.

Perform Step: 1 Calculate gamma dose stay time per team.

Standard: CALCULATED the following:

75 mrem/hr gamma x 4 persons = 300 mrem/hr from gamma.

500 person-REM allowed 100 minute gamma Stay Time Comment: SAT UNSAT Perform Step: 2 Calculate neutron dose stay time per team.

Standard: CALCULATED the following:

10 mrem/hr neutron x 4 persons = 40 mrem/hr from neutron.

50 person-REM allowed 75 minute neutron Stay Time Comment: SAT UNSAT Examiner Note: The following step is from STA-674, Section 4.0, Definitions.

Perform Step: 3 Calculate Heat Stress Stay Time.

Standard: CALCULATED the following:

Heat Stress Action Time is 40 minutes per the Initial Conditions.

Heat Stress Stay Time is 2 x 40 minutes = 80 minutes Comment: SAT UNSAT Perform Step: 4 Determine limiting Containment entry time.

Standard: DETERMINED the limiting Containment entry time is 75 minutes based on Neutron Dose Stay Time.

Comment: SAT UNSAT Page 4 of 7 CPNPP NRC 2012 JPM SA4 Rev d.docx

Appendix C JPM STEPS Form ES-C-1 Examiner Note: Provide the examinee with copy of JPM Cue Sheet #2.

Examiner Note: The following steps are from STA-501, Attachment 8.D/13.

Perform Step: 5 Determine oral Reporting Requirements per STA-501. .D/13 Page 9 of 17 Standard: DETERMINED oral Reporting Requirements per STA-501:

Any event requiring the transport of a radioactively contaminated person to an off-site medical facility for treatment.

Oral Report within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Examiner Note: Answer in bold print.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 5 of 7 CPNPP NRC 2012 JPM SA4 Rev d.docx

Appendix C JPM CUE SHEET #1 Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

A Containment entry is about to be performed by a 4 member team.

The estimated gamma dose rate is 75 mrem/hr.

The estimated neutron dose rate is 10 mrem/hr.

Health Physics has limited the total gamma dose received by the team to 0.5 person-REM.

Health Physics has limited the total neutron dose received by the team to 0.05 person-REM.

The Safety Supervisor has performed a heat stress evaluation and all personnel will be wearing ice vests.

The Heat Stress Action Time has been determined to be 40 minutes.

INITIATING CUE: The Work Control Supervisor directs you to PERFORM the following:

CALCULATE the following:

Gamma dose stay time per team. _____ minutes.

Neutron dose stay time per team. _____ minutes.

Heat Stress Stay Time _____ minutes.

DETERMINE the most limiting allowable time for the Containment entry team based on ALARA and Heat Stress:

Limiting Containment entry time: _____ minutes.

Page 6 of 7 CPNPP NRC 2012 JPM SA4 Rev d.docx

Appendix C JPM CUE SHEET #2 Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

The Shift Manager was notified by Radiation Protection that a member of the Containment entry team was injured and contaminated.

The individual is in route to the hospital.

INITIATING CUE: The Shift Manager directs you to PERFORM the following:

DETERMINE Oral Reportability Requirements, if any.

Oral Reporting Requirement _______________

Page 7 of 7 CPNPP NRC 2012 JPM SA4 Rev d.docx

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d COMANCHE PEAK NUCLEAR POWER PLANT l STATION ADMINISTRATION MANUAL FOR EMPLOYEE USE: l DATE VERIFIED/INITIALS / LATEST PCN/EFFECTIVE DATE NA / l LEVEL OF USE: l INFORMATION USE l QUALITY RELATED CONTAINMENT ENTRY PROCEDURE NO. STA-620 REVISION NO. 13 SORC MEETING NO. #12-002 DATE: 1/30/12 EFFECTIVE DATE: 2/09/12 MAJOR REVISION l PREPARED BY (Print): AMY DOWELL EXT. 5272 TECHNICAL REVIEW BY (Print): RON CUTLIP EXT. 8228 APPROVED BY: STEVE SMITH DATE: 2/2/12 PLANT MANAGER CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 2 OF 37 l TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2.0 APPLICABILITY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4

3.0 REFERENCES

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 4.0 DEFINITIONS/ACRONYMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 5.0 RESPONSIBILITIES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 6.0 INSTRUCTIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 6.1 Precautions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 6.2 Containment Entry Requirements Non-Emergency . . . . . . . . . . . . . . . . . . . . . 18 l 6.3 Emergency Containment Entry Requirements . . . . . . . . . . . . . . . . . . . . . . . . . 26 6.4 Use of Emergency Airlock . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27 7.0 FIGURES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 29 7.1 Containment Pre-Access Filtration System . . . . . . . . . . . . . . . . . . . . . . . . . . . 30 l 8.0 ATTACHMENTS/FORMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 29 8.A Guidelines for Containment Visual Inspections . . . . . . . . . . . . . . . . . . . . . . . . 31 l 8.B Containment Floor Plans . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32 l 8.C General Airlock Cautionary and Awareness Criteria . . . . . . . . . . . . . . . . . . . . . 36 l 9.0 RECORDS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 29 CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 3 OF 37 l

[C] 1.0 PURPOSE 1.1 The purpose of this procedure is to delineate responsibilities and provide the necessary instructions required to safely enter Containment during MODES 1 through 4 of operation.

1.2 This procedure satisfies the following requirements of the CPSES Technical Requirements Manual:

! TRS 13.5.31.2 visual inspection for loose debris in affected areas of Containment during MODES 1 through 4.

1.3 This procedure is also a trigger procedure for the following requirements of the CPSES Technical Specifications:

! SR 3.6.2.1, Containment Airlock operability.

1.4 The figures/attachments/forms listed below do not require SORC review when being modified and issued per STA-202:

! Figure 7.1, Containment Pre-Access Filtration System

! Attachment 8.A, Guidelines for Containment Visual Inspections l

! Attachment 8.B, Containment Floor Plans l

! Attachment 8.C, General Airlock Cautionary and Awareness Criteria l

! STA-620-1, Containment Entry Authorization and Visual Inspection Verification CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 4 OF 37 l 2.0 APPLICABILITY NOTE: MODE 4 requirements may be implemented at the discretion of the Shift Manager while the plant is in MODE 5 or 6.

2.1 This procedure applies to all personnel requiring access to Containment during MODES 1 through 4 of operation or following a reactor trip or plant emergency.

2.2 When performing activities associated with this procedure, REFER to STA-919, CPNPP Safety-Security Interface Requirements to determine if a Safety-Security interface requirement may be adversely affected prior to continuing the activity.

[CR-2010-000434]

Example of activity: Emergency entry through the Emergency Airlock CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 5 OF 37 l

3.0 REFERENCES

3.1 Performance References 3.1.1 STA-123, Pre-Job and Post-Job Briefs 3.1.2 STA-607, Housekeeping Control l l

3.1.3 STA-625, Foreign Material Exclusion l 3.1.4 STA-628, Confined Space Entry 3.1.5 STA-660, Control of High Radiation Areas l 3.1.6 STA-674, Heat Stress Management 3.1.7 STA-681, Pressurized Containment Entry 3.1.8 STA-702, Surveillance Program 3.1.9 STA-729, Control of Transient Combustibles, Ignition Sources and Fire Watches 3.1.10 STA-919, CPNPP Safety-Security Interface Requirements 3.1.11 OPT-305, Containment Closeout Inspection 3.1.12 SOP-801A/B, Containment Ventilation System 3.1.13 A1-0413 Series Drawings, Room Area Designations Unit 1 and 2 CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 6 OF 37 l 3.2 Developmental References 3.2.1 STA-601, Authority for Equipment Operation 3.2.2 STA-606, Control of Maintenance and Work Activities l

3.2.3 STA-656, Radiation Work Control l

3.2.4 OPT-408A/B, Refueling Containment Penetration Verification 3.2.5 RFO-102A/B, Refueling Operation 3.2.6 SOP-907A/B, Containment Personnel Airlocks 3.2.7 CPSES Technical Specifications section SR 3.6.2.1 3.2.8 Commitment #s 00747, 24998, and 26722 l 3.2.9 NRC-60FR46497 (09/07/95) (Modified Security requirements) 3.2.10 AN-96-000190-00-05 3.2.11 CR-2011-010210 Unable to pressurize inner door seal for Unit 1 PAL l during OPT-802A. l CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 7 OF 37 l 4.0 DEFINITIONS/ACRONYMS 4.1 Bioshield - The permanent plant shielding encompassing the NSSS components (i.e.,

reactor vessel, steam generators and reactor coolant pumps).

4.2 [C] - Indicates steps referenced in the CPNPP Commitment Management Program l 4.3 Containment Pre-entry Meeting - A meeting typically scheduled at least one (1) day prior to Containment entry. This meeting should be conducted for entries involving non-routine, complex activities or as requested by RP, Operations, or any other organization involved in the entry. Items to be discussed during the conduct of this meeting are described in Step 6.2.3.

4.4 Emergency Entry - Entry into Containment to prevent actual or potential personnel injury or damage to equipment and facilities or as requested by the Shift Manager to address plant operational concerns.

4.5 FME Zone (FMEZ) - The clean area identified by an FMEZ sign (similar to Attachment 8.D) and an FME red/white boundary ribbon/tape where FME controls are required to protect open components or systems from being degraded by foreign material. The natural enclosure of a room or area may be designated as an FMEZ with a sign only at the entrance/s.

4.6 FME Control Plan - A written description of the FME controls, consisting of the Work Order, implementing procedure and the STA-625-4 FME Control Planthat will be discussed during the pre-job brief and used during the work to prevent an FME event.

4.7 General Entry - Includes but are not limited to Operator tours, inspection and system manipulations, RP or Safety surveys, or initial entries to evaluate equipment performance.

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 8 OF 37 l 4.8 Multiple RWO Entry - Entry in which multiple RWOs are working on different components in different locations inside Containment.

4.9 Multiple Team Entry - Entry in which one task involves multiple work organizations (e.g.,

valve rework/MM, IC).

4.10 Responsible Work Organization (RWO) - The lead organization (e.g., Chemistry, Maintenance Team, Operations, PROMPT Team or Maintenance Services) that has l responsibility for resolution of a work activity.

4.11 RWO Supervisor - The individual designee assigned by the RWO and having responsibility for the work activity performance (e.g., a Manager, Supervisor, Team Leader, Craftsman or Technician).

4.12 Scheduled Entry - Entry into Containment for the purpose of conducting routine tasks necessary to support unit operations.

4.13 Unplanned Entry - Entry into Containment that has NOT been included in the POD/Outage schedule.

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 9 OF 37 l 5.0 RESPONSIBILITIES 5.1 Shift Manager 5.1.1 Responsible for verifying incore instrumentation is in the stored position and tagged out of service, if required.

5.1.2 Responsible for turning ON Containment lighting prior to Containment Entry and for turning OFF Containment lighting after the work group exits Containment. Security should be contacted to ensure all personnel have exited containment. Contact CAS or SAS at ext. 5606 to obtain accountability report for applicable containment. IF a backup method is utilized for personnel accountability, THEN the RWO Supervisor will provide this information.

5.1.3 Responsible for authorizing a Containment Entry.

5.1.4 Responsible for signing Form STA-620-1 as specified in STA-702.

[C] 5.1.5 Responsible for assigning an individual to operate the Personnel Airlock.

5.1.6 Responsible for ensuring the Operations Department has a representative at the scheduled Containment pre-entry meetings when requested.

5.1.7 Responsible for having Containment checked for Class C Atmosphere as defined by STA-628 if Nitrogen or other gas leaks are suspected.

5.1.8 Responsible for performing leak test of Containment Airlock seals after entry completion as applicable.

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 10 OF 37 l 5.2 RWO Supervisor 5.2.1 Responsible for notifying Radiation Protection of pending entry and for notifying Security if the entry is planned through the Emergency Airlock.

