Text

Revision to Emergency Implementing Procedures
	ML16047A255
Person / Time
Site:	Palisades
Issue date:	02/16/2016
From:	Hardy J; Entergy Nuclear Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	PNP 2016-012 EI-1, Rev. 57, EI-12.1, Rev. 19, EI-2.2, Rev. 16, EI-5.0, Rev. 8, EI-6.10, Rev. 7, EI-6.4, Rev. 5, EI-6.6, Rev. 5, EI-6.9, Rev. 8
	Download: ML16047A255 (85)
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=::- Entergy PNP 2016-012 February 16, 2016 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Entergy Nuclear Operations, Inc.

Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043 269.764.2000 Jeffery A. Hardy Regulatory Assurance Manager 10 CFR 50.4(b)(5)

Subject:

Revision to Palisades Nuclear Plant Emergency Implementing Procedures Palisades Nuclear Plant Docket 50-255 License No. DPR-20

Dear Sir or Madam:

In accordance with 10 CFR 50.4(b)(5), enclosed are revisions to Palisades Nuclear Plant (PNP) Emergency Implementing (EI) Procedure EI-1, "Emergency Classification and Actions," EI-2.2, "Emergency Staff Augmentation," EI-5.0, "Reentry," EI-6.4, "Release/Potential Release Determination from Containment High-Range Monitors,"

EI-6.6, Gamma E Determination," EI-6.9, "Automated Dose Assessment Program,"

EI-6.10, "Offsite Dose Calculation - Straight Line Gaussian (Manual Method)," and E 1-12.1, "Personnel Accountability and Assembly." The changes were made in accordance with 10 CFR 50.54(q), and do not decrease the effectiveness of the Emergency Plan.

This letter contains no new commitments and no revisions to existing commitments.

Sincerely, 9~~sJ.

JAH/bed : Palisades Nuclear Plant Emergency Implementing Procedure Revisions CC Administrator, Region III, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC Marsha Fields, Palisades EP Palisades Nuclear Plant Emergency Implementing Procedure Revision EI-1, Revision 57 EI-2.2, Revision 1S EI-5.0, Revision 8 EI-S.4, Revision 5 EI-S.S, Revision 5 EI-S.9, Revision 8 EI-S.10, Revision 7 EI-12.1, Revision 19

Procedure No EI-1 Revision 57 Effective Date 1/26/16 PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: EMERGENCY CLASSIFICATION AND ACTIONS Approved: MEFields for TPHoran Procedure Sponsor I Process Applicability Exclusion New Procedure/Revision Summary:

Editorial, Rev 57 Specific Changes DRN-13-00945, DRN-13-00602 1

D 1/21/16 Date Removed reference to Plant Operating Review Committee and On Site Safety Review Committee under Special Reviews.

Changed ONP-23.1 to AOP-23 Changed ONP-23.2 to AOP-24 Revision. Rev 56 DRN-12-02419 - Added "Habitability" to Attachment 1, item #11 for Alert, Site Area Emergency and General Emergency.

DRN-12-02467 - Changed reference to SOP-34 as a back up method for ERDS Activation to "Ensure ERDS is activated" on Attachment 1, Item #10 for Alert, Site Area Emergency and General Emergency.

Updated Source Document Reference 3.1.11 to NEI 99-01 Revision 5.

Deleted Item 7, Call Duty Station Manager, from Attachment 1 for Unusual Event.

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: EMERGENCY CLASSIFICATION AND ACTIONS Table of Contents Proc No EI-1 Revision 57 Page i 1.0 PERSONNEL RESPONSIBILITIES............................................................................... 1 2.0 PURPOSE...................................................................................................................... 1

3.0 REFERENCES

............................................................................................................... 1 3.1 SOURCE DOCUMENTS................................................................................ 1 3.2 REFERENCE DOCUMENTS......................................................................... 2 3.3 COMMITMENTS............................................................................................ 3 4.0 INITIAL CONDITIONS AND/OR REQUiREMENTS....................................................... 4 5.0 PRECAUTIONS AND LIMITATIONS............................................................................. 5 6.0 EMERGENCY CLASSIFICATION................................................................................. 5 6.1 CLASSIFICATION/RECLASSIFICATION..................................................... 5 6.2 DETERMINATION OF EMERGENCY ACTIONS/NOTIFICATIONS.............. 7 7.0 ATTACHMENTS............................................................................................................ 8 8.0 SPECIAL REVIEWS...................................................................................................... 8 ATTACHMENTS, "Emergency Actions/Notifications"

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: EMERGENCY CLASSIFICATION AND ACTIONS REFERENCE USE Procedure and Procedure Precautions and Limitations are at the work location for reference.

Proc No EI-1 Revision 57 Page 1 of 8 Review and understand segments before performing any steps.

Signoff steps are completed, when included, before starting the next step.

Place keep in accordance with EN-HU-106, "Procedure and Work Instruction Use and Adherence."

Review the Procedure to verify segments have been completed.

1.0 PERSONNEL RESPONSIBILITIES 1.1 The Shift Manager shall implement this procedure and assume responsibilities of the Site Emergency Plan until relieved by the Emergency Operations Facility Emergency Director.

2.0 PURPOSE To classify those emergency conditions which necessitate the activation to the Site Emergency Plan. To identify actions that should be taken to mitigate the consequences of an emergency.

3.0 REFERENCES

3.1 SOURCE DOCUMENTS 3.1.1 Emergency Operating Procedure EOP-2.0, "Reactor Trip Recovery" 3.1.2 Emergency Operating Procedure EOP-3.0, "Station Blackout Recovery" 3.1.3 Emergency Operating Procedure EOP-5.0, "Steam Generator Tube Rupture Recovery" 3.1.4 Emergency Operating Procedure EOP-6.0, "Excess Steam Demand Event" 3.1.5 Emergency Operating Procedure EOP-7.0, "Loss of All Feedwater Recovery" 3.1.6 Emergency Operating Procedure EOP-8.0, "Loss of Offsite Power/Forced Circulation Recovery" 3.1.7 Emergency Operating Procedure Supplement 12, "'A' S/G SGTR Isolation Checklist"

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: EMERGENCY CLASSIFICATION AND ACTIONS Proc No EI*1 Revision 57 Page 2 of8 3.1.8 Emergency Operating Procedure Supplement 13, B' S/G SGTR Isolation Checklist" 3.1.9 Emergency Operating Procedure Supplement 17, "'A' S/G ESDE Isolation Checklist" 3.1.10 Emergency Operating Procedure Supplement 18, "'B' S/G ESDE Isolation Checklist" 3.1.11 NEI 99-01 Rev 5, "Methodology for Development of Emergency Action Levels" 3.1.12 Palisades Site Emergency Plan 3.1.13 EPPOS No 2, "Emergency Preparedness Position (EPPOS) on Timeliness of Classification of Emergency Conditions" 3.1.14 Engineering Analysis, EA-JBB-01-04, "Failed Fuel Dose Rates on NSSS Piping" 3.1.15 1 OCFR50 Appendix E Section VI - Emergency Response Data System (ERDS) 3.2 REFERENCE DOCUMENTS 3.2.1 Emergency Implementing Procedure EI-2.2, "Emergency Staff Augmentation" 3.2.2 Emergency Implementing Procedure EI-3, "Communications and Notifications" 3.2.3 Emergency Implementing Procedure EI-5.0, "Reentry" 3.2.4 Emergency Implementing Procedure EI-5.1, "Recovery" 3.2.5 Emergency Implementing Procedure EI-6.0, "Rapid Dose Calculation" 3.2.6 Emergency Implementing Procedure EI-6.13, "Protective Action Recommendations for Offsite Populations" 3.2.7 Emergency Implementing Procedure EI-7.0, "Determination of Fuel Failure Using Dose Rates" 3.2.8 Emergency Implementing Procedure EI-8, "Onsite Radiological Monitoring" 3.2.9 Emergency Implementing Procedure EI-9, "Offsite Radiological Monitoring" 3.2.10 Emergency Implementing Procedure EI-10, "Accident Environmental Assessment" 3.2.11 Emergency Implementing Procedure EI-11, "Determination of Extent of Core Damage"

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: EMERGENCY CLASSIFICATION AND ACTIONS Proc No EI-1 Revision 57 Page 30f8 3.2.12 Emergency Implementing Procedure EI-12.1, "Personnel Accountability and Assembly" 3.2.13 Emergency Implementing Procedure EI-13, "Evacuation/Reassembly" 3.2.14 Entergy Procedure EN-U-102, "Corrective Action Program" 3.2.15 Palisades Administrative Procedure 4.00, "Operations Organization, Responsibilities and Conduct" 3.2.16 Abnormal Operating Procedure AOP-23, "Primary Coolant Leak" 3.2.17 Abnormal Operating Procedure AOP-24, "Steam Generator Tube Leak" 3.2.18 Fire Protection Implementing Procedures (FPIPs) 3.2.19 Severe Accident Management Guidelines (SAMG) 3.2.20 Entergy Procedure EN-EP-305, "Emergency Planning 10CFR50.54(q) Program" 3.2.21 Emergency Planning Job Aid GEN-032, "Emergency Response Data System (EROS) Activation Instructions-Control Room" 3.2.22 SEP SUPP 1, "Site Emergency Plan Supplement 1 - EAL Wall Charts" 3.2.23 EAL Technical Basis Document 3.2.24 Entergy Procedure EN-HU-106, "Procedure and Work Instruction Use and Adherence" 3.3 COMMITMENTS CMT902000021, CMT902000428, and CMT922001158 provide for the action to implement the Emergency Response Data System.

CMT912000770 and CMT01201 0971 provide for the action to operate the Public Address System at an Unusual Event or above and activate the site siren at an Alert or above.

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: EMERGENCY CLASSIFICATION AND ACTIONS 4.0 INITIAL CONDITIONS ANDIOR REQUIREMENTS Proc No EI-1 Revision 57 Page 4of8 4.1 This procedure shall be implemented when an event occurs or conditions exist which, in the opinion of the Shift Manager, may require activation of the Site Emergency Plan (SEP).

When events occur or conditions exist after the activation of the SEP that, in the opinion of the Shift Manager or Emergency Director, may require reclassification, either upgrading or downgrading.

4.2 The assessment, classification, and declaration of an emergency condition is expected to be completed within 15 minutes after the availability of indications (ie, plant instrumentation, plant alarms, computer displays, or incoming verbal reports) to plant operators that an EAL has been exceeded.

The 15-minute criterion is not to be construed as a grace period to restore plant conditions to avoid declaring the event.

The emergency declaration should be made promptly without waiting for the 15-minute period to elapse once the EAL is recognized as being exceeded.

For EALs that specify duration of the off-normal condition, such as fire lasting 15 minutes, loss of power for 15 minutes, etc:

o The Emergency Director shall make the declaration at the first available opportunity when the time has elapsed (not after an additional 15 minutes).

o The declaration should be made before the EAL is met (time duration has elapsed) when the Emergency Director has information that the off-normal condition will not be corrected within the specified time duration.

4.3 After events are no longer meeting the criteria of SEP Supp 1 "Site Emergency Plan Supplement 1 - EAL Wall Charts," the event classification may be exited or downgraded. If it is not possible to clearly exit an event, refer to Emergency Implementing Procedures EI-5.0, "Reentry," and EI-5.1, "Recovery." Caution should be exercised when exiting or downgrading to avoid premature termination of events.

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: EMERGENCY CLASSIFICATION AND ACTIONS 5.0 PRECAUTIONS AND LIMITATIONS Proc No EI-1 Revision 57 Page 50t8 5.1 Safeguards Contingency Procedures shall be activated if, during event response, signs of tampering, sabotage, or other items of suspicious nature are indicated, or if the event affects security systems (ie, loss of detection systems, loss of communications, etc).

5.2 Security Safeguard measures can only be suspended by a currently licensed on-watch Senior Reactor Operator.

6.0 EMERGENCY CLASSIFICATION REFERENCE USE Procedure and Procedure Precautions and Limitations are at the work location for reference.

Review and understand segments before performing any steps.

Signoff steps are completed, when included, before starting the next step.

Place keep in accordance with EN-HU-106, "Procedure and Work Instruction Use and Adherence."

Review the Procedure to verify segments have been completed.

6.1 CLASSIFICATION/RECLASSIFICATION

a.

Emergencies are grouped into four classifications listed below in order of severity:

1.

Unusual Event Events are in process or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: EMERGENCY CLASSIFICATION AND ACTIONS

2.

Alert Proc No EI-1 Revision 57 Page 6 of8 Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of HOSTILE ACTION.

Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.

3.

Site Area Emergency Events are in process or have occurred which involve an actual or likely major failures of plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to the likely failure of or; (2) that prevent effective access to equipment needed for the protection of the public. Any releases are not expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels beyond the site boundary.

4.

General Emergency Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity or HOSTILE ACTION that results in an actual loss of physical control of the facility. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area.

b.

The Shift Manager or Emergency Director shall classify emergency conditions/events using SEP Supplement 1 as follows:

1.

Determine the Category in which the Initiating Conditions/symptoms best fit from the list of Categories below:

A - Abnormal Rad Levels / Radiological Effluent C - Cold Shutdown / Refueling System Malfunction E - Independent Spent Fuel Storage Installation (ISFSI)

F - Fission Product Barrier Degradation H - Hazards S - System Malfunction

6.2 NOTE:

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: EMERGENCY CLASSIFICATION AND ACTIONS Proc No EI-1 Revision 57 Page70fS

2.

Use the Category identified above and SEP Supplement 1 to determine which Emergency Action Level (EAL) threshold has been exceeded. Move from the highest classification (left) to lowest classification (right) when determining the classification.

3.

Use the EAL Basis Document when necessary for clarification of the EAL.

4.

After events no longer meet the criteria of SEP Supplement 1 the event classification may be exited or downgraded. Caution should be exercised when exiting or downgrading to avoid premature termination of event response.

The Shift Manager or Emergency Director may downgrade the emergency classification when plant and site conditions permit.

Downgrading and termination from an Alert level or above should only be considered after it is understood that plant conditions are stable and will remain so and no releases are in progress or expected. For the Alert or above concurrence with offsite agencies should occur and be obtained prior to downgrading or termination.

DETERMINATION OF EMERGENCY ACTIONS/NOTIFICATIONS The Shift Manager or Emergency Director may assign a person to complete, "Emer enc Actions/Notifications."

a.

Each action may be categorized as either:

1.

Mandatory Actions (M) - Actions that shall be performed within one hour of the declaration of the emergency.

OR

2.

Subsequent Actions (S) - Actions that should be performed in an expeditious manner as conditions, time, and personnel permit.

OR

3.

If Needed Actions (I) - Actions that are not required in every case, but may be needed.

b.

Using the "Action" column of Attachment 1, perform each action as M (Mandatory), S (Subsequent), or I (If Needed).

c.

Each action on Attachment 1 should be initialed when the action is completed.

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: EMERGENCY CLASSIFICATION AND ACTIONS 7.0 ATTACHMENTS 7.1, "Emergency Actions/Notifications" 8.0 SPECIAL REVIEWS Proc No EI-1 Revision 57 Page 8of8 The scope of this procedure does not include activities that require a SO.S9 review.

Therefore, changes to this procedure do not require a SO.S9 review.

Revisions of this procedure require a SO.S4(q) review per Entergy Procedure EN-EP-30S, "Emergency Planning 10CFRSO.S4(q) Program."

Revisions of this procedure that impact Emergency Action Levels will be reviewed and documented by State of Michigan, Van Buren, Allegan and Berrien County personnel.

EVENT TYPE:

ITEM ACTION 1*

M 3*

M 4

M 5

M 8

M 12 I

15 S

16 I

18 I

22 S

EMERGENCY ACTIONS/NOTIFICATIONS UNUSUAL EVENT DESCRIPTION OF ACTION Announce Emergency on PA Activate ERO Notification System to inform ERO of the Unusual Event.

In addition, see Note 4 below Notify Van Buren County (within 15 min of declaration) See Notes 2 and 3 below Notify State of Michigan (within 15 min of declaration) See Notes 2 and 3 below Notify NRC See Note 1 below Activate Safeguards Contingency Procedures Notify Public Affairs See Note 3 below Activate Fire Protection Plan Notify Covert Fire Dept and Call Security Initiate Condition Report Proc No EI-1 Revision 57 Page 1 of 4 Date: _______ _

(INITIAL)

REF DONE?

EI-3 EI-2.2/Job Aid EI-3 EI-3 EI-3 N/A EI-3 FPIPs EI-3 EN-U-102

During Security related events performance of this action may be delayed until the safety of Personnel is assured.