5.2.2 Responsible for notifying Control Room before and after Containment entries.

5.2.3 Responsible for coordinating Containment Entry activities and completing applicable forms.

5.2.4 Responsible for Housekeeping in accordance with STA-607, AND Foreign Material Exclusion in accordance with STA-625 including completion of the FME Control Plan form (STA-625-4).

5.2.5 Responsible for ensuring that visual inspections are performed in affected areas of Containment in accordance with Technical Requirements Manual TRS 13.5.31.2 and documented on form STA-620-1. A Form STA-620-1 shall be completed once a day or fraction of a day for the entire job duration. A Form STA-620-1 should be completed as part of each shift turnover of the applicable job.

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 11 OF 37 l 5.2.6 Responsible for maintaining personnel accountability in the event of a Containment evacuation.

NOTE: SMF-2004-00003660 identified an event where personnel accountability was lost when employee badges were unable to be read by the Containment Access Control card readers.

5.2.6.1 Responsible for discussing the methods of accountability with Operations. Reference Step 5.1.2.

! Utilization of the Containment Access Control accountability card readers should be used as the primary method for accomplishing personnel accountability.

! Use of the RWP access events from the RP computer or manual paper logs are acceptable backup methods for maintaining personnel accountability.

5.2.6.2 Responsible for ensuring all personnel utilize the appropriate method for personnel accountability when entering and exiting the containment.

5.2.6.3 Responsible for ensuring that individuals are familiar with the location of the Containment and Emergency Airlocks, the intended work location(s), and evacuation routes.

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 12 OF 37 l 5.2.7 Responsible for completing Containment Entry Checklist (part of STA-620-1) prior to Containment pre-entry meetings.

5.2.8 Responsible for familiarizing self and all team members with the Containment Entry Checklist.

5.2.9 Responsible for attending Containment pre-entry meetings when requested.

5.2.10 Responsible for ensuring a minimum of two people enter Containment.

Reference steps 6.1.5 and 6.3.1.

5.3 Radiation Protection 5.3.1 The On-shift Radiation Protection Technician is responsible for preparation of the RWP when necessary.

5.3.2 Responsible for providing radiological briefing to personnel prior to entry.

5.3.3 Responsible for attending Containment pre-entry meetings when requested.

5.4 Security 5.4.1 Responsible for establishing vital area entry/exit controls for Containment entries through the Emergency Airlock.

5.4.2 Responsible for attending Containment pre-entry meetings when requested.

5.4.3 Responsible for providing a Containment accountability report when requested by the Control Room / Shift Manager.

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 13 OF 37 l 5.5 System Engineering 5.5.1 Responsible for attending Containment pre-entry meetings when requested.

5.6 Safety Services 5.6.1 Responsible for attending Containment pre-entry meetings when requested and discussing the heat stress program requirements when appropriate. IF required, the heat stress form should be completed at the meeting.

5.7 Work Control Manager OR Outage Manager 5.7.1 Responsible for scheduling Containment entry activities.

5.7.2 Responsible for scheduling and coordinating Containment pre-entry meetings when required. Reference Step 4.3.

5.7.3 Responsible for contacting the RWOs, RP, OPS, Safety Services and System Engineering of impending Containment entries and pre-entry meetings and for contacting Security if the entry is planned through the Emergency Airlock.

5.7.4 Responsible for chairing Containment pre-entry meetings.

5.8 Maintenance 5.8.1 The Maintenance Support Manager is responsible for maintaining this procedure current.

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 14 OF 37 l 6.0 INSTRUCTIONS 6.1 Precautions 6.1.1 IF Containment Evacuation Alarm or Area Radiation Monitor alarms annunciate in the affected areas, or a Containment Evacuation announcement is made over the plant communication system, THEN all personnel shall leave Containment immediately. Containment re-entry shall be authorized by the Shift Manager only when the reason and circumstances associated with the evacuation, AND the existing radiological conditions in Containment are known.

6.1.1.1 Upon exiting Containment, all personnel shall proceed to the designated Containment Evacuation Assembly area.

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 15 OF 37 l 6.1.2 During refueling outages and maintenance activities, or when Containment is otherwise occupied for extended periods, the incore detectors should be tagged out of service until work activities are completed and/or arrangements made to preclude entry to the following areas:

! 808'-Incore Instrumentation Room

! 808'-Excess Letdown Heat Exchanger Room

! 808'-Steam Generator Loop Rooms

! 832'-Incore Instrumentation Room

! 832'-Regenerative Heat Exchanger Room

! 849'-Incore Instrumentation Room IF either of the following is true, THEN Caution Tags may be lifted by the Shift Manager:

! The detectors have been placed in storage and/or are incapable of being withdrawn or moved during performance of maintenance and testing.

! It has been determined by Radiation Protection that operation of the incore detectors will not adversely affect other activities in Containment.

6.1.3 IF entry into the Seal Table or Incore Drive rooms is required for reasons other than repair of the Incore System, THEN the Incore instrumentation shall be placed within the reactor core or otherwise located to minimize exposure; AND should be tagged out of service.

6.1.4 When in MODES 1 and 2, entry into the S/G Loop Rooms should be approved by the Radiation Protection Manager or the Plant Manager. Entry should be in accordance with STA-660.

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 16 OF 37 l 6.1.5 The following personnel criteria should be observed :

6.1.5.1 A minimum of two people are required to enter Containment. IF Radiation Protection coverage is provided, THEN the Radiation Protection technician may be considered as the second person.

6.1.5.2 A maximum of 50 people should be allowed in Containment at any one time during MODES 1 and 2. This is an administrative limit recommended by EVAL-2004-000472-01.

6.1.6 WHEN the reactor trip breakers are closed, portable radios with an output power greater than 0.5 watts are prohibited from transmitting on the 842' and 860' elevations inside Containment.

6.1.7 Treat all material/debris inside Containment as potentially contaminated.

6.1.8 Work in progress may allow certain clothing, tools, equipment, etc. to remain in Containment. Such materials shall be removed when work is completed.

6.1.9 Formal visual close-out inspections are not required for General Entries.

Under these circumstances, individuals are responsible for ensuring that any equipment or personal item(s), for example flashlights, survey meters, test equipment, PPE, clipboards, pens, note paper, or similar items, inherently required for the activity are still in their possession upon exit. The RWO Supervisor should ensure that individuals are aware of this requirement prior to entry.

6.1.10 Personnel entering containment are the responsibility of the RWO Supervisor.

NO PERSON should tag along on an open STA-620-1 form without the approval of the RWO Supervisor as indicated in Section 3 of the Containment Entry Checklist.

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 17 OF 37 l 6.1.11 Personnel entering the Containment Building during Modes 1 through 4 are entering an FMEZ.

6.1.12 S/G Loop Room platform handrails may be partially to completely removed.

Access to the platforms in these areas may require compensatory fall protection measures.

6.1.13 Verify the PAL OR EAL seals and sealing surfaces are clear of any obvious l foreign material AND debris when closing the doors during Containment l entries. (CR-2011-010210-00) l CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 18 OF 37 l 6.2 Containment Entry Requirements Non-Emergency NOTE 1: IF a multiple team entry is required, (entry in which one work task involves multiple organizations), a Lead RWO Supervisor may be appointed from the disciplines entering Containment. The Lead RWO Supervisor is then responsible for coordinating the Containment entry and visual inspection for loose debris in accordance with Section 5.2 of this procedure.

IF a multiple RWO entry is required, (entry in which multiple RWOs are working on different components in different locations in Containment), RWO Supervisors are responsible for their respective Containment entry and the visual inspection for loose debris in accordance with Section 5.2 of this procedure.

NOTE 2: Access is limited to those locations/elevations specified by the Shift Manager.

6.2.1 The RWO Supervisor requiring access has the overall responsibility for initiating and coordinating those activities which culminate in entry to Containment.

6.2.1.1 IF this is an Unplanned Entry, the Containment Entry Checklist may be N/Ad with the concurrence of the Shift Manager. ALL other requirements for entry are still applicable. Note reason for entry in ACTION ITEMS/Comments section of STA-620-1.

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 19 OF 37 l 6.2.2 The Shift Manager should determine if entry to Containment is feasible on the date and time requested. This determination should be made based on the following general conditions:

! The present MODE of operation;

! Projected or potential changes in the existing MODE of plant operation;

! Plant evolutions within a given MODE

! Radiological conditions.

! Containment Atmosphere IF Containment Entry is NOT feasible, when requested, the Shift Manager should recommend an appropriate date and time.

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 20 OF 37 l 6.2.3 The Work Control Manager, Outage Manager, or designee should perform the following:

! When required (Reference Step 4.3), schedule a Containment pre-entry meeting prior to the entry.

! Notify the RWOs, RP, Security, OPS, Safety Services, Engineering, and other groups, as appropriate.

! When conducted, chair the Containment pre-entry meeting. Each RWO entering Containment should have answered the questions on the Containment Entry Checklist (part of STA-620-1) appropriate to their work. The meeting is to discuss the entry, this includes:

- Purpose

- Participation (Work Week Coordinator to ensure the number of personnel required for entry during MODES 1 and 2 satisfies the requirement of Step 6.1.5.2.)

- Specific objective

- Contingency plans

- Schedules

- Individual responsibilities

! Reinforce the expectation to verify the PAL OR EAL seals and sealing l surfaces are clear of any obvious foreign material AND debris when l closing the doors during Containment entries. (CR-2011-010210-00) l CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 21 OF 37 l 6.2.4 Upon determining that Containment Entry is feasible, each RWO Supervisor requiring access should initiate the following as required:

! A Confined Space Entry Permit Request IF access is required into any l confined spaces inside Containment such as sumps, vessels, pits or others identified in accordance with STA-628.

! A heat stress survey form in accordance with STA-674.

! An FME Control Plan, in accordance with STA-625, describing the FME l controls that will be used during the work to prevent an FME event.

! Notify the Fire Protection Supervisor if the task requires permits associated with hot work activities or transient combustibles in accordance with STA-729.

! Ensure the requirements for Pressurized Containment Entry are reviewed and complied with in accordance with STA-681.

! Ensure a pre-job and post-job brief per STA-123 is performed for a specific task. This brief is in addition to the Containment pre-entry meeting scheduled by Work Control.

NOTE: The following is NOT required for an Unplanned Entry.

! Complete the Containment Entry Checklist (part of STA-620-1),

Sections 1 Work Scope and 2 Responsibilities, before the Containment pre-entry meeting. Section 3, Personnel, of the Containment Entry Checklist is to be used to list those personnel who have been properly briefed or have permission from the RWO Supervisor for entry on this STA-620-1, not necessarily a list of actual entrants.

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 22 OF 37 l 6.2.5 Upon receiving notification of pending entry, Radiation Protection should perform the following tasks:

! Evaluate airborne radioactivity concentrations from the respective unit's Containment Particulate, Iodine and Gas (PIG) monitor (1/2RE5502, 1/2RE5503 and 1/2RE5566) or, if the PIG is NOT operable, an air sample should be obtained and evaluated as soon as possible prior to allowing initial entry.

! Recommend operation of the pre-access filtration system if airborne activity levels warrant its use. Refer to Figure 7.1 for pre-access filtration system operating characteristics;

! Review DRMS information applicable to area within Containment where the entry team may traverse;

! Prepare RWP for Containment Entry or specify the appropriate GAP the entry team may utilize;

! Determine if Radiation Protection coverage is required based on area to be traversed, radiological conditions and current survey data.; and

! IF entry is to Seal Table room or Incore Drive room areas for trouble shooting purposes AND incore instruments are NOT tagged out, THEN, prior to entry, obtain approval from the Shift Manager.

6.2.6 Security should establish vital area entry/exit controls adjacent to Containment Emergency Airlock upon receiving notification of a pending entry through the Emergency Airlock.

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 23 OF 37 l 6.2.7 Once conditions have been met to proceed with a Containment Entry, the Shift Manager is responsible for the following:

! Ensure that incore instrumentation is placed in storage and tagged out of service in accordance with Section 6.1.2.