LEGENDS: M=MANDATORY S=SUBSEQUENT I=IF NEEDED NOTES:

1.

2.

3.

4.

1 DCFR5D.72(c) REQUIRES ENTERGY "MAINTAIN AN OPEN, CONTINUOUS COMMUNICATION CHANNEL WITH THE NRC OPERATIONS UPON REQUEST OF THE NRC" 3D-MINUTE UPDATES REQUIRED WHEN ABOVE UE REFER TO THE PALISADES EMERGENCY CONTACT TELEPHONE BOOK FOR PHONE NUMBERS Direct Work Week Manager to provide follow-up information to ERO (via the ERO Notification System) regarding the status of the plant and circumstances that led to the Unusual Event declaration.

Completed forms shall be transmitted to Plant Licensing within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

EVENT TYPE:

ITEM ACTION 1*

M 2*

M 3*

M 4

M 5

M 8

M 9*

M 10 M

11*

M 12 I

13 S

14*

S 15 S

16 I

17*

S 18 I

19 I

20 I

21 S

22 S

23 S

EMERGENCY ACTIONS/NOTIFICATIONS ALERT DESCRIPTION OF ACTION Announce Emergency on PA Sound Emergency Siren Activate ERO Notification System for Staff Augmentation Notify Van Buren County (within 15 min of declaration) See Notes 2 and 3 below Notify State of Michigan (within 15 min of declaration) See Notes 2 and 3 below Notify NRC See Note 1 below Perform Personnel Accountability - Notify Security Ensure ERDS is activated.

Initiate Onsite Monitoring/Habitability Activate Safeguards Contingency Procedures Perform Offsite Dose Assessment Initiate Offsite Monitoring Notify Public Affairs See Note 3 below Activate Fire Protection Plan Consider the Release/Evacuation of Nonessential Personnel Notify Covert Fire Dept and Call Security Perform Core Damage Calculation Perform Environmental Assessment Initiate Re-entry/Recovery Initiate Condition Report Contact INPO via 24-hr line (In event of radiological emergency)

Proc No EI-1 Revision 57 Page 2 of4 Date: _______ _

REF (INITIAL)

DONE?

EI-3 EI-3 EI-2.2/Job Aid EI-3 EI-3 EI-3 EI-12.1 EP Job Aid GEN-032 EI-8 N/A EI-6.0 EI-9 EI-3 FPIPs EI-13 EI-3 EI-7.0/EI-11 EI-10 EI-5.0/EI-5.1 EN-Ll-102 SEP

During Security related events performance of this action may be delayed until the safety of Personnel is assured.

LEGENDS: M=MANDATORY S=SUBSEQUENT I=IF NEEDED NOTES:

1.

2.

3.

10CFR50.72(c) REQUIRES ENTERGY "MAINTAIN AN OPEN, CONTINUOUS COMMUNICATION CHANNEL WITH THE NRC OPERATIONS UPON REQUEST OF THE NRC" 30-MINUTE UPDATES REQUIRED WHEN ABOVE UE REFER TO THE PALISADES EMERGENCY CONTACT TELEPHONE BOOK FOR PHONE NUMBERS Completed forms shall be transmitted to Plant Licensing within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

EVENT TYPE:

ITEM ACTION 1*

M 2*

M 3*

M 4

M 5

M 8

M 9*

M 10 M

11*

M 12 I

13 S

14*

M 15 M

16 I

17*

S 18 I

19 I

20 I

21 S

22 S

23 S

24 I

25 I

EMERGENCY ACTIONS/NOTIFICATIONS SITE AREA EMERGENCY DESCRIPTION OF ACTION Announce Emergency on PA Sound Emergency Siren Activate ERO Notification System for Staff Augmentation Notify Van Buren County (within 15 min of declaration) See Notes 2 and 3 below Notify State of Michigan (within 15 min of declaration) See Notes 2 and 3 below Notify NRC See Note 1 below Perform Personnel Accountability - Notify Security Ensure EROS is activated.

Initiate Onsite Monitoring/Habitability Activate Safeguards Contingency Procedures Perform Offsite Dose Assessment Initiate Offsite Monitoring Notify Public Affairs See Note 3 below Activate Fire Protection Plan Evacuate Nonessential Personnel Notify Covert Fire Dept and Call Security Perform Core Damage Calculation Perform Environmental Assessment Initiate Re-entry/Recovery Initiate Condition Report Contact INPO via 24-hr line (In event of radiological emergency)

Implement SAMG Phase 1 - Initial Diagnosis Implement Emergency Management Guidelines Proc No EI-1 Revision 57 Page 3 of4 Date: ______ _

(INITIAL)

REF DONE?

EI-3 EI-3 EI-2.2/Job Aid EI-3 EI-3 EI-3 EI-12.1 EP Job Aid GEN-032 EI-8 N/A EI-6.0 EI-9 EI-3 FPIPs EI-13 EI-3 EI-7.0/EI-11 EI-10 EI-5.0/EI-5.1 EN-Ll-102 SEP SAMGs EMGs

During Security related events performance of this action may be delayed until the safety of Personnel is assured.

LEGENDS: M=MANDATORY S=SUBSEQUENT I=IF NEEDED NOTES:

1.

2.

3.

10CFR50.72(c) REQUIRES ENTERGY "MAINTAIN AN OPEN, CONTINUOUS COMMUNICATION CHANNEL WITH THE NRC OPERATIONS UPON REQUEST OF THE NRC" 30-MINUTE UPDATES REQUIRED WHEN ABOVE UE REFER TO THE PALISADES EMERGENCY CONTACT TELEPHONE BOOK FOR PHONE NUMBERS Completed forms shall be transmitted to Plant Licensing within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

EVENT TYPE:

ITEM ACTION 1*

M 2*

M 3*

M 4

M 5

M 6

M 8

M 9*

M 10 M

11*

M 12 I

13 M

14*

M 15 M

16 I

17*

S 18 I

19 S

20 S

21 S

22 S

23 S

24 S

25 I

EMERGENCY ACTIONS/NOTIFICATIONS GENERAL EMERGENCY DESCRIPTION OF ACTION Announce Emergency on PA Sound Emergency Siren Activate ERO Notification System for Staff Augmentation Notify Van Buren County (within 15 min of declaration) See Notes 2 and 3 below Notify State of Michigan (within 15 min of declaration) See Notes 2 and 3 below Provide Protective Action Recommendation Notify NRC See Note 1 below Perform Personnel Accountability - Notify Security Ensure EROS is activated.

Initiate Onsite Monitoring/Habitability Activate Safeguards Contingency Procedures Perform Offsite Dose Assessment Initiate Offsite Monitoring Notify Public Affairs See Note 3 below Activate Fire Protection Plan Evacuate Nonessential Personnel Notify Covert Fire Dept and Call Security Perform Core Damage Calculation Perform Environmental Assessment Initiate Re-entry/Recovery Initiate Condition Report Contact INPO via 24-hr line (In event of radiological emergency)

Implement SAMG Phase 1 - Initial Diagnosis Implement Emergency Management Guidelines Proc No EI-1 Revision 57 Page 40f4 Date: _______ _

(INITIAL)

REF DONE?

EI-3 EI-3 EI-2.2/Job Aid EI-3 EI-3 EI-6.13 EI-3 EI-12.1 EP Job Aid GEN-032 EI-8 N/A EI-6.0 EI-9 EI-3 FPIPs EI-13 EI-3 EI-7.0/EI-11 EI-10 EI-5.0/EI-5.1 EN-Ll-102 SEP SAMGs EMGs

Dunng Secunty related events performance of this action may be delayed until the safety of Personnel IS assured.

LEGENDS: M=MANDATORY S=SUBSEQUENT I=IF NEEDED NOTES:

1.

2.

3.

1 DCFR5D.72(c) REQUIRES ENTERGY "MAINTAIN AN OPEN, CONTINUOUS COMMUNICATION CHANNEL WITH THE NRC OPERATIONS UPON REQUEST OF THE NRC" 3D-MINUTE UPDATES REQUIRED WHEN ABOVE UE REFER TO THE PALISADES EMERGENCY CONTACT TELEPHONE BOOK FOR PHONE NUMBERS Completed forms shall be transmitted to Plant Licensing within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Procedure No EI-2.2 Revision 16 Effective Date 1/26/16 PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: EMERGENCY STAFF AUGMENTATION Approved: MEFields 1

1/21/16

-=----~--~------------------------------------------------~---

Procedure Sponsor Date I Process Applicability Exclusion New Procedure/Revision Summary:

Editorial, Rev 16 Specific Changes DRNs: 13-00954,15-00678,15-01453 Removed reference to Plant Operating Review Committee and On Site Safety Review Committee under Special Reviews.

Removed reference to EN-OM-119.

Changed title to Step 5.3.1.

Revision. Rev 15 DRN-10-00939 DRN-09-02187 Removed references to the Rapid Notify System.

Section 1.0 - Changed responsibility for activating the automated notification system from Security to the Shift Manager or designee. Added responsibility for Security to perform manual call staff augmentation. Added responsibility for site employees to maintain their contact information. Added responsibility for Emergency Planning to maintain and test the notification system.

Section 2.0 - Grammatical changes.

Section 4.0 - Grammatical changes.

Section 5.1 - Complete rewrite.

Section 5.2 - Complete rewrite.

Section 5.3 - Complete rewrite.

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: EMERGENCY STAFF AUGMENTATION Table of Contents Proc No EI-2.2 Revision 16 Page i 1.0 PERSONNEL RESPONSIBILITY.................................................................................. 1 2.0 PURPOSE...................................................................................................................... 1

3.0 REFERENCES

............................................................................................................... 1 3.1 SOURCE DOCUMENTS................................................................................ 1 3.2 REFERENCE DOCUMENTS......................................................................... 1 3.3 NRC COMMITMENT REFERENCE NUMBER.............................................. 2 4.0 INITIAL CONDITIONS ANDIOR REQUiREMENTS....................................................... 2 5.0 PROCEDURE................................................................................................................. 2 5.1 INITIATION.................................................................................................... 2 5.2 NOTIFICATION SYSTEM MAINTENANCE AND TESTING.......................... 3 5.3 EVALUATING QUARTERLY TEST RESULTS............................................. 3 6.0 ATTACHMENTS AND RECORDS................................................................................. 3 6.1 ATTACHMENTS............................................................................................ 3 6.2 RECORDS..................................................................................................... 3 7.0 SPECIAL REVIEWS...................................................................................................... 4

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: EMERGENCY STAFF AUGMENTATION INFORMATIONAL USE Proc No EI-2.2 Revision 16 Page 1 of 4 Procedure is available and referenced for review, but not necessarily at the work location.

Procedure may be performed from memory or referred to as needed.

User remains responsible for procedure adherence.

1.0 PERSONNEL RESPONSIBILITY 1.1 The Shift Manager (SM) or designee shall activate the automated Emergency Response Organization (ERO) notification system.

1.2 Plant Security personnel shall perform Manual Telephone Call staff augmentation should the automated ERO notification system fail.

1.3 Plant employees shall verify and maintain their contact information on a quarterly basis or when contact information changes are required.

1.4 Emergency Planning shall maintain and periodically test the automated ERO notification system.

2.0 PURPOSE To provide a method of timely ERO notification for the purpose of staff augmentation during emergency events.

3.0 REFERENCES

3.1 SOURCE DOCUMENTS 3.1.1 Palisades Site Emergency Plan 3.2 REFERENCE DOCUMENTS 3.2.1 Emergency Augmentation Instruction Binder 3.2.2 Entergy Procedure EN-AD-103, "Document Control and Records Management Programs" 3.2.3 Palisades Site Emergency Plan, Section 5, Figure 5-2 3.2.4 Entergy Procedure EN-EP-305, "Emergency Planning 10CFR50.54(q) Review Program"

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: EMERGENCY STAFF AUGMENTATION 3.3 NRC COMMITMENT REFERENCE NUMBER Proc No EI-2.2 Revision 16 Page 2 of4 3.3.1 CMT912000681, Response to NRC Inspection Report 90-34. (Step 5.2.1 of Section 5.2, "Notification System Maintenance and Testing") ensuring Emergency Response Organization (ERO) personnel are current in emergency training each month.

4.0 INITIAL CONDITIONS ANDIOR REQUIREMENTS Staff augmentation is mandatory at the Alert or higher emergency classification.

Staff augmentation may be performed before an Alert or higher emergency classification is declared at the discretion of the SM.

5.0 PROCEDURE INFORMATIONAL USE Procedure is available and referenced for review, but not necessarily at the work location.

Procedure may be performed from memory or referred to as needed.

User remains responsible for procedure adherence.

5.1 INITIATION 5.1.1 Initiate staff augmentation using the automated ERO notification system.

5.1.2 Instructions and Access Codes for activating the ERO notification system are maintained in an envelope in the Emergency Preparedness forms file drawer.

5.1.3 In the event the automated ERO notification system cannot be activated, notify the Security Shift Lieutenant or Captain to begin the manual ERO call-in process.

5.1.4 Manual call-in ERO phone lists are contained in the Emergency Augmentation Instruction Binder located at the Security Captain's desk, Security 10 Station, Central Alarm Station and Secondary Alarm Station and Emergency Operations Center (EOF).

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: EMERGENCY STAFF AUGMENTATION 5.2 NOTIFICATION SYSTEM MAINTENANCE AND TESTING Proc No EI-2.2 Revision 16 Page 3 of 4 5.2.1 Emergency Planning shall review the data base of the automated ERO notification system each month to ensure listed ERG personnel are qualified. {NRC CMT912000681 }

5.2.2 Plant employees should verify their contact information on a quarterly basis upon receiving a scheduled message sent by the ERO notification system.

5.2.3 Emergency Planning should verify manual call lists on a quarterly basis.

5.2.4 Emergency planning shall maintain ERG notification system Access Codes. An Access Code should be changed if it has been used for a drill or actual emergency.

5.2.5 Off-hours ERG notification system testing shall be conducted on a quarterly basis.

Conduct at least one test annually on a scheduled day off.

5.3 EVALUATING QUARTERLY TEST RESULTS 5.3.1 Evaluate quarterly test results relative to the requirements of the Site Emergency Plan, Section 5, Figure 5-2, "Plant Staffing and Augmentation Requirements."

Unsuccessful results shall be entered into the Corrective Action Program.

5.3.2 Evaluate responses using a combination of notification system reports, voice messages and security system reports.

5.3.3 Document the test result evaluation.

6.0 ATTACHMENTS AND RECORDS 6.1 ATTACHMENTS None 6.2 RECORDS Records generated by this procedure shall be filed in accordance with Entergy Procedure EN-AD-103, "Document Control and Records Management Programs."

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: EMERGENCY STAFF AUGMENTATION 7.0 SPECIAL REVIEWS Proc No EI-2.2 Revision 16 Page 4 of4 7.1 The scope of this procedure does not include activities that require a 50.59 review.

Therefore, changes to this procedure do not require a 50.59 review.

7.2 Revisions to this procedure require a 50.54(q) review per Entergy Procedure EN-EP-305, "Emergency Planning 10CFR50.54(q) Program."

Procedure No EI-S.O Revision 8 Effective Date 01/26/16 PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: REENTRY Approved: MEFields 1

01/21/16

-=~~~~~--------------------------~------------------~~~~-

Procedure Sponsor Date I Process Applicability Exclusion D

New Procedure/Revision Summarv:

Rev 8, Editorial Correction Specific Changes:

Revision 8 Removed reference to Plant Operating Review Committee and On Site Safety Review Committee under Special Reviews. (DRN-1 0-00031 )(DRN-13-00959)

Added references Revision 7 -Editorial-PCR01089066 - DRN-09-01906 Changes to implement Standard ERO position Titles and to eliminate reference to NMC Procedures.

PCR01068589 - Revision 6 - Editorial Added the following references to the Special Reviews section: Revisions of this procedure require a 50.54(q) review per NMC Fleet Procedure FP-R-EP-02, "10CFR50.54(q) Review Process." The Site Emergency Plan requires Emergency Implementing Procedure revisions to be reviewed by the Plant Operating Review Committee.

Changed the reference section from Admin 10.41 to NMC Fleet Procedure FP-G-DOC-04, "Procedure Processing."

Changed the Records Center from Admin 10.46 to NMC Fleet Procedure FP-G-RM-01, "Records Management."