! IF airborne radioactivity concentrations warrant its use, THEN notify the Unit Supervisor to start up the pre-access filtration system in accordance with SOP-801A/B, "Containment Ventilation System;"

! Ensure a LCOAR has been initiated to ensure completion of the Containment Airlock seal test as required to satisfy Technical Specification SR 3.6.2.1.

CAUTION: The following action ensures that there is adequate lighting in Containment for egress. This lighting is NOT load-shed after Safety Injection.

! Switch ON all available Containment lighting at the Containment Lighting Local Control Stations located in the Safeguards Building prior to Containment Entry. Normally as a minimum, ensure the following switches are on:

For Unit 1:

1-XF-SC1/3 (TR A Switchgear Room) 1-XF-SC2/4 (TR B Switchgear Room)

For Unit 2:

2-XF-SC1/3 (TR A Switchgear Room) 2-XF-SC2/4 (TR B Switchgear Room)

! Sign STA-620-1 authorizing Containment Entry.

! IF Nitrogen or other gas leaks are suspected, THEN have Containment sampled and analyzed for Class C Atmosphere as defined by STA-628.

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 24 OF 37 l 6.2.8 Once the RWP is approved, Containment Entry may proceed. At this point the work group should perform the following tasks:

! Ensure STA-620-1 has been signed authorizing initial entry for the present shift.

NOTE: A signature on STA-620-1 authorizing Containment Entry does NOT satisfy the requirement to notify the Control Room immediately prior to entry by the RWO.

! The RWO Supervisor should notify the Control Room immediately prior to the work group entering Containment.

! Maintain material and tool accountability using STA-625-1.

NOTE 1: Attachment 8.B, Containment Floor Plans, may be used to document l approximate work location(s), and location of any equipment/material left in Containment.

NOTE 2: Work in progress may allow certain clothing, tools, equipment, etc. to remain in Containment. Such materials shall be removed when work is completed.

[C] 6.2.9 After work is complete or at least once per shift, the RWO Supervisor should ensure a visual inspection of the affected area is performed. All trash, clothing l or other loose materials shall be secured or removed to prevent transport to the Containment Sump. Refer to Attachment 8.A for final inspection criteria. l 6.2.9.1 A Form STA-620-1 shall be completed once a day or fraction of a day for the entire job duration.

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 25 OF 37 l 6.2.10 Upon exiting Containment, the RWO Supervisor should notify the Control Room immediately.

NOTE: Containment lighting may be left ON, at the discretion of the Shift Manager, as required to support plant activities, such as an additional Containment entry scheduled near term.

! IF ALL Entry Teams have exited Containment, as determined by Containment accountability (reference step 5.1.2), THEN the Shift Manager should have Containment lighting switched OFF at the Containment Lighting Local Control Stations located in the Safeguards Building.

For Unit 1:

1-XF-SC1/3 (TR A Switchgear Room) 1-XF-SC2/4 (TR B Switchgear Room)

For Unit 2:

2-XF-SC1/3 (TR A Switchgear Room) 2-XF-SC2/4 (TR B Switchgear Room)

! WHEN entries have been completed and Containment has been secured, THEN the Shift Manager shall ensure the requirements of TS 4.6.1.3a, Containment Operability, are met.

NOTE: The Shift Managers authorizing signature is only required for the initial entry per shift of the associated job.

6.2.11 The RWO Supervisor shall complete Form STA-620-1, Containment Entry Authorization And Visual Inspection Verification and obtain the Shift Managers signature.

6.2.12 The Shift Manager should subsequently disposition Form(s) STA-620-1 after final acceptance.

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 26 OF 37 l 6.3 Emergency Containment Entry Requirements 6.3.1 A minimum of two people are required to enter Containment, one of which should be a Radiation Protection Technician.

6.3.2 All personnel entering Containment should wear the necessary protective clothing recommended by Radiation Protection. Personnel should also wear self contained breathing apparatus if airborne concentration levels are unknown or subject to change due to worsening plant conditions OR IF Nitrogen or other gas leaks are suspected. IF Containment has been sampled and analyzed for Class C Atmosphere as defined by STA-628, THEN Respiratory Protection may NOT be required if entry is made for a non-operational type emergency (e.g., medical injury).

6.3.3 A Containment briefing should be held by the Shift Manager. Each RWO entering into Containment should ensure that all questions on the checklist have been reviewed and that all entry members understand their responsibilities.

6.3.4 The Shift Manager shall approve all entries.

6.3.5 IF the Containment PIG (1/2RE5502, 1/2RE5503 and 1/2RE5566) is NOT operable, the Shift Manager should notify Radiation Protection to obtain Containment air samples in accordance with Section 6.2.5 of this procedure.

6.3.6 The Shift Manager should also notify Security prior to an emergency entry into Containment through the Emergency Airlock.

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 27 OF 37 l NOTE: During emergencies, an RWP need NOT be completed or issued prior to entry.

The required paperwork is expected to be completed in a timely manner consistent with related emergency response activities.

6.3.7 Containment entry should be documented by filling out an RWP. The RWP should be filled out by Radiation Protection.

6.3.8 A back-up team should be ready for Containment entry to provide assistance, if required.

6.4 Use of Emergency Airlock 6.4.1 Normal access and egress from Containment should be made using the Personnel Airlock. However, it may become necessary to use the Emergency Airlock. This decision should be made by the Shift Manager. For normal access through the Emergency Airlock, Security should be notified and an operator should be stationed with Radio Communication to ensure the Emergency Airlock Interlock is NOT challenged. All entry requirements specified in Sections 6.2 and 6.3 are applicable, with the exception of those items pertaining to the entry location.

6.4.2 The Emergency Airlock should be used for egress under the following conditions:

6.4.2.1 Whenever plant or environmental conditions are such that use of the Personnel Airlock is unfeasible or presents a personnel safety hazard; 6.4.2.2 Whenever the Personnel Airlock door malfunctions, provided that the following conditions are met:

! The control room operator is notified and the Shift Manager authorizes use of the Emergency Airlock; and

! Every reasonable effort has been made to repair and open the inoperable Airlock door.

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 28 OF 37 l NOTE: Should environmental conditions preclude staying on the 899' elevation (e.g.,

steam generator atmospherics have lifted) personnel may wait for RP at the next lower elevation after exiting Containment.

6.4.3 Upon exiting Containment, personnel should stay in the enclosure on the 899' elevation until RP assistance arrives.

7.0 FIGURES 7.1 Figure 7.1 - Containment Pre-Access Filtration System 8.0 ATTACHMENTS/FORMS 8.1 Attachments 8.1.1 Attachment 8.A Guidelines for Containment Visual Inspections l NOTE: The Containment Floor Plans are BASIC plans for Unit 1 Containment. Unit 2 is a mirror image of Unit 1. These floor plans are for information only.

8.1.2 Attachment 8.B Containment Floor Plans l 8.1.3 Attachment 8.C General Airlock Cautionary and Awareness Criteria l 8.2 Forms 8.2.1 Form STA-620-1, Containment Entry Authorization And Visual Inspection Verification 9.0 RECORDS When completed, the following forms, reports, or other documents generated in response to this procedure should be dispositioned in accordance with STA-302, "Station Records" by the Shift Manager.

9.1 Form STA-620-1, Containment Entry Authorization And Visual Inspection Verification CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 29 OF 37 l FIGURE 7.1 PAGE 1 OF 1 CONTAINMENT PRE-ACCESS FILTRATION SYSTEM (CPFS)

Below is a table which predicts the reduction of particulate and radioiodine removal by the CPFS as a function of time. The filtration efficiency was set at 90%, and perfect mixing in Containment was assumed. The data below assumes 15,000 CFM from each unit (actual tolerance is 15,000 + 10%). Therefore operating times may vary + 10% from those listed. This table assumes no addition of particulates or iodine (i.e. Reactor NOT at power/no leakage). Cleanup at power will be significantly different and only come to equilibrium.

1 Unit Operating Both Units Operating (Minutes) (Minutes) 100% of Original 0 0.0 50% of Original 153 76.5 25% of Original 306 153.0 10% of Original 509 254.0 5% of Original 662 331.0 CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 30 OF 37 l ATTACHMENT 8.A l PAGE 1 OF 1 GUIDELINES FOR CONTAINMENT VISUAL INSPECTION NOTE 1: Visual inspection requirements are limited to those areas of Containment that the entry team(s) traversed and where work was performed.

NOTE 2: OPT-305, Containment Close Out Inspection step 8.1.2 contains a list of items approved by a Technical Evaluation to remain in Containment.

When multiple Containment entries occur over more than one work shift with Containment Integrity established, the inspection shall be performed at least once per shift.

During the final entry, the inspection shall be performed and should also include the l following: l

1. Verify that no attached items/equipment or staging materials have been left behind (e.g.,

plastic sheeting, scaffolding, test equipment, drain hoses, sleeving, etc.).

2. Verify that no foreign material such as temporary tags or posting materials have been left behind (e.g., work in progress tags, information tags, radiological postings associated with the work activity). Equipment labels, locked valve tags and valve/equipment tags installed per STA-618 are NOT included.

3. The last person exiting Containment is to verify the PAL OR EAL seals and sealing l surfaces are clear of any obvious foreign material AND debris prior to final closing of l each door upon completion of Containment entries. (CR-2011-010210-00) l CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 31 OF 37 l ATTACHMENT 8.B l PAGE 1 OF 5 CONTAINMENT FLOOR PLANS STAIR NO. C-2 STAIR NO. C-1 STEAM GEN STEAM GEN NO. 3 NO. 2 STAIR NO. C-12 ELEVATOR OPEN REACTOR & CONTAINMENT STEAM GEN NO. 4 STEAM GEN NO. 1 OPEN OPEN LADDER OPEN OPEN LADDER EMERGENCY AIR LOCK ELEVATION 905'-6" NOTE: The Containment Floor Plans are BASIC plans for Unit 1 Containment. Unit 2 is a mirror image of Unit 1. These floor plans are for information only to provide a general layout arrangement. Reference the A1-0413 series drawings for specific details, room numbers, etc.

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 32 OF 37 l ATTACHMENT 8.B l PAGE 2 OF 5 CONTAINMENT FLOOR PLANS CONTAINMENT CONTAINMENT COOLING UNIT COOLING UNIT EQUIPMENT HATCH STAIR NO. C-7 STAIR STEAM STEAM NO. C-1 GEN #3 GEN #2 RCP RCP STAIR NO. C-2 #3 #2 ELEVATOR RX RCP RCP STAIR

4 #1 NO. C-5 STEAM STEAM ROD POSITION GEN #4 GEN #1 INDICATOR ROOM PRZR ACCUMULATOR LADDERS PENETRATION AREA ELEVATION 860'-0" NOTE: The Containment Floor Plans are BASIC plans for Unit 1 Containment. Unit 2 is a mirror image of Unit 1. These floor plans are for information only to provide a general layout arrangement. Reference the A1-0413 series drawings for specific details, room numbers, etc.

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 33 OF 37 l ATTACHMENT 8.B l PAGE 3 OF 5 CONTAINMENT FLOOR PLANS ELEVATOR

INCORE * *INST *

DRIVE RM

PARTIAL PLAN AT ELEVATION 842'-0 LADDER * *

PARTIAL PLAN AT ELEVATION 849'-0

STAIR NO. C-4 PARTIAL PLAN AT ELEVATION 842'-0

AND PARTIAL PLAN AT ELEVATION 849'-0

NOTE: The Containment Floor Plans are BASIC plans for Unit 1 Containment. Unit 2 is a mirror image of Unit 1. These floor plans are for information only to provide a general layout arrangement. Reference the A1-0413 series drawings for specific details, room numbers, etc.