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: REENTRY Table of Contents Proc No EI-S.O Revision 8 Page i 1.0 PERSONNEL RESPONSIBILITY.................................................................................. 1 2.0 PURPOSE...................................................................................................................... 1

3.0 REFERENCES

............................................................................................................... 1 3.1 SOURCE DOCUMENTS................................................................................ 1 3.2 REFERENCE DOCUMENTS......................................................................... 1 4.0 INITIAL CONDITIONS ANDIOR REQUiREMENTS....................................................... 2 5.0 PROCEDURE................................................................................................................. 3 6.0 ATTACHMENTS AND RECORDS................................................................................. 5 6.1 ATTACHMENTS............................................................................................ 5 6.2 RECORDS..................................................................................................... 5 6.3 SPECIAL REVIEWS...................................................................................... 5 ATTACHMENTS, "Record of Major Actions Performed"

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: REENTRY REFERENCE USE Procedure and Procedure Precautions and Limitations are at the work location for reference.

Proc No EI*5.0 Revision 8 Page 1 of 5 Review and understand segments before performing any steps.

Signoff steps are completed, when included, before starting the next step.

Place keep in accordance with EN-HU-106, "Procedure and Work Instruction Use and Adherence."

Review the Procedure to verify segments have been completed.

1.0 PERSONNEL RESPONSIBILITY 1.1 The Emergency Operations Facility (EOF) Emergency Director, in conjunction with the Shift Manager, the Emergency Plant Manager and the Site Vice President, is responsible for initiating the reentry phase of emergency response.

1.2 The Emergency Plant Manager is responsible for directing reentry.

2.0 PURPOSE To provide guidelines for reentry of the Plant following implementation of the Site Emergency Plan.

3.0 REFERENCES

3.1 SOURCE DOCUMENTS 3.1.1 NUREG 0654, Section M, "Recovery and Reentry Planning and Post-Accident Operations" 3.1.2 Palisades Site Emergency Plan, Section 9, "Recovery" 3.2 REFERENCE DOCUMENTS 3.2.1 Palisades Administrative Procedure 1.15, "Performance of Job Briefings" 3.2.2 Emergency Implementing Procedure EI-5.1, "Recovery" 3.2.3 Entergy Procedure EN-AD-103, "Document Control and Records Management Programs."

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: REENTRY Proc No EI-S.O Revision 8 Page 2 of S 3.2.4 Entergy Procedure EN-EP-305, "Emergency Planning 1 OCFR50.54(q) Review Program."

4.0 INITIAL CONDITIONS ANDIOR REQUIREMENTS 4.1 The following conditions should be considered before entering reentry:

a.

The reactor and associated systems are in a stable, safe condition.

b.

The release of radioactive materials to the environment is under control or has ceased.

c.

In-plant radiation levels are stable or decreasing.

d.

Fire, flood, etc, is under control or has ceased.

e.

At least one level of redundancy in plant systems should be available to prevent reinitiation of the event.

f.

Consensus has been reached among the SED, EOF Directors, NRC, and the state.

4.2 Damaged or failed equipment should be quarantined except when required to support safe shutdown of the plant.

4.3 A log of important actions and persons performing the actions should be maintained using Attachment 1 of this procedure.

4.4 Radiation exposure of personnel involved in reentry shall be As Low As Reasonably Achievable. Limits imposed may be dependent upon specific circumstances and risk versus benefit.

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: REENTRY 5.0 PROCEDURE REFERENCE USE Procedure and Procedure Precautions and Limitations are at the work location for reference.

Proc No EI-S.O Revision 8 Page 3 of S Review and understand segments before performing any steps.

Signoff steps are completed, when included, before starting the next step.

Place keep in accordance with EN-HU-106, "Procedure and Work Instruction Use and Adherence."

Review the Procedure to verify segments have been completed.

5.1 Prior to authorizing the dispatch of a reentry team, the Emergency Plant Manager, with input from Technical Support Center (TSC) Team Leaders, should determine the following:

a.

Areas of the plant potentially affected by radiation and/or contamination.

b.

Identify damaged equipment which needs to be quarantined for failure analysis.

c.

Adequacy of radiation survey instrumentation and equipment.

d.

Radiation exposures of personnel expected to participate in reentry operations.

5.2 Reentry into the plant should encompass the following goals, in order of priority:

a.

Identification of hazards or potential hazards.

b.

Determination of damage to equipment.

c.

Conduct comprehensive radiation surveys and identify areas needing shielding.

d.

Isolate and post areas with warning signs and barriers (ie, safety hazards, Radiation Areas, Contamination Areas).

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: REENTRY Proc No EI-5.0 Revision 8 Page 4 of5 5.3 Each reentry team should include a designated team leader and a Radiation Safety representative. Personnel from Operations, Maintenance, and Engineering may be included as needed.

5.4 Pre-job briefings should follow the guidance of Palisades Administrative Procedure 1.15, "Performance of Job Briefings."

5.4.1 Pre-job briefings for reentry teams should also include the following:

a.

Area to be surveyed

b.

Anticipated radiation and contamination levels

c.

Radiation survey equipment required

d.

Availability of shielding

e.

Protective clothing and equipment required

f.

Radiation Work Permit

g.

Exposure limits and dosimetry requirements h

Decontamination requirements

i.

Communication equipment required 5.5 Following completion of their tasks, a reentry team shall be debriefed to assess data gathered and to document work completed. Copies of documentation shall be provided to the Recovery Manager to be utilized in recovery planning per Emergency Implementing Procedure EI-5.1, "Recovery."

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: REENTRY 6.0 ATTACHMENTS AND RECORDS 6.1 ATTACHMENTS, "Record of Major Actions Performed" 6.2 RECORDS Proc No EI-5.0 Revision 8 Page 5 of 5 Records generated by this procedure shall be filed in accordance with Entergy Procedure EN-AD-103, "Document Control and Records Management Programs."

6.3 SPECIAL REVIEWS 6.3.1 The scope of this procedure does not include activities that require a 50.59 review.

Therefore, changes to this procedure do not require a 50.59 review.

6.3.2 Revisions of this procedure require a 50.54(q) review per Entergy Procedure EN-EP-305, "Emergency Planning 10CFR50.54(q) Review Program."

RECORD OF MAJOR ACTIONS PERFORMED Proc No EI-5.0 Revision 8 Page 1 of 1 Page of DatelTime of Emergency:

/

Date/Time Reentry Action Accomplished By Reviewed By

Procedure No EI-S.O Revision 8 Effective Date 01/26/16 PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: REENTRY Approved: ME Fields 1