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 34 OF 37 l ATTACHMENT 8.B l PAGE 4 OF 5 CONTAINMENT FLOOR PLANS STAIR NO. C-2 STAIR NO. C-1 STEAM STEAM GEN #3 GEN #2 ACC ACC

2

3 RCP #3 RCP #2

*

EL

EV AT INCORE INST RM

OR RX LADDER ACC

1 RCP #4 RCP #1 STEAM STEAM GEN #4 GEN #1 HX RE GEN STAIR NO. C-4 ELEVATION 832'-6" NOTE: The Containment Floor Plans are BASIC plans for Unit 1 Containment. Unit 2 is a mirror image of Unit 1. These floor plans are for information only to provide a general layout arrangement. Reference the A1-0413 series drawings for specific details, room numbers, etc.

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 35 OF 37 l ATTACHMENT 8.B l PAGE 5 OF 5 CONTAINMENT FLOOR PLANS STAIR NO. C-1 STAIR NO. C-2 ELEVATOR INCORE INST AREA LADDER RX * * * * * * * * * *

LADDER * * *

RCDT HX HX N

LT DT D

RC XS RECIRC SUMPS ELEVATION 808'-0

NOTE: The Containment Floor Plans are BASIC plans for Unit 1 Containment. Unit 2 is a mirror image of Unit 1. These floor plans are for information only to provide a general layout arrangement. Reference the A1-0413 series drawings for specific details, room numbers, etc.

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 36 OF 37 l ATTACHMENT 8.C l PAGE 1 OF 2 l l

GENERAL AIRLOCK CAUTIONARY AND AWARENESS CRITERIA l

[L] l l

1.0 CONTACT Operations with any questions or concerns regarding door operations l l

2.0 IF door operator is starting the entry, THEN contact Control Room prior to opening the l airlock. l l

3.0 OPERATIONS is always in charge when in the area. l l

4.0 WHEN you are operating the airlock, YOU assume responsibility for its operation. l l

5.0 WHEN operating the airlock, VERIFY correct button to be pressed. Once indicator light l is lit on the control panel, NEVER press any button other than one of the buttons below l that indicator light. (PAL Only) l l

6.0 IF there are other personnel in the area, THEN always announce action to be taken. l l

7.0 DO NOT close the interior door from the exterior. IF this type of action is needed, THEN l Operations should be called because something is wrong. l l

8.0 Stop buttons will stop any door at any time. Use them as needed. The stop button may l be used on every cycle of the door. (PAL Only) l l

9.0 It is expected the door operator go to a stop button once operation of the door has l started OR be within arms reach of the stop button once operation has started except l when getting ready to pull the door closed. (PAL Only) l l

10.0 The door is designed to stop with reasonable force applied to it; the door can be stopped l by pushing it. The direction of the door can be reversed if pushed even harder, it does l not damage the door. WHEN the door needs to be stopped, the normal action should be l to use the stop button. (PAL Only) l l

l CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d CPNPP PROCEDURE NO. l STATION ADMINISTRATION MANUAL STA-620 REVISION NO. 13 CONTAINMENT ENTRY INFORMATION USE PAGE 37 OF 37 l ATTACHMENT 8.C l PAGE 2 OF 2 l l

GENERAL AIRLOCK CAUTIONARY AND AWARENESS CRITERIA l l

l 11.0 Once a door has started to close OR open, the correct way to stop the sequence is to l use a stop button. In order to re-open a door that is closing or is partially closed, USE l the stop button first. (PAL Only) l l

12.0 DO NOT tolerate horse-play around the airlock. (Zero tolerance) l l

13.0 Watch all personnel entering AND exiting airlock to ensure there is no contact with l locking ring or sealing surfaces. The seal is greased with silicon grease. The locking l tabs and ring are greased with petroleum grease. IF petroleum grease is transferred to l sealing surface, THEN it will dissolve the seal. Always have at least one paper towel to l do immediate clean up if this occurs. l l

14.0 DO NOT allow the airlock to be over-filled. l l

15.0 Watch seals for possible pull out the first time the doors are opened. Occasionally, l when PAL has been closed for several weeks in a row, seal will pull out of the channel l when door is opened the first time. (PAL Only) l l

16.0 The hydraulic fluid in the airlock is a solvent that will go right through your skin. Contact l with eyes, nose and mouth is extremely hazardous and must be reported to Safety even l if it is only a drop. l l

IF you get a small amount on clothing, THEN contact someone to take your place. l Change clothes AND wash area that made contact with the skin. DO NOT ignore it. l l

17.0 Verify the PAL OR EAL seal and sealing surfaces are clear of any obvious foreign l material AND debris when closing the doors during Containment entries. l (CR-2011-010210-00) l CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d (For Information Only) Record of Changes Page 1 Rev/PCN Affected Pages Description of Change 12 / 4 6, 8, 12, 15, 24 Incorporated Foreign Material Exclusion (FME) into the procedure by adding the appropriate definitions, responsibilities, and instructions. This change is in response to the changes made to STA-625. The change heightens the awareness of personnel entering Containment during Modes 1-4 by making it an FME Zone.

12 / 5 3, 12 Added step to exempt figures/attachments/forms from SORC review as per STA-202, 6.2.10. Added step to require compensatory fall protection measures be addressed if accessing S/G Loop Room platforms. Ref: ACTN-MAN-2007-001267-03.

12 / 6 6, 6.1, 7, 8, 9, In support of continuous improvement, the Containment Pre-Entry meeting 10, 14 will be scheduled for non-routine, complex activities or as requested by RP, Operations, or any other organization involved in the entry. For routine maintenance and activities that are scheduled in the POD, this meeting is considered optional.

12/7 4, 25, 26, 27, Removed room numbers from Attachment 8.1.2, Containment Floor Plans.

28, 29 Provided additional detail in note for each floor plan that plans are provided for information only and A1-0413 series drawings should be referenced for specific details, room numbers, etc. this PCN in response to SMF-2009-002168. This PCN is considered an allowed editorial change per STA-202 ATT. 8.F SECTION 3.0.

12 / 8 5, 18 Editorial PCN adding STA-601 as a Developmental Reference, and adding a clarifying note to Step 6.2.8 stating that a signature on STA-620-1 authorizing Containment Entry does not satisfy the requirement to notify the Control Room immediately prior to entry by the RWO. Ref: AI-CR-2009-005381-00-9.

12 / 9 3, 4 Editorial change approved by SORC (Mtg. #10-003) to add reference to STA-919 and to add a step relative to the implementation of safety-security interface requirements (CR-2010-000434).

13 / 0 All Incorporated previous PCNs, added levels of use, made minor administrative changes. Added requirement for last person exiting Containment to verify PAL/EAL seals and surfaces are clear of foreign material/debris prior to closing the doors. Added new attachment containing general airlock cautionary and awareness criteria. (Ref: AI-CR-2011-010210-9/10)

CPNPP NRC 2012 JPM SA4 Procedure 1 Rev d

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SA5 Task # SO1136 K/A # 2.4.41 2.9 / 4.6

Title:

Classify an Emergency Plan Event Examinee (Print):

Testing Method:

Simulated Performance: Classroom: X Actual Performance: X Simulator:

Alternate Path: Plant:

Time Critical:

READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue.

When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

Unit 1 is in MODE 5.

Unit 2 is in MODE 1.

A sodium hypochlorite hose has ruptured while transferring chemicals at the Service Water Intake Structure.

Personnel performing the evolution were wearing respirators and have evacuated the area; however, nearby maintenance workers are requesting medical attention related to breathing difficulties.

Initiating Cue: The Shift Manager directs you to PERFORM the following:

DETERMINE the Emergency Action Level Group / Category, Subcategory, and Event Classification per EPP-201, Assessment of Emergency Action Levels, Emergency Classification, and Plan Activation.

Task Standard: Utilizing EPP-201, determined the Event Category and Event Classification using the Emergency Action Level Hot & Cold Classification Charts.

Required Materials: EPP-201, Assessment of Emergency Action Levels, Emergency Classification, and Plan Activation, Rev. 12.

CPNPP Emergency Action Level Hot & Cold Classification Charts, Rev. 12.

Sodium Hypochlorite Material Safety Data Sheet, Rev. 1.0 Validation Time: 15 minutes Completion Time: ________ minutes Comments:

Result: SAT UNSAT Examiner (Print / Sign): Date:

Page 1 of 4 CPNPP NRC 2012 JPM SA5 Rev d.docx

Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:

MAKE the following available in the classroom:

EPP-201, Assessment of Emergency Action Levels, Emergency Classification, and Plan Activation.

CPNPP Emergency Action Level Hot & Cold Classification Charts.

Sodium Hypochlorite Material Safety Data Sheet.

Page 2 of 4 CPNPP NRC 2012 JPM SA5 Rev d.docx

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from CPNPP Emergency Action Levels Hot.

Perform Step: 1 DETERMINE the Event Category.

Standard: REFERRED to CPNPP Emergency Action Levels Hot and Cold and DETERMINED the following chart is applicable:

CPNPP EAL Hot or Cold Conditions Comment: SAT UNSAT Perform Step: 2 MATCH plant conditions in the EAL Group / Category.

Standard: IDENTIFIED EAL Group / Category as HAZARDS (H).

Comment: SAT UNSAT Perform Step: 3 MATCH plant conditions in the selected EAL Subcategory.

Standard: IDENTIFIED EAL Subcategory as Hazardous Gas (3).

Comment: SAT UNSAT Perform Step: 4 Classify the event.

Standard: CLASSIFIED the event as an ALERT (HA3.1).

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 3 of 4 CPNPP NRC 2012 JPM SA5 Rev d.docx

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

Unit 1 is in MODE 5.

Unit 2 is in MODE 1.

A sodium hypochlorite hose has ruptured while transferring chemicals at the Service Water Intake Structure.

Personnel performing the evolution were wearing respirators and have evacuated the area; however, nearby maintenance workers are requesting medical attention related to breathing difficulties.

INITIATING CUE: The Shift Manager directs you to PERFORM the following:

DETERMINE the Emergency Action Level Group /

Category, Subcategory, and Event Classification per EPP-201, Assessment of Emergency Action Levels, Emergency Classification, and Plan Activation.

Page 4 of 4 CPNPP NRC 2012 JPM SA5 Rev d.docx

CPNPP NRC 2012 JPM SA5 Document Rev d MATERIAL SAFETY DATA SHEET PRODUCT R-50650 Sodium Hypochlorite, 12.5%

EMERGENCY TELEPHONE NUMBER(S)

(800) 424-9300 (24 Hours) CHEMTREC

1. CHEMICAL PRODUCT AND COMPANY IDENTIFICATION PRODUCT NAME : R-50650 Sodium Hypochlorite, 12.5%

COMPANY IDENTIFICATION : Nalco Company 1601 W. Diehl Road Naperville, Illinois 60563-1198 EMERGENCY TELEPHONE NUMBER(S) : (800) 424-9300 (24 Hours) CHEMTREC NFPA 704M/HMIS RATING HEALTH : 3/3 FLAMMABILITY : 0/0 INSTABILITY : 0/0 OTHER :

0 = Insignificant 1 = Slight 2 = Moderate 3 = High 4 = Extreme

2. COMPOSITION/INFORMATION ON INGREDIENTS Our hazard evaluation has identified the following chemical substance(s) as hazardous. Consult Section 15 for the nature of the hazard(s).

Hazardous Substance(s) CAS NO % (w/w)

Sodium Hypochlorite 7681-52-9 10.0 - 30.0 Sodium Hydroxide 1310-73-2 0.1 - 2.0

3. HAZARDS IDENTIFICATION

- EMERGENCY OVERVIEW**

DANGER Corrosive. CORROSIVE. MAY CAUSE SEVERE SKIN IRRITATION OR CHEMICAL BURNS TO BROKEN SKIN.

CAUSES EYE DAMAGE.

Do not get in eyes, on skin, on clothing. Do not take internally. Use with adequate ventilation. In case of contact with eyes, rinse immediately with plenty of water and seek medical advice. After contact with skin, wash immediately with plenty of water.

Wear a face shield. Wear chemical resistant apron, chemical splash goggles, impervious gloves and boots.

Not flammable but can act as an oxidizing agent, enhancing the burning rate of other materials. May evolve chlorine under fire conditions. May evolve HCl under fire conditions. Hypochlorous acid PRIMARY ROUTES OF EXPOSURE :

Eye, Skin HUMAN HEALTH HAZARDS - ACUTE :

EYE CONTACT :

Corrosive. Will cause eye burns and permanent tissue damage.

Nalco Company 1601 W. Diehl Road

Naperville, Illinois 60563-1198 * (630)305-1000 For additional copies of an MSDS visit www.nalco.com and request access 1 / 10 CPNPP NRC 2012 JPM SA5 Document Rev d

CPNPP NRC 2012 JPM SA5 Document Rev d MATERIAL SAFETY DATA SHEET PRODUCT R-50650 Sodium Hypochlorite, 12.5%

EMERGENCY TELEPHONE NUMBER(S)

(800) 424-9300 (24 Hours) CHEMTREC SKIN CONTACT :

May cause severe irritation or tissue damage depending on the length of exposure and the type of first aid administered. Repeated or prolonged contact may cause skin sensitization.

INGESTION :

Not a likely route of exposure. Corrosive; causes chemical burns to the mouth, throat and stomach.

INHALATION :

Not a likely route of exposure. Elevated temperatures or mechanical action may form vapors, mists or fumes which may be irritating to the eyes, nose, throat and lungs.

HUMAN HEALTH HAZARDS - CHRONIC :

No adverse effects expected other than those mentioned above.

4. FIRST AID MEASURES EYE CONTACT :

Get immediate medical attention. PROMPT ACTION IS ESSENTIAL IN CASE OF CONTACT. Immediately flush eye with water for at least 15 minutes while holding eyelids open.

SKIN CONTACT :

Get immediate medical attention. Immediately flush with plenty of water for at least 15 minutes. For a large splash, flood body under a shower. Remove contaminated clothing. Wash off affected area immediately with plenty of water. Contaminated clothing, shoes, and leather goods must be discarded or cleaned before re-use.

INGESTION :

Get immediate medical attention. DO NOT INDUCE VOMITING. If conscious, washout mouth and give water to drink.

INHALATION :

Remove to fresh air, treat symptomatically. If symptoms develop, seek medical advice.

NOTE TO PHYSICIAN :

Probable mucosal damage may contraindicate the use of gastric lavage. Based on the individual reactions of the patient, the physician's judgement should be used to control symptoms and clinical condition.

5. FIRE FIGHTING MEASURES FLASH POINT : Not flammable EXTINGUISHING MEDIA :

Not expected to burn. Use extinguishing media appropriate for surrounding fire.

FIRE AND EXPLOSION HAZARD :

Not flammable but can act as an oxidizing agent, enhancing the burning rate of other materials. May evolve chlorine under fire conditions. May evolve HCl under fire conditions. Hypochlorous acid Nalco Company 1601 W. Diehl Road

Naperville, Illinois 60563-1198 * (630)305-1000 For additional copies of an MSDS visit www.nalco.com and request access 2 / 10 CPNPP NRC 2012 JPM SA5 Document Rev d

CPNPP NRC 2012 JPM SA5 Document Rev d MATERIAL SAFETY DATA SHEET PRODUCT R-50650 Sodium Hypochlorite, 12.5%

EMERGENCY TELEPHONE NUMBER(S)

(800) 424-9300 (24 Hours) CHEMTREC SPECIAL PROTECTIVE EQUIPMENT FOR FIRE FIGHTING :

In case of fire, wear a full face positive-pressure self contained breathing apparatus and protective suit.

6. ACCIDENTAL RELEASE MEASURES PERSONAL PRECAUTIONS :

Restrict access to area as appropriate until clean-up operations are complete. Use personal protective equipment recommended in Section 8 (Exposure Controls/Personal Protection). Stop or reduce any leaks if it is safe to do so.

Ventilate spill area if possible. Ensure clean-up is conducted by trained personnel only. Do not touch spilled material. Have emergency equipment (for fires, spills, leaks, etc.) readily available. Notify appropriate government, occupational health and safety and environmental authorities.

METHODS FOR CLEANING UP :

SMALL SPILLS: Soak up spill with absorbent material. Place residues in a suitable, covered, properly labeled container. Wash affected area. LARGE SPILLS: Contain liquid using absorbent material, by digging trenches or by diking. Reclaim into recovery or salvage drums or tank truck for proper disposal. Clean contaminated surfaces with water or aqueous cleaning agents. Contact an approved waste hauler for disposal of contaminated recovered material. Dispose of material in compliance with regulations indicated in Section 13 (Disposal Considerations).

ENVIRONMENTAL PRECAUTIONS :

Do not contaminate surface water.

7. HANDLING AND STORAGE HANDLING :

Do not get in eyes, on skin, on clothing. Do not take internally. Use with adequate ventilation. Do not breathe vapors/gases/dust. Keep the containers closed when not in use. Have emergency equipment (for fires, spills, leaks, etc.) readily available. Ensure all containers are labeled. Do not mix with acids.

STORAGE CONDITIONS :

Store in suitable labeled containers. Store the containers tightly closed. Store separately from acids.

SUITABLE CONSTRUCTION MATERIAL :

Compatibility with Plastic Materials can vary; we therefore recommend that compatibility is tested prior to use.

8. EXPOSURE CONTROLS/PERSONAL PROTECTION OCCUPATIONAL EXPOSURE LIMITS :

Exposure guidelines have not been established for this product. Available exposure limits for the substance(s) are shown below.

ACGIH/TLV :

Substance(s)

Sodium Hydroxide CEILING: 2 mg/m3 OSHA/PEL :

Substance(s)

Sodium Hydroxide CEILING: 2 mg/m3 Nalco Company 1601 W. Diehl Road

Naperville, Illinois 60563-1198 * (630)305-1000 For additional copies of an MSDS visit www.nalco.com and request access 3 / 10 CPNPP NRC 2012 JPM SA5 Document Rev d

CPNPP NRC 2012 JPM SA5 Document Rev d MATERIAL SAFETY DATA SHEET PRODUCT R-50650 Sodium Hypochlorite, 12.5%

EMERGENCY TELEPHONE NUMBER(S)

(800) 424-9300 (24 Hours) CHEMTREC ENGINEERING MEASURES :

General ventilation is recommended.

RESPIRATORY PROTECTION :

Where concentrations in air may exceed the limits given in this section, the use of a half face filter mask or air supplied breathing apparatus is recommended. A suitable filter material depends on the amount and type of chemicals being handled. Consider the use of filter type: Acid gas cartridge. with a Particulate pre-filter. In event of emergency or planned entry into unknown concentrations a positive pressure, full-facepiece SCBA should be used. If respiratory protection is required, institute a complete respiratory protection program including selection, fit testing, training, maintenance and inspection.

HAND PROTECTION :

When handling this product, the use of chemical gauntlets is recommended., The choice of work glove depends on work conditions and what chemicals are handled, but we have positive experience under light handling conditions using gloves made from, PVC, ., Gloves should be replaced immediately if signs of degradation are observed.,

Breakthrough time not determined as preparation, consult PPE manufacturers.

SKIN PROTECTION :

When handling this product, the use of overalls, a chemical resistant apron and rubber boots is recommended. A full slicker suit is recommended if gross exposure is possible.

EYE PROTECTION :

Wear a face shield with chemical splash goggles.

HYGIENE RECOMMENDATIONS :

Use good work and personal hygiene practices to avoid exposure. Keep an eye wash fountain available. Keep a safety shower available. If clothing is contaminated, remove clothing and thoroughly wash the affected area.

Launder contaminated clothing before reuse. Always wash thoroughly after handling chemicals. When handling this product never eat, drink or smoke.

9. PHYSICAL AND CHEMICAL PROPERTIES PHYSICAL STATE Liquid APPEARANCE Clear Light yellow Green ODOR Chlorine SPECIFIC GRAVITY 1.22 DENSITY 10.2 lb/gal SOLUBILITY IN WATER Complete pH () 12.5 FREEZING POINT 8.0 °F / -13.3 °C VOC CONTENT 0.0 % Calculated Note: These physical properties are typical values for this product and are subject to change.

Nalco Company 1601 W. Diehl Road

Naperville, Illinois 60563-1198 * (630)305-1000 For additional copies of an MSDS visit www.nalco.com and request access 4 / 10 CPNPP NRC 2012 JPM SA5 Document Rev d

CPNPP NRC 2012 JPM SA5 Document Rev d MATERIAL SAFETY DATA SHEET PRODUCT R-50650 Sodium Hypochlorite, 12.5%

EMERGENCY TELEPHONE NUMBER(S)

(800) 424-9300 (24 Hours) CHEMTREC

10. STABILITY AND REACTIVITY STABILITY :

Stable under normal conditions.

HAZARDOUS POLYMERIZATION :

Hazardous polymerization will not occur.

CONDITIONS TO AVOID :

Avoid extremes of temperature.

MATERIALS TO AVOID :

Acids Contact with strong acids (e.g. sulfuric, phosphoric, nitric, hydrochloric, chromic, sulfonic) may generate heat, splattering or boiling and toxic vapors. Contact with organic materials (e.g. rags, sawdust, hydrocarbon oils or solvents) and avoid reducing agents (e.g. hydrazine, sulfites, sulfide, aluminum or magnesium dust) which can generate heat, fires, explosions and the release of toxic fumes. Metals HAZARDOUS DECOMPOSITION PRODUCTS :

Under fire conditions: Chlorine gas, HCl, May evolve toxic fumes.

11. TOXICOLOGICAL INFORMATION No toxicity studies have been conducted on this product.

SENSITIZATION :

This product is not expected to be a sensitizer.

CARCINOGENICITY :

None of the substances in this product are listed as carcinogens by the International Agency for Research on Cancer (IARC), the National Toxicology Program (NTP) or the American Conference of Governmental Industrial Hygienists (ACGIH).

12. ECOLOGICAL INFORMATION ECOTOXICOLOGICAL EFFECTS :

No toxicity studies have been conducted on this product.

MOBILITY :

The environmental fate was estimated using a level III fugacity model embedded in the EPI (estimation program interface) Suite TM, provided by the US EPA. The model assumes a steady state condition between the total input and output. The level III model does not require equilibrium between the defined media. The information provided is intended to give the user a general estimate of the environmental fate of this product under the defined conditions of the models.

If released into the environment this material is expected to distribute to the air, water and soil/sediment in the approximate respective percentages; Air Water Soil/Sediment Nalco Company 1601 W. Diehl Road

Naperville, Illinois 60563-1198 * (630)305-1000 For additional copies of an MSDS visit www.nalco.com and request access 5 / 10 CPNPP NRC 2012 JPM SA5 Document Rev d

CPNPP NRC 2012 JPM SA5 Document Rev d MATERIAL SAFETY DATA SHEET PRODUCT R-50650 Sodium Hypochlorite, 12.5%

EMERGENCY TELEPHONE NUMBER(S)

(800) 424-9300 (24 Hours) CHEMTREC

<5% 30 - 50% 50 - 70%

The portion in water is expected to be soluble or dispersible.

BIOACCUMULATION POTENTIAL This preparation or material is not expected to bioaccumulate.

If released into the environment, see CERCLA/SUPERFUND in Section 15.

13. DISPOSAL CONSIDERATIONS If this product becomes a waste, it could meet the criteria of a hazardous waste as defined by the Resource Conservation and Recovery Act (RCRA) 40 CFR 261. Before disposal, it should be determined if the waste meets the criteria of a hazardous waste.

Hazardous Waste: D002 Hazardous wastes must be transported by a licensed hazardous waste transporter and disposed of or treated in a properly licensed hazardous waste treatment, storage, disposal or recycling facility. Consult local, state, and federal regulations for specific requirements.