01/21/16

~~~~~~------------------------~------------------~~~~

Procedure Sponsor Date I Process Applicability Exclusion D

New Procedure/Revision Summary:

Rev 8, Editorial Correction Specific Changes:

Revision 8 Removed reference to Plant Operating Review Committee and On Site Safety Review Committee under Special Reviews. (ORN-1 0-00031 )(ORN-13-00959)

Added references Revision 7 -Editorial - PCR01 089066 - ORN-09-01906 Changes to implement Standard ERO position Titles and to eliminate reference to NMC Procedures.

PCR01068589 - Revision 6 - Editorial Added the following references to the Special Reviews section: Revisions of this procedure require a 50.54(q) review per NMC Fleet Procedure FP-R-EP-02, "10CFR50.54(q) Review Process." The Site Emergency Plan requires Emergency Implementing Procedure revisions to be reviewed by the Plant Operating Review Committee.

Changed the reference section from Admin 10.41 to NMC Fleet Procedure FP-G-OOC-04, "Procedure Processing."

Changed the Records Center from Admin 10.46 to NMC Fleet Procedure FP-G-RM-01, "Records Management."

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: REENTRY Table of Contents Proc No EI-S.O Revision 8 Pagei 1.0 PERSONNEL RESPONSIBILITY.................................................................................. 1 2.0 PURPOSE...................................................................................................................... 1

3.0 REFERENCES

............................................................................................................... 1 3.1 SOURCE DOCUMENTS................................................................................ 1 3.2 REFERENCE DOCUMENTS......................................................................... 1 4.0 INITIAL CONDITIONS ANDIOR REQUiREMENTS....................................................... 2 5.0 PROCEDURE................................................................................................................. 3 6.0 ATTACHMENTS AND RECORDS................................................................................. 5 6.1 ATTACHMENTS............................................................................................ 5 6.2 RECORDS..................................................................................................... 5 6.3 SPECIAL REVIEWS...................................................................................... 5 ATTACHMENTS, "Record of Major Actions Performed"

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: REENTRY REFERENCE USE Procedure and Procedure Precautions and Limitations are at the work location for reference.

Proc No EI-5.0 Revision 8 Page 1 of 5 Review and understand segments before performing any steps.

Signoff steps are completed, when included, before starting the next step.

Place keep in accordance with EN-HU-106, "Procedure and Work Instruction Use and Adherence."

Review the Procedure to verify segments have been completed.

1.0 PERSONNEL RESPONSIBILITY 1.1 The Emergency Operations Facility (EOF) Emergency Director, in conjunction with the Shift Manager, the Emergency Plant Manager and the Site Vice President, is responsible for initiating the reentry phase of emergency response.

1.2 The Emergency Plant Manager is responsible for directing reentry.

2.0 PURPOSE To provide guidelines for reentry of the Plant following implementation of the Site Emergency Plan.

3.0 REFERENCES

3.1 SOURCE DOCUMENTS 3.1.1 NUREG 0654, Section M, "Recovery and Reentry Planning and Post-Accident Operations" 3.1.2 Palisades Site Emergency Plan, Section 9, "Recovery" 3.2 REFERENCE DOCUMENTS 3.2.1 Palisades Administrative Procedure 1.15, "Performance of Job Briefings" 3.2.2 Emergency Implementing Procedure EI-5.1, "Recovery" 3.2.3 Entergy Procedure EN-AD-103, "Document Control and Records Management Programs."

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: REENTRY Proc No EI-S.O Revision 8 Page 2 of S 3.2.4 Entergy Procedure EN-EP-305, "Emergency Planning 10CFR50.54(q) Review Program."

4.0 INITIAL CONDITIONS ANDIOR REQUIREMENTS 4.1 The following conditions should be considered before entering reentry:

a.

The reactor and associated systems are in a stable, safe condition.

b.

The release of radioactive materials to the environment is under control or has ceased.

c.

In-plant radiation levels are stable or decreasing.

d.

Fire, flood, etc, is under control or has ceased.

e.

At least one level of redundancy in plant systems should be available to prevent reinitiation of the event.

f.

Consensus has been reached among the SED, EOF Directors, NRC, and the state.

4.2 Damaged or failed equipment should be quarantined except when required to support safe shutdown of the plant.

4.3 A log of important actions and persons performing the actions should be maintained using Attachment 1 of this procedure.

4.4 Radiation exposure of personnel involved in reentry shall be As Low As Reasonably Achievable. Limits imposed may be dependent upon specific circumstances and risk versus benefit.

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: REENTRY 5.0 PROCEDURE REFERENCE USE Procedure and Procedure Precautions and Limitations are at the work location for reference.

Proc No EI-S.O Revision 8 Page 3 of S Review and understand segments before performing any steps.

Signoft steps are completed, when included, before starting the next step.

Place keep in accordance with EN-HU-106, "Procedure and Work Instruction Use and Adherence."

Review the Procedure to verify segments have been completed.

5.1 Prior to authorizing the dispatch of a reentry team, the Emergency Plant Manager, with input from Technical Support Center (TSC) Team Leaders, should determine the following:

a.

Areas of the plant potentially affected by radiation and/or contamination.

b.

Identify damaged equipment which needs to be quarantined for failure analysis.

c.

Adequacy of radiation survey instrumentation and equipment.

d.

Radiation exposures of personnel expected to participate in reentry operations.

5.2 Reentry into the plant should encompass the following goals, in order of priority:

a.

Identification of hazards or potential hazards.

b.

Determination of damage to equipment.

c.

Conduct comprehensive radiation surveys and identify areas needing shielding.

d.

Isolate and post areas with warning signs and barriers (ie, safety hazards, Radiation Areas, Contamination Areas).

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: REENTRY Proc No EI-5.0 Revision 8 Page 4 of5 5.3 Each reentry team should include a designated team leader and a Radiation Safety representative. Personnel from Operations, Maintenance, and Engineering may be included as needed.

5.4 Pre-job briefings should follow the guidance of Palisades Administrative Procedure 1.15, "Performance of Job Briefings."

5.4.1 Pre-job briefings for reentry teams should also include the following:

a.

Area to be surveyed

b.

Anticipated radiation and contamination levels

c.

Radiation survey equipment required

d.

Availability of shielding

e.

Protective clothing and equipment required

f.

Radiation Work Permit

g.

Exposure limits and dosimetry requirements h

Decontamination requirements

i.

Communication equipment required 5.5 Following completion of their tasks, a reentry team shall be debriefed to assess data gathered and to document work completed. Copies of documentation shall be provided to the Recovery Manager to be utilized in recovery planning per Emergency Implementing Procedure EI-5.1, "Recovery."

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: REENTRY 6.0 ATTACHMENTS AND RECORDS 6.1 ATTACHMENTS, "Record of Major Actions Performed" 6.2 RECORDS Proc No EI-5.0 Revision 8 Page 5 of 5 Records generated by this procedure shall be filed in accordance with Entergy Procedure EN-AD-103, "Document Control and Records Management Programs."

6.3 SPECIAL REVIEWS 6.3.1 The scope of this procedure does not include activities that require a 50.59 review.

Therefore, changes to this procedure do not require a 50.59 review.

6.3.2 Revisions of this procedure require a 50.54(q) review per Entergy Procedure EN-EP-305, "Emergency Planning 10CFR50.54(q) Review Program."

RECORD OF MAJOR ACTIONS PERFORMED Proc No EI-5.0 Revision 8 Page 1 of 1 Page of DatelTime of Emergency:

I DatelTime Reentry Action Accomplished By Reviewed By

Procedure No EI-6.4 Revision 5 Effective Date 01/28/16 PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: RELEASE/POTENTIAL RELEASE DETERMINATION FROM CONTAINMENT HIGH-RANGE MONITORS Approved: DGMalone Procedure Sponsor I Process Applicability Exclusion New Procedure/Revision Summary:

Rev 5, Editorial Correction Specific Changes:

1 D

01/21/16 Date

- 3.2.1 and 4.0a Corrected title of reference EI-6.0, "Offsite Dose Calculation and Recommendation for Protective Actions" to "Rapid Dose Calculation"

- 3.2.4 Removed reference to EN-OM-119, "On-Site Safety Review Committee" under the Special Reviews section.

- 7.0 Removed reference to Plant Operating Review Committee and On Site Safety Review Committee under Special Reviews (DRN-13-00966, DRN 01424)

Revision 4 - Editorial Incorporated PCR-01051552.

Minor editorial changes to Emergency Personnel titles to align with Emergency Planning Standard Organization.

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE Proc No EI-6.4 Revision 5 Page i TITLE: RELEASE/POTENTIAL RELEASE DETERMINATION FROM CONTAINMENT HIGH-RANGE MONITORS Table of Contents 1.0 PERSONNEL RESPONSIBILITY.................................................................................. 1 2.0 PURPOSE...................................................................................................................... 1

3.0 REFERENCES

............................................................................................................... 1 3.1 SOURCE DOCUMENTS..................................................................................... 1 3.2 REFERENCE DOCUMENTS............................................................................... 1 4.0 INITIAL CONDITIONS AND/OR REQUiREMENTS....................................................... 2 5.0 PROCEDURE................................................................................................................. 2 5.1 RELEASE RATE................................................................................................. 2 5.2 HIGH-RANGE MONITOR READING.................................................................. 2 6.0 ATTACHMENTS AND RECORDS................................................................................. 3 6.1 ATTACHMENTS................................................................................................. 3 6.2 RECORDS........................................................................................................... 3 7.0 SPECIAL REVIEWS...................................................................................................... 3 ATTACHMENTS, "Containment High-Range Monitor Conversion Factor", "Containment High-Range Monitor Release Rate Worksheet"

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE Proc No EI-6.4 Revision 5 Page 1 of 3 TITLE: RELEASE/POTENTIAL RELEASE DETERMINATION FROM CONTAINMENT HIGH-RANGE MONITORS INFORMATIONAL USE Procedure is available and referenced for review, but not necessarily at the work location.

Procedure may be performed from memory or referred to as needed.

User remains responsible for procedure adherence.

1.0 PERSONNEL RESPONSIBILITY The Radiological Assessment Coordinator shall implement this procedure. In the absence of a Radiological Assessment Coordinator, the Emergency Plant Manager, or Emergency Director shall delegate this responsibility.

2.0 PURPOSE This procedure provides a method to determine release rate/potential release rate from radioactive material released from containment. This data is used as input to offsite dose calculations.

This procedure provides a manual backup method to the containment high-range monitor release rate calculations performed in the Automated Dose Assessment Program, "Offsite."

3.0 REFERENCES

3.1 SOURCE DOCUMENTS 3.1.1 Site Emergency Plan Section 4, "Emergency Conditions" 3.1.2 NUREG 0654 Section I, "Accident Assessment" 3.1.3 Dose Assessment Basis Document DABD-05, "Palisades - Containment High Range Release Rate Calculation" 3.2 REFERENCE DOCUMENTS 3.2.1 Emergency Implementing Procedure EI-6.0, "Rapid Dose Calculation" 3.2.2 Entergy Procedure EN-AD-103, "Document Control and Records Management Programs" 3.2.3 Entergy Procedure EN-EP-305, "Emergency Planning 10CFR50.54(q) Program"

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE Proc No EI-6.4 Revision 5 Page 2 of 3 TITLE: RELEASE/POTENTIAL RELEASE DETERMINATION FROM CONTAINMENT HIGH-RANGE MONITORS 4.0 INITIAL CONDITIONS AND/OR REQUIREMENTS

a.

This procedure shall be implemented as required per Emergency Implementing Procedure EI-6.0, "Rapid Dose Calculation."

b.

This procedure assumes a release from the primary coolant system into the containment atmosphere.

c.

If there is a breach in containment, the leak rate should be determined by the best method available.

5.0 PROCEDURE INFORMATIONAL USE Procedure is available and referenced for review, but not necessarily at the work location.

Procedure may be performed from memory or referred to as needed.

User remains responsible for procedure adherence.

5.1 RELEASE RATE 5.2 HIGH-RANGE MONITOR READING

a.

Determine if there has been or is a release from the primary coolant system to the containment atmosphere.

NOTE:

Time of shutdown can be obtained from the TSC Operations Support Group.

b.

Determine the time since reactor shutdown (hours) and record on worksheet,, Step 1.

c.

Mark the monitor from which the reading is taken on Attachment 2, Step 2 - RIA-2321 or RIA-2322.

d.

Record the monitor reading on Attachment 2, Step 3 in rem/hr. The readout for both monitors is on Control Room Panel C-11A and the Palisades Plant Computer (PPC) page 352.

e.

Obtain from Attachment 1 the f.1Ci/cc conversion factor for the specified time rem/h since reactor shutdown for noble gas. Record on Attachment 2, Step 4.

NOTE:

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE Proc No EI-6.4 Revision 5 Page 3 of 3 TITLE: RELEASE/POTENTIAL RELEASE DETERMINATION FROM CONTAINMENT HIGH-RANGE MONITORS

f.

Determine the containment leak rate in cc/s. If no breach of containment has occurred, then the design leak rate should be used (0.1 %/day = 537.0 cc/s).

If there is a breach in containment, then the leak rate must be determined by the best available method. Record on Attachment 2, Step 5.

g.

Calculate noble gas release rate (ON) as follows:

h.

ON = [

rem/h ]

x conversion Monitor

[ Noble gas reading factor (leak rate cc/s) x (1.0 E-6 CilIlCi)

Record on Attachment 2, Step 6.

IlCi/cc

]

x rem/h As soon as the concentration of iodine has been quantified from either a RGEM, Primary Coolant, or offsite air sample, the corrected ratio of iodine to noble gas should be incorporated into the offsite dose calculation.

Calculate the dose equivalent 1-131 release rate (QI) as follows:

QN x 1.0 E-3 Record on Attachment 2, Step 7.

6.0 ATTACHMENTS AND RECORDS 6.1 ATTACHMENTS 6.1.1, "Containment High-Range Monitor Conversion Factor" 6.1.2, "Containment High-Range Monitor Release Rate Worksheet" 6.2 RECORDS Records generated by this procedure shall be filed in accordance with Entergy Procedure EN-AD-103, "Document Control and Records Management Programs."

7.0 SPECIAL REVIEWS The scope of this procedure does not include activities that require a 50.59 review.

Therefore, changes to this procedure do not require a 50.59 review.

Revisions of this procedure require a 50.54(q) review per Entergy Procedure EN-EP-305, "Emergency Planning 10CFR50.54(q) Program."

1.0

.5

.3

.2

e UI~

C$ !.1

,,~

.04

.03

.02

.01

.1

~

V CONTAINMENT HIGH-RANGE MONITOR CONVERSION FACTOR (RIA-2321 AND RIA-2322) k-::::-:

,/

/ V

/

//

/

V

/

I V

",V' V V 1

i Proc No EI-6.4 Revision 5 Page 1 of 1 I

J I

I I l"-

I

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I

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I I

i I

I I

.2

.3.4.5 2

3 4

5 10 20 30 40 50 100 200 300 400 500 1000 Time Since Reactor Shutdown (Hours)

Proc No EI-6.4 Revision 5 Page 1 of 1 CONTAINMENT HIGH-RANGE MONITOR RELEASE RATE WORKSHEET

1.

Time since reactor shutdown = ___ hours

2.

Monitor number ( ) RIA-2321

3.

4.

5.

6.

7.

( ) RIA-2322 Monitor reading = _____ remlh Noble gas conversion factor = ___ _

Leak rate =

ccls ON, noble gas release rate =

(#3) x (#4) x (#5) x (1.0 E-6) 01, 1-131 dose equivalent release rate =

(#6) x (1.0 E-3) 11 Ci/cc remlh

= ____ Ci/s

= ____ Ci/s Date: ____ Time: _____ Completed By: ___________ _

Procedure No EI-6.6 Revision 5 Effective Date 01/28/16 PAUSADESNUCLEARPLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: GAMMA E DETERMINATION Approved: DGMalone 1

Procedure Sponsor I Process Applicability Exclusion D

New Procedure/Revision Summary:

Rev 5, Editorial Correction Specific Changes:

- 3.2.1 and 4.0a Updated procedure EI-6.0 from "Rapid Dose Calculation Offsite Dose Calculation and Recommendations for Protective Actions" to "Rapid Dose Calculation"

- 3.2.5 removed reference to EM-OM-119, "On-Site Safety Review Committee"

- 3.2.6 removed reference to Admin 10.41, "Site Procedures and Processes" 01/21/16 Date

- 7.0 Removed references to the "Plant Operating Review Committee" and "On-Site Safety Review Committee" under the Special reviews section (DRN-13-00967, DRN-15-01423, DRN-15-01430)

Revision 4 - Editorial DRN-09-02066 Incorporated PCR-01051553.

Minor editorial changes to Emergency Personnel titles to align with Emergency Planning Standard Organization.

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: GAMMA E DETERMINATION Table of Contents Proc No EI-6.6 Revision 5 Page i 1.0 PERSONNEL RESPONSIBILITY.................................................................................. 1 2.0 PURPOSE...................................................................................................................... 1

3.0 REFERENCES

............................................................................................................... 1 3.1 SOURCE DOCUMENTS................................................................................ 1 3.2 REFERENCE DOCUMENTS......................................................................... 1 4.0 INITIAL CONDITIONS ANDIOR REQUiREMENTS....................................................... 2 5.0 PROCEDURE................................................................................................................. 2 5.1 E DETERMINATION...................................................................................... 2 6.0 ATTACHMENTS AND RECORDS................................................................................. 4 6.1 ATTACHMENTS............................................................................................ 4 6.2 RECORDS..................................................................................................... 4 7.0 SPECIAL REVIEWS...................................................................................................... 4 ATTACHMENTS, "Energy per Disintegration Versus Decay Time Prior to Release for Noble Gas", "Gamma E Determination Worksheet"

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: GAMMA E DETERMINATION INFORMATIONAL USE Proc No EI-6.6 Revision 5 Page 1 of 4 Procedure is available and referenced for review, but not necessarily at the work location.