14. TRANSPORT INFORMATION The information in this section is for reference only and should not take the place of a shipping paper (bill of lading) specific to an order. Please note that the proper Shipping Name / Hazard Class may vary by packaging, properties, and mode of transportation. Typical Proper Shipping Names for this product are as follows.

The presence of an RQ component (Reportable Quantity for U.S. EPA and DOT) in this product causes it to be regulated with an additional description of RQ for road, or as a class 9 for road and air, ONLY when the net weight in the package exceeds the calculated RQ for the product.

LAND TRANSPORT :

Proper Shipping Name : HYPOCHLORITE SOLUTION Technical Name(s) :

UN/ID No : UN 1791 Hazard Class - Primary : 8 Packing Group : III Flash Point : Not flammable DOT Reportable Quantity (per package) : 900 lbs DOT RQ Component : SODIUM HYPOCHLORITE AIR TRANSPORT (ICAO/IATA) :

Proper Shipping Name : HYPOCHLORITE SOLUTION Technical Name(s) :

Nalco Company 1601 W. Diehl Road

Naperville, Illinois 60563-1198 * (630)305-1000 For additional copies of an MSDS visit www.nalco.com and request access 6 / 10 CPNPP NRC 2012 JPM SA5 Document Rev d

CPNPP NRC 2012 JPM SA5 Document Rev d MATERIAL SAFETY DATA SHEET PRODUCT R-50650 Sodium Hypochlorite, 12.5%

EMERGENCY TELEPHONE NUMBER(S)

(800) 424-9300 (24 Hours) CHEMTREC UN/ID No : UN 1791 Hazard Class - Primary : 8 Packing Group : III IATA Cargo Packing Instructions : 821 IATA Cargo Aircraft Limit : 60 L (Max net quantity per package)

MARINE TRANSPORT (IMDG/IMO) :

Proper Shipping Name : HYPOCHLORITE SOLUTION Technical Name(s) :

UN/ID No : UN 1791 Hazard Class - Primary : 8 Packing Group : III

15. REGULATORY INFORMATION This section contains additional information that may have relevance to regulatory compliance. The information in this section is for reference only. It is not exhaustive, and should not be relied upon to take the place of an individualized compliance or hazard assessment. Nalco accepts no liability for the use of this information.

NATIONAL REGULATIONS, USA :

OSHA HAZARD COMMUNICATION RULE, 29 CFR 1910.1200 :

Based on our hazard evaluation, the following substance(s) in this product is/are hazardous and the reason(s) is/are shown below.

Sodium Hypochlorite : Corrosive, Oxidizer Sodium Hydroxide : Corrosive CERCLA/SUPERFUND, 40 CFR 117, 302 :

This product contains the following Reportable Quantity (RQ) Substance. Also listed is the RQ for the product. If a reportable quantity of product is released, it requires notification to the NATIONAL RESPONSE CENTER, WASHINGTON, D.C. (1-800-424-8802).

RQ Substance RQ Sodium Hypochlorite 900 lbs SARA/SUPERFUND AMENDMENTS AND REAUTHORIZATION ACT OF 1986 (TITLE III) - SECTIONS 302, 311, 312, AND 313 :

SECTION 302 - EXTREMELY HAZARDOUS SUBSTANCES (40 CFR 355) :

This product does not contain substances listed in Appendix A and B as an Extremely Hazardous Substance.

SECTIONS 311 AND 312 - MATERIAL SAFETY DATA SHEET REQUIREMENTS (40 CFR 370) :

Our hazard evaluation has found this product to be hazardous. The product should be reported under the following indicated EPA hazard categories:

X Immediate (Acute) Health Hazard Delayed (Chronic) Health Hazard Nalco Company 1601 W. Diehl Road

Naperville, Illinois 60563-1198 * (630)305-1000 For additional copies of an MSDS visit www.nalco.com and request access 7 / 10 CPNPP NRC 2012 JPM SA5 Document Rev d

CPNPP NRC 2012 JPM SA5 Document Rev d MATERIAL SAFETY DATA SHEET PRODUCT R-50650 Sodium Hypochlorite, 12.5%

EMERGENCY TELEPHONE NUMBER(S)

(800) 424-9300 (24 Hours) CHEMTREC Fire Hazard Sudden Release of Pressure Hazard Reactive Hazard Under SARA 311 and 312, the EPA has established threshold quantities for the reporting of hazardous chemicals.

The current thresholds are: 500 pounds or the threshold planning quantity (TPQ), whichever is lower, for extremely hazardous substances and 10,000 pounds for all other hazardous chemicals.

SECTION 313 - LIST OF TOXIC CHEMICALS (40 CFR 372) :

This product does not contain substances on the List of Toxic Chemicals.

TOXIC SUBSTANCES CONTROL ACT (TSCA) :

The substances in this preparation are included on or exempted from the TSCA 8(b) Inventory (40 CFR 710)

FEDERAL WATER POLLUTION CONTROL ACT, CLEAN WATER ACT, 40 CFR 401.15 / formerly Sec. 307, 40 CFR 116.4 / formerly Sec. 311 :

This product contains the following substances listed in the regulation:

Substance(s) Citations

Sodium Hypochlorite Sec. 311

Sodium Hydroxide CLEAN AIR ACT, Sec. 112 (40 CFR 61, Hazardous Air Pollutants), Sec. 602 (40 CFR 82, Class I and II Ozone Depleting Substances) :

None of the substances are specifically listed in the regulation.

CALIFORNIA PROPOSITION 65 :

This product does not contain substances which require warning under California Proposition 65.

MICHIGAN CRITICAL MATERIALS :

This product contains the following substances listed in the regulation:

Sodium Hypochlorite STATE RIGHT TO KNOW LAWS :

The following substances are disclosed for compliance with State Right to Know Laws:

Sodium Hypochlorite 7681-52-9 Sodium Hydroxide 1310-73-2 NATIONAL REGULATIONS, CANADA :

WORKPLACE HAZARDOUS MATERIALS INFORMATION SYSTEM (WHMIS) :

This product has been classified in accordance with the hazard criteria of the Controlled Products Regulations (CPR) and the MSDS contains all the information required by the CPR.

WHMIS CLASSIFICATION :

E - Corrosive Material Nalco Company 1601 W. Diehl Road

Naperville, Illinois 60563-1198 * (630)305-1000 For additional copies of an MSDS visit www.nalco.com and request access 8 / 10 CPNPP NRC 2012 JPM SA5 Document Rev d

CPNPP NRC 2012 JPM SA5 Document Rev d MATERIAL SAFETY DATA SHEET PRODUCT R-50650 Sodium Hypochlorite, 12.5%

EMERGENCY TELEPHONE NUMBER(S)

(800) 424-9300 (24 Hours) CHEMTREC CANADIAN ENVIRONMENTAL PROTECTION ACT (CEPA) :

The substance(s) in this preparation are included in or exempted from the Domestic Substance List (DSL).

AUSTRALIA All substances in this product comply with the National Industrial Chemicals Notification & Assessment Scheme (NICNAS).

CHINA All substances in this product comply with the Chemical Control Law and are listed on the Inventory of Existing Chemical Substances China (IECSC).

EUROPE The substances in this preparation have been reviewed for compliance with the EINECS or ELINCS inventories.

JAPAN All substances in this product comply with the Law Regulating the Manufacture and Importation Of Chemical Substances and are listed on the Ministry of International Trade & industry List (MITI).

KOREA All substances in this product comply with the Toxic Chemical Control Law (TCCL) and are listed on the Existing Chemicals List (ECL)

PHILIPPINES All substances in this product comply with the Republic Act 6969 (RA 6969) and are listed on the Philippine Inventory of Chemicals & Chemical Substances (PICCS).

16. OTHER INFORMATION This product material safety data sheet provides health and safety information. The product is to be used in applications consistent with our product literature. Individuals handling this product should be informed of the recommended safety precautions and should have access to this information. For any other uses, exposures should be evaluated so that appropriate handling practices and training programs can be established to insure safe workplace operations. Please consult your local sales representative for any further information.

REFERENCES Threshold Limit Values for Chemical Substances and Physical Agents and Biological Exposure Indices, American Conference of Governmental Industrial Hygienists, OH., (Ariel Insight# CD-ROM Version), Ariel Research Corp.,

Bethesda, MD.

Hazardous Substances Data Bank, National Library of Medicine, Bethesda, Maryland (TOMES CPS# CD-ROM Version), Micromedex, Inc., Englewood, CO.

IARC Monographs on the Evaluation of the Carcinogenic Risk of Chemicals to Man, Geneva: World Health Organization, International Agency for Research on Cancer.

Integrated Risk Information System, U.S. Environmental Protection Agency, Washington, D.C. (TOMES CPS# CD-ROM Version), Micromedex, Inc., Englewood, CO.

Nalco Company 1601 W. Diehl Road

Naperville, Illinois 60563-1198 * (630)305-1000 For additional copies of an MSDS visit www.nalco.com and request access 9 / 10 CPNPP NRC 2012 JPM SA5 Document Rev d

CPNPP NRC 2012 JPM SA5 Document Rev d MATERIAL SAFETY DATA SHEET PRODUCT R-50650 Sodium Hypochlorite, 12.5%

EMERGENCY TELEPHONE NUMBER(S)

(800) 424-9300 (24 Hours) CHEMTREC Annual Report on Carcinogens, National Toxicology Program, U.S. Department of Health and Human Services, Public Health Service.

Title 29 Code of Federal Regulations, Part 1910, Subpart Z, Toxic and Hazardous Substances, Occupational Safety and Health Administration (OSHA), (Ariel Insight# CD-ROM Version), Ariel Research Corp., Bethesda, MD.

Registry of Toxic Effects of Chemical Substances, National Institute for Occupational Safety and Health, Cincinnati, OH, (TOMES CPS# CD-ROM Version), Micromedex, Inc., Englewood, CO.

Ariel Insight# (An integrated guide to industrial chemicals covered under major regulatory and advisory programs),

North American Module, Western European Module, Chemical Inventories Module and the Generics Module (Ariel Insight# CD-ROM Version), Ariel Research Corp., Bethesda, MD.

The Teratogen Information System, University of Washington, Seattle, WA (TOMES CPS# CD-ROM Version),

Micromedex, Inc., Englewood, CO.

Prepared By : Product Safety Department Date issued : 04/30/2008 Version Number : 1.0 Nalco Company 1601 W. Diehl Road

Naperville, Illinois 60563-1198 * (630)305-1000 For additional copies of an MSDS visit www.nalco.com and request access 10 / 10 CPNPP NRC 2012 JPM SA5 Document Rev d

CPNPP NRC 2012 JPM SA5 Procedure Rev d COMANCHE PEAK NUCLEAR POWER PLANT EMERGENCY PLAN MANUAL LEVEL OF USE:

INFORMATION USE ASSESSMENT OF EMERGENCY ACTION LEVELS EMERGENCY CLASSIFICATION AND PLAN ACTIVATION PROCEDURE NO. EPP-201 REVISION NO. 12 SORC Meeting No.: 10-018 Date: 10-14-2010 EFFECTIVE DATE: 11-04-2010 12:00 MAJOR REVISON ELECTRONIC CONTROLLED COPY CHANGES ARE NOT INDICATED LATEST CHANGE NOTICE EFFECTIVE DATE /

Verify current status in the Document Control Database prior to use PREPARED BY: (Print): Gary Wiechering EXT: 0180 TECHNICAL REVIEW BY (Print) Kelly Faver EXT: 5628 APPROVED BY: Steve Sewell DATE: 14-Oct-2010 PLANT MANAGER CPNPP NRC 2012 JPM SA5 Procedure Rev d

CPNPP NRC 2012 JPM SA5 Procedure Rev d CPNPP PROCEDURE NO.

EMERGENCY PLAN MANUAL EPP-201 REVISION NO. 12 ASSESSMENT OF EMERGENCY ACTION LEVELS INFORMATION USE PAGE 2 OF 16 EMERGENCY CLASSIFICATION AND PLAN ACTIVATION 1.0 PURPOSE (C-01882)

This procedure provides guidance to the Shift Manager, TSC Manager, or EOF Manager to assist in the classification of an emergency as either an Unusual Event, Alert, Site Area Emergency, or General Emergency.

2.0 APPLICABILITY This procedure applies to the Shift Manager, TSC Manager, or EOF Manager in the event of an emergency situation at CPNPP.

3.0 DEFINITIONS/ACRONYMS 3.1 Alert - Events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small fractions of the Environmental Protection Agency (EPA) Protection Action Guideline exposure levels. It is the lowest level of classification where near-site or offsite emergency response may be anticipated. For most Alert events, the plant would be brought to a safe condition, and radioactive releases, if any, would be minimal. [C-05703]

3.2 Emergency Action Levels (EALs) - A Pre-determined, Site-specific, observable threshold for a plant Initiating Condition that places the plant in a given emergency class. An EAL can be: an instrument reading; an equipment status indicator; a measurable parameter; a discrete, observable event; or another phenomenon which, if it occurs, indicates entry into a particular emergency class.

3.3 Emergency Classification - A classification system of emergency severity based on projected or confirmed initiating conditions/emergency action levels. The classes, from least to most severe, are: Unusual Event, Alert, Site Area Emergency and General Emergency.

3.4 Emergency Conditions - Situations which occur that can cause or may threaten to cause hazards affecting the health and safety of employees or the public, or which may result in damage to property.

CPNPP NRC 2012 JPM SA5 Procedure Rev d

CPNPP NRC 2012 JPM SA5 Procedure Rev d CPNPP PROCEDURE NO.

EMERGENCY PLAN MANUAL EPP-201 REVISION NO. 12 ASSESSMENT OF EMERGENCY ACTION LEVELS INFORMATION USE PAGE 3 OF 16 EMERGENCY CLASSIFICATION AND PLAN ACTIVATION 3.5 General Emergency - The General Emergency classification reflects accident situations involving actual or imminent substantial core degradation or melting with the potential for loss of containment integrity or the potential loss of reactor coolant system integrity.

Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area. [C-05705]

3.6 Site Area Emergency - Events are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of the public. Any releases are not expected to exceed EPA Protective Action Guideline exposure levels except within the site boundary. [C-05704]

3.7 Unusual Event - Unusual events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant. No releases of radioactive material requiring offsite response or monitoring are expected for this classification unless further degradation of safety systems occur. [C-05702]

4.0 INSTRUCTIONS 4.1 General Instructions NOTE: For the purposes of this procedure, the title Emergency Coordinator is used generically to refer to the position with responsibility for emergency classifications, even though the Emergency Coordinator may not always have this responsibility.

4.1.1 In most cases the decision to declare, upgrade, or proceed to recovery/closeout of an emergency rests with the Emergency Coordinator.

When the EOF Manager is the Emergency Coordinator, he may elect to have the TSC Manager retain responsibility for assessing, classifying, and declaring an emergency condition.

4.1.2 The Emergency Action Level Technical Bases Document and the Emergency Action Level Classification Matrix, cites specific conditions that denote whether the emergency is to be classified as an Unusual Event, Alert, Site Area Emergency or General Emergency. The Emergency Action Level Classification Matrix is provided as guidance to assist the Emergency Coordinator in making that decision. In many cases, a very general statement has been used to denote the emergency action level (EAL) on the Emergency Action Level Classification Matrix. This was done to allow the Emergency Coordinator flexibility to assess any undefinable parameters which may exist. [C-05327]

CPNPP NRC 2012 JPM SA5 Procedure Rev d

CPNPP NRC 2012 JPM SA5 Procedure Rev d CPNPP PROCEDURE NO.

EMERGENCY PLAN MANUAL EPP-201 REVISION NO. 12 ASSESSMENT OF EMERGENCY ACTION LEVELS INFORMATION USE PAGE 4 OF 16 EMERGENCY CLASSIFICATION AND PLAN ACTIVATION 4.1.3 Plant-specific operator actions required to mitigate the emergency condition are prescribed in the appropriate Abnormal Conditions Procedures or Emergency Operating Procedures (ABNs or EOPs) and are independent of any actions required by this Emergency Plan Procedure.

4.2 Use of the EAL Classification Matrix 4.2.1 The CPNPP EAL scheme includes the following features:

4.2.1.1 Division of the EAL set into three broad groups:

EALs applicable under all plant operating modes - This group would be reviewed by the EAL-user any time emergency classification is considered.

EALs applicable only under hot operating modes - This group would only be reviewed by the EAL-user when the plant is in Hot Shutdown, Hot Standby, Startup, or Power Operation mode.

EALs applicable only under cold operating modes - This group would only be reviewed by the EAL-user when the plant is in Cold Shutdown, Refueling or Defueled mode.

4.2.1.2 The purpose of the groups is to avoid review of hot condition EALs when the plant is in a cold condition and avoid review of cold condition EALs when the plant is in a hot condition. This approach significantly minimizes the total number of EALs that must be reviewed by the EAL-user for a given plant condition, reduces EAL-user reading burden and, thereby, speeds identification of the EAL that applies to the emergency.

4.2.1.3 Within each of the above three groups, assignment of EALs to categories/subcategories - Category and subcategory titles are selected to represent conditions that are operationally significant to the EAL-user.

4.2.1.4 Subcategories are used as necessary to further divide the EALs of a category into logical sets of possible emergency classification thresholds. The CPNPP EAL categories/subcategories are listed below.

CPNPP NRC 2012 JPM SA5 Procedure Rev d

CPNPP NRC 2012 JPM SA5 Procedure Rev d CPNPP PROCEDURE NO.

EMERGENCY PLAN MANUAL EPP-201 REVISION NO. 12 ASSESSMENT OF EMERGENCY ACTION LEVELS INFORMATION USE PAGE 5 OF 16 EMERGENCY CLASSIFICATION AND PLAN ACTIVATION EAL Groups, Categories and Subcategories EAL Group/Category EAL Subcategory Any Operating Mode:

R - Abnormal Rad Release / Rad Effluent 1 - Offsite Rad Conditions 2 - Onsite Rad Conditions & Spent Fuel Events 3 - CR/CAS Rad H - Hazards 1 - Natural or Destructive Phenomena 2 - Fire or Explosion 3 - Hazardous Gas 4 - Security 5 - Control Room Evacuation 6 - Judgment E - ISFSI None Hot Conditions:

S - System Malfunction 1 - Loss of AC Power 2 - Loss of DC Power 3 - Criticality & RPS Failure 4 - Inability to Reach or Maintain Shutdown Conditions 5 - Instrumentation 6 -Communications 7 - Fuel Clad Degradation 8 - RCS Leakage F - Fission Product Barrier Degradation None Cold Conditions:

C - Cold Shutdown / Refueling System 1 - Loss of AC Power Malfunction 2 - Loss of DC Power 3 - RCS Level 4 - RCS Temperature 5 - Communications 6 - Inadvertent Criticality CPNPP NRC 2012 JPM SA5 Procedure Rev d

CPNPP NRC 2012 JPM SA5 Procedure Rev d CPNPP PROCEDURE NO.

EMERGENCY PLAN MANUAL EPP-201 REVISION NO. 12 ASSESSMENT OF EMERGENCY ACTION LEVELS INFORMATION USE PAGE 6 OF 16 EMERGENCY CLASSIFICATION AND PLAN ACTIVATION 4.2.1.5 The primary tool for determining the emergency classification level is the EAL Classification Matrix.

To help in determining the EAL Classification, color coded copies of the EAL Classification Matrix are maintained in the Control Room, the Technical Support Center, and the Emergency Operations Facility and selected other locations.

4.2.1.6 The user of the EAL Classification Matrix may consult the EAL Technical Bases Document in order to obtain additional information concerning the EALs under classification consideration.

4.2.2 Fission Product Barrier Loss/Potential Loss Matrix and Bases 4.2.2.1 If a cell in the Fission Product Barrier Matrix contains more than one numbered threshold, each of the numbered thresholds, if exceeded, signifies a Loss or Potential Loss of the barrier. It is not necessary to exceed all of the thresholds in a category before declaring a barrier Loss/Potential Loss.

4.2.2.2 Subdivision of the Fission Product Barrier Matrix by category facilitates association of plant conditions to the applicable fission product barrier Loss and Potential Loss thresholds. This structure promotes a systematic approach to assessing the classification status of the fission product barriers.

4.2.2.3 When equipped with knowledge of plant conditions related to the fission product barriers, the EAL-user first scans down the category column of the Fission Product Barrier Matrix, locates the likely category and then reads across the row of fission product barrier Loss and Potential Loss thresholds in that category to determine if any threshold has been exceeded. If a threshold has not been exceeded in that category row, the EAL-user proceeds to the next likely category and continues review of the row of thresholds in the new category 4.2.2.4 If the EAL-user determines that a Loss threshold has been exceeded, a check mark or circle may be placed in or around the threshold box for the Loss column. This signifies that the threshold barrier is lost.

Similarly, this is done for a Potential Loss threshold that has been exceeded.

CPNPP NRC 2012 JPM SA5 Procedure Rev d

CPNPP NRC 2012 JPM SA5 Procedure Rev d CPNPP PROCEDURE NO.

EMERGENCY PLAN MANUAL EPP-201 REVISION NO. 12 ASSESSMENT OF EMERGENCY ACTION LEVELS INFORMATION USE PAGE 7 OF 16 EMERGENCY CLASSIFICATION AND PLAN ACTIVATION 4.2.2.5 The EAL-user must examine each of the three fission product barriers to determine if other barrier thresholds in the category are lost or potentially lost. For example, if Containment radiation is sufficiently high (i.e., greater than 4,000 R/hr), a Loss of the Fuel Clad and RCS barriers and a Potential Loss of the Containment barrier exist. Barrier Losses and Potential Losses are then applied to the algorithms given in EALs FG1.1, FS1.1, FA1.1 and FU1.1 to determine the appropriate emergency classification.

4.2.3 Classifying Transient Events 4.2.3.1 The key consideration during a Transient Event is to determine whether or not further plant damage occurred while the corrective actions were being taken. In some situations, this can be readily determined, in other situations, further analyses may be necessary (e.g., coolant radiochemistry following an ATWT event, plant structural examination following an earthquake, etc.). Classify the event as indicated and terminate the emergency once assessment shows that there were no consequences from the event and other termination criteria are met.

4.2.3.2 Existing guidance for classifying transient events addresses the period of time of event recognition and classification (15 minutes).

However, in cases when EAL declaration criteria may be met momentarily during the normal expected response of the plant, declaration requirements should not be considered to be met when the conditions are a part of the designed plant response, or result from appropriate Operator actions.

4.2.3.3 There may be cases in which a plant condition that exceeded an EAL was not recognized at the time of occurrence but is identified well after the condition has occurred (e.g., as a result of routine log or record review), and the condition no longer exists. In these cases, an emergency should not be declared. Reporting requirements of 10 CFR 50.72 are applicable and the guidance of NUREG-1022, Event Reporting Guidelines 10 CFR 50.72 and 50.73, should be applied.

CPNPP NRC 2012 JPM SA5 Procedure Rev d

CPNPP NRC 2012 JPM SA5 Procedure Rev d CPNPP PROCEDURE NO.

EMERGENCY PLAN MANUAL EPP-201 REVISION NO. 12 ASSESSMENT OF EMERGENCY ACTION LEVELS INFORMATION USE PAGE 8 OF 16 EMERGENCY CLASSIFICATION AND PLAN ACTIVATION 4.2.4 Multiple Events and Classification Upgrading/Downgrading 4.2.4.1 When multiple simultaneous events occur, the emergency classification level is based on the highest EAL reached.

For example, two Alerts remain in the Alert category. Or, an Alert and a Site Area Emergency is a Site Area Emergency. Emergency classification level upgrading for multi-unit stations such as CPNPP with shared safety-related systems and functions must also consider the effects of a loss of a common system on more than one unit (e.g.

potential for radioactive release from more than one core at the same site).

4.3 Emergency Classification Initial Actions [C-08621]

NOTE: Once indication of an abnormal condition is available, classification declaration must be made within 15 minutes. This time is available to ensure that the classification and subsequent actions associated with the classification, if warranted, are appropriate. It does not allow a delay of 15 minutes if the classification is recognized to be necessary.

It is meant to provide sufficient time to accurately assess the emergency conditions and then evaluate the need for an emergency classification based on the assessment performed. The decision to terminate the event or enter Recovery is NOT time independent.

NOTE: IF a higher classification is made prior to transmitting an event notification, THEN notification for the higher classification can supersede the event notification, provided that it can be performed within the 15-minute timeframe of the previous event. IF the notification of the higher classification cannot be performed within the 15-minute timeframe of the previous event classification, THEN the previous event notification is required within its 15-minute timeframe, and the subsequent event notification is required within its 15-minute timeframe.

CAUTION: Shutdown and outage conditions should be given special consideration since they will likely create abnormalities such as the loss of containment integrity or loss of the RCS pressure boundary (refueling, mid-loop operations, equipment hatch open, etc.). These types of boundary breaches combined with a plant transient (loss of AC power, etc.) may create a worse situation than would be expected if the Unit was at power.

CPNPP NRC 2012 JPM SA5 Procedure Rev d

CPNPP NRC 2012 JPM SA5 Procedure Rev d CPNPP PROCEDURE NO.

EMERGENCY PLAN MANUAL EPP-201 REVISION NO. 12 ASSESSMENT OF EMERGENCY ACTION LEVELS INFORMATION USE PAGE 9 OF 16 EMERGENCY CLASSIFICATION AND PLAN ACTIVATION 4.3.1 Upon recognition that an abnormal or emergency condition exists, the Shift Manager shall be immediately notified.

4.3.2 Operators shall refer to the appropriate ABNs or EOPs and take actions based upon the indicated symptoms.

4.3.3 The Shift Manager shall evaluate the conditions to determine the need for classifying into one of the four (4) Emergency Classification levels.

4.3.4 If the conditions do not fit any of the general descriptions on the EAL Classification Matrix, the Shift Manager should evaluate the conditions and, if appropriate, classify the emergency based upon professional judgment. If classification is not warranted, no further action is required except to continue monitoring the event.

4.3.5 If the on-duty Shift Manager determines that the conditions fit one or more of the Emergency Classifications shown on the matrix, the Shift Manager shall assume the role of Emergency Coordinator as prescribed in Procedure EPP-109, Duties and Responsibilities of the Emergency Coordinator/Recovery Manger and consult his Position Assistant Document (PAD) for further actions. [C-05687, 01278]

4.3.6 When an abnormal or emergency condition is being evaluated, REFER to the EAL Classification Matrix and PERFORM the following:

IDENTIFY the Unit Mode for the state of the plant prior to the abnormal condition (Operating Modes are identified in respective EALs).

REVIEW the Initiating Conditions applicable to the operating mode as follows.

- Starting with the highest (General Emergency) classification level on the left side of the matrix and continue to the lowest (Unusual Event) classification level on the right side of the matrix.

- If more than one Initiating Conditions applies to the event, THEN SELECT the Initiating Conditions for the highest classification (from all of the Initiating Conditions that were determined to have been met).

CPNPP NRC 2012 JPM SA5 Procedure Rev d

CPNPP NRC 2012 JPM SA5 Procedure Rev d CPNPP PROCEDURE NO.

EMERGENCY PLAN MANUAL EPP-201 REVISION NO. 12 ASSESSMENT OF EMERGENCY ACTION LEVELS INFORMATION USE PAGE 10 OF 16 EMERGENCY CLASSIFICATION AND PLAN ACTIVATION

REVIEW the EAL Threshold Values for the Initiating Conditions.

- If the EAL Threshold Values have been met or exceeded, THEN:

- NOTE the EAL number associated with the Initiating Conditions.

- DECLARE the event. For events affecting both Units, the highest classification on either Unit shall be declared.

4.4 Subsequent Actions [C-05701]

The Shift Manager or Emergency Coordinator shall continually monitor plant conditions and compare the current plant conditions to the EAL Classification Matrix to determine whether a change in emergency classification is warranted and whether to escalate the emergency classification or proceed to EPP-121, Reentry, Recovery and Closeout.

CPNPP NRC 2012 JPM SA5 Procedure Rev d

CPNPP NRC 2012 JPM SA5 Procedure Rev d CPNPP PROCEDURE NO.

EMERGENCY PLAN MANUAL EPP-201 REVISION NO. 12 ASSESSMENT OF EMERGENCY ACTION LEVELS INFORMATION USE PAGE 11 OF 16 EMERGENCY CLASSIFICATION AND PLAN ACTIVATION

5.0 REFERENCES

5.1 Emergency Action Level Technical Bases Document 5.2 CPNPP Emergency Plan, Section 2.0 5.3 EPP-109, Duties and Responsibilities of the Emergency Coordinator/Recovery Manager 5.4 NUREG-0654/FEMA-REP-1, Rev. 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 5.5 10CFR, Part 50.72, Notification of Significant Events 5.6 NEI 99-01 Rev. 5 5.7 CPSES FSAR Chapter 15 5.8 EPP-121, Reentry, Recovery and Closeout 6.0 ATTACHMENTS/FORMS 6.1 Attachments 6.1.1 Attachment 1, Initiating Condition Table 6.1.2 Attachment 2, EAL Classification Matrix 6.1.3 Attachment 3, EAL Technical Bases Document 6.2 Forms None CPNPP NRC 2012 JPM SA5 Procedure Rev d

CPNPP NRC 2012 JPM SA5 Procedure Rev d CPNPP PROCEDURE NO.

EMERGENCY PLAN MANUAL EPP-201 REVISION NO. 12 ASSESSMENT OF EMERGENCY ACTION LEVELS INFORMATION USE PAGE 12 OF 16 EMERGENCY CLASSIFICATION AND PLAN ACTIVATION Attachment 1 Initiating Condition Table

[C-05327, 05701, 05702, 05703, 05704, 05705, 09308, 26728]

Page 1 of 2 Categories GE SAE Alert UE ALL Modes Offsite Rad Offsite Rad Offsite Rad Offsite Rad Abnormal Rad Conditions Conditions Conditions Conditions Release / Rad Onsite Rad Conditions Onsite Rad Conditions Effluent (R) & Spent Fuel Events & Spent Fuel Events CR/CAS Rad Natural or Destructive Natural or Destructive Phenomena Phenomena Fire or Explosion Fire or Explosion Hazardous Gas Hazardous Gas Hazards (H)

Security Security Security Security Control Room Control Room Evacuation Evacuation Judgment Judgment Judgment Judgment ISFSI ISFSI Categories GE SAE Alert UE HOT Conditions Loss of AC Loss of AC Loss of Loss of Power Power AC Power AC Power Loss of DC Power Criticality & Criticality & Criticality & Criticality &

RPS Failure RPS Failure RPS Failure RPS Failure System Inability to Reach or Malfunctions (S)

Maintain Shutdown Conditions Instrumentation Instrumentation Instrumentation Communication Fuel Clad Degradation RCS Leakage Fission Product Fission Fission Product Fission Product Fission Product Barriers (F) Product Barriers Barriers Barriers Barriers CPNPP NRC 2012 JPM SA5 Procedure Rev d

CPNPP NRC 2012 JPM SA5 Procedure Rev d CPNPP PROCEDURE NO.

EMERGENCY PLAN MANUAL EPP-201 REVISION NO. 12 ASSESSMENT OF EMERGENCY ACTION LEVELS INFORMATION USE PAGE 13 OF 16 EMERGENCY CLASSIFICATION AND PLAN ACTIVATION Attachment 1 Initiating Condition Table

[C-05327, 05701, 05702, 05703, 05704, 05705, 09308, 26728]

Page 2 of 2 Categories GE SAE Alert UE COLD Conditions Loss of AC Power Loss of AC Power Loss of DC Power Cold SD / RCS Level RCS Level RCS Level RCS Level Refueling System RCS Temp. RCS Temp.

Malfunct. (C) Communication Inadvertent Criticality CPNPP NRC 2012 JPM SA5 Procedure Rev d

CPNPP NRC 2012 JPM SA5 Procedure Rev d CPNPP PROCEDURE NO.

EMERGENCY PLAN MANUAL EPP-201 REVISION NO. 12 ASSESSMENT OF EMERGENCY ACTION LEVELS INFORMATION USE PAGE 14 OF 16 EMERGENCY CLASSIFICATION AND PLAN ACTIVATION Attachment 2 EAL Classification Matrix Page 1 of 2 The following EAL Classification Matrix is an example only. There are larger versions of EAL Classification Matrix, which are color coded to help in the determination of the classifications in the Control Room, Technical Support Center, Emergency Operations Facility and selected other locations.

EXAMPLE All Modes / Hot Conditions CPNPP NRC 2012 JPM SA5 Procedure Rev d

CPNPP NRC 2012 JPM SA5 Procedure Rev d CPNPP PROCEDURE NO.

EMERGENCY PLAN MANUAL EPP-201 REVISION NO. 12 ASSESSMENT OF EMERGENCY ACTION LEVELS INFORMATION USE PAGE 15 OF 16 EMERGENCY CLASSIFICATION AND PLAN ACTIVATION Attachment 2 EAL Classification Matrix Page 2 of 2 EXAMPLE All Modes / Cold Conditions CPNPP NRC 2012 JPM SA5 Procedure Rev d

CPNPP NRC 2012 JPM SA5 Procedure Rev d CPNPP PROCEDURE NO.

EMERGENCY PLAN MANUAL EPP-201 REVISION NO. 12 ASSESSMENT OF EMERGENCY ACTION LEVELS INFORMATION USE PAGE 16 OF 16 EMERGENCY CLASSIFICATION AND PLAN ACTIVATION Attachment 3 EAL Technical Bases Document Page 1 of 1 The EAL Technical Bases Document is a stand alone document that provides an explanation and rationale for each Emergency Action Level (EAL). Decision-makers responsible for implementation of EPP-201, Assessment of Emergency Action Levels, Emergency Classification and Plan Activation, may use this document as a technical reference in support of EAL interpretation. This information may assist the Emergency Coordinator in making classifications, particularly those involving judgment or multiple events. Below is the Table of Contents for the EAL Technical Bases Document Section 1.0 PURPOSE 2.0 DISCUSSION

2.1 Background

2.2 Fission Product Barriers 2.3 Emergency Classification Based on Fission Product Barrier Degradation 2.4 EAL Relationship to ERGs 2.5 Symptom-Based vs. Event-Based Approach 2.6 EAL Organization 2.7 Technical Bases Information 2.8 Operating Mode Applicability 2.9 Validation of Indications, Reports and Conditions 2.10 Planned vs. Unplanned Events 2.11 Classifying Transient Events 2.12 Imminent EAL Thresholds 2.13 Multiple Events and Classification Upgrading/Downgrading 2.14 Unit Designation

3.0 REFERENCES

3.1 Developmental 3.2 Implementing 3.3 Commitments 4.0 DEFINITIONS 5.0 CPNPP-TO-NEI 99-01 EAL CROSSREFERENCE 6.0 ATTACHMENTS 6.1 Attachment 1 - Emergency Action Level Technical Bases 6.2 Attachment 2 - Fission Product Barrier Loss / Potential Loss Matrix and Bases CPNPP NRC 2012 JPM SA5 Procedure Rev d

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5.0 REFERENCES

2.1 Background

3.0 REFERENCES

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