Procedure may be performed from memory or referred to as needed.

User remains responsible for procedure adherence.

1.0 PERSONNEL RESPONSIBILITY The Radiological Assessment Coordinator shall implement this procedure. In the absence of a Radiological Assessment Coordinator, the Emergency Plant Manager or Emergency Director shall delegate this responsibility.

2.0 PURPOSE This procedure provides a gamma E: (average gamma energy per disintegration) for input into offsite dose calculations.

This procedure provides a manual backup to the gamma E: calculation performed in the automated dose assessment program, "Offsite."

3.0 REFERENCES

3.1 SOURCE DOCUMENTS 3.1.1 NUREG 0654,Section I, "Accident Assessment" 3.1.2 Dose Assessment Basis Document-06, "Palisades Gamma E Calculations" 3.2 REFERENCE DOCUMENTS 3.2.1 Emergency Implementing Procedure EI-6.0, "Rapid Dose Calculation" 3.2.2 Emergency Implementing Procedure EI-11, "Determination of Extent of Core Damage" 3.2.3 Entergy Procedure EN-AD-103, "Document Control and Records Management Programs" 3.2.4 Entergy Procedure EN-EP-305, "Emergency Planning 10CFR50.54(q) Program" 3.2.5 Palisades Administrative Procedure 10.41, "Site Procedure and Policy Processes"

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: GAMMA E DETERMINATION 4.0 INITIAL CONDITIONS ANDIOR REQUIREMENTS Proc No EI-6.6 Revision 5 Page 2 of4

a.

This procedure shall be implemented as required per Emergency Implementing Procedure EI-6.0, "Rapid Dose Calculation."

b.

Data and results from this procedure should be recorded on the Gamma E Determination Worksheet, Attachment 2.

c.

E is dependent on the source of the radionuclide release, the type of accident/release and the time of decay (or time after reactor shutdown).

Those parameters should be known prior to performing this procedure. In the event these parameters cannot be determined, the default value for E of 0.7 MeV should be used.

5.0 PROCEDURE 5.1 E DETERMINATION INFORMATIONAL USE Procedure is available and referenced for review, but not necessarily at the work location.

Procedure may be performed from memory or referred to as needed.

User remains responsible for procedure adherence.

NOTE:

Time of shutdown can be obtained from the TSC Operations Support Group.

a.

Determine the decay time in hours and record on worksheet, Attachment 2.

b.

Determine the source of the release and record on worksheet.

NOTE:

c.

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: GAMMA E DETERMINATION Proc No EI-S.S Revision 5 Page 3 of 4 Fuel failure may be determined using Emergency Implementing Procedure EI-11, "Determination of Extent of Core Dama e."

Determine E from the appropriate section below:

1.

Release With Fuel Melt or Fuel Failure - Using the time after reactor shutdown as the "Decay Time Prior to Release," determine E using. This method is used for all release sources when fuel melt or failure is involved.

2.

Mainsteam and Offgas (Air Ejector) Releases (No Fuel Melt or Failure)

- If the release originates from the Primary Coolant System with a Primary to Secondary leak, and there is no fuel melt or failure, then use the E that corresponds with the 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months value (0.134 MeV) from.

3.

Surge Tank, Volume Control Tank, and Degasifier Releases (No Fuel Melt or Failure) - Use E that corresponds to the six-hour time in (0.180 MeV). This corresponds to a release from the Primary Coolant System (excluding mainsteam releases) without fuel damage. This value may be used for any release that involves fresh primary coolant.

4.

Waste Gas Decay Tank Releases (No Fuel Melt or Failure) - If the decay time for activity in a Waste Gas Decay Tank is known, then E should be determined using Attachment 1 and six hours as the starting point for the decay time determination. (If decay time is not known, then use 0.180 MeV as a default.)

For example, if the tank contains activity that has decayed for two days, then the "Decay Time Prior to Release" is 48 + 6 = 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months .

5.

Fuel Handling, Sipping, and Cask Drop Releases - If the release is coming from a fresh spent fuel bundle (directly out of the reactor core and less than 30 days old), then use the time after reactor shutdown as the "Decay Time Prior to Release," and determine E using. If the release is coming from an old fuel bundle, then use an E of 0.035 MeV.

d.

Record E on the worksheet.

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: GAMMA E DETERMINATION 6.0 ATTACHMENTS AND RECORDS 6.1 ATTACHMENTS Proc No EI-S.S Revision 5 Page 4 of4 6.1.1, "Energy per Disintegration Versus Decay Time Prior to Release for Noble Gas" 6.1.2, "Gamma E: Determination Worksheet" 6.2 RECORDS Records generated by this procedure shall be filed in accordance with Entergy Procedure EN-AD-103, "Document Control and Records Management Programs."

7.0 SPECIAL REVIEWS The scope of this procedure does not include activities that require a 50.59 review.

Therefore, changes to this procedure do not require a 50.59 review.

Revisions of this procedure require a 50.54(q) review per Entergy Procedure EN-EP-305, "Emergency Planning 10CFR50.54(q) Program."

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.5.1 C

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.1 ENERGY PER CISINTEGRA TION Proc No EI-6.6 Revision 5 Page 1 of 1 VERSUS CECA Y TIME PRIOR TO RELEASE FOR NOBLE GAS

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5 10 20 30 40 50 100 200 300 400 500 1000 Decay Time Prior to Release (Hours)

(After 720 hrs use 0.035 MeV)

GAMMA E DETERMINATION WORKSHEET

1.

Decay time _____ hours Proc No EI-6.6 Revision 5 Page 1 of 1

2.

Source of release () Fuel Melt or Fuel Failure

3.

() Main Steam or Offgas (Air Ejector) Releases

() Surge Tank, Volume Control Tank, and Degasifier Releases

() Waste Gas Decay Tank Releases

() Fuel Handling, Sipping, and Cask Drop Releases E= ___ MeV Date: ____ Time: ____ Completed By: ___________ _

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE Procedure No EI-6.9 Revision 8 Effective Date 1/26/16 TITLE: AUTOMATED DOSE ASSESSMENT PROGRAM Approved: DGMalone Procedure Sponsor I Process Applicability Exclusion New Procedure/Revision Summary:

Rev 8, Editorial Correction Specific Changes:

Revision 8 DRN-15-01422; Reworded Step 3.2.2 Revision 7 1

01/21/16 Date DRN-14-01309; Procedure sections revised to implement the Unified RASCAL Interface (URI) dose assessment program.

DRN-13-00970; Removed OSRC review from Section 8.0 "Special Reviews."

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: AUTOMATED DOSE ASSESSMENT PROGRAM Table of Contents Proc No EI-6.9 Revision 8 Page i 1.0 PERSONNEL RESPONSIBILITY.................................................................................. 1 2.0 PURPOSE...................................................................................................................... 1

3.0 REFERENCES

............................................................................................................... 1 3.1 SOURCE DOCUMENTS................................................................................ 1 3.2 REFERENCE DOCUMENTS......................................................................... 2 4.0 DEFINITIONS................................................................................................................. 2 4.1 CDE.............................................................................................................. 2 4.2 CEDE............................................................................................................. 2 4.3 DOE............................................................................................................... 2 4.4 TEDE.............................................................................................................. 3 4.5 RELEASE OF RADIOACTIVE MATERIAL................................................... 3 4.6 UNIFIED RASCAL INTERFACE (URI).......................................................... 3 4.7 PROJECTED DOSE...................................................................................... 3 4.8 COOLANT SPIKING...................................................................................... 3 5.0 INITIAL CONDITIONS ANDIOR REQUiREMENTS....................................................... 3 6.0 PROCEDURE................................................................................................................. 4 6.1 "DETAILED" DOSE ASSESSMENT............................................................. 4 6.2 QUICK GUIDE FOR MONITORED RELEASE ASSESSMENT..................... 4 6.3 QUICK GUIDE FOR CONTAINMENT LEAKAGE ASSESSMENT................ 6 6.4 QUICK GUIDE FOR REACTOR COOLANT SYSTEM (RCS) LEAKAGE ASSESSMENT.................................................................................... 7 6.5 QUICK GUIDE FOR FIELD TEAM ASSESSMENT....................................... 9 6.6 QUICK GUIDE FOR SUMMATION ASSESSMENT.................................... 10 7.0 ATTACHMENTS AND RECORDS............................................................................... 11 8.0 SPECIAL REVIEWS.................................................................................................... 11

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: AUTOMATED DOSE ASSESSMENT PROGRAM REFERENCE USE Procedure and Procedure Precautions and Limitations are at the work location for reference.

Proc No EI-6.9 Revision 8 Page 1 of 11 Review and understand segments before performing any steps.

Signoff steps are completed, when included, before starting the next step.

Place keep in accordance with EN-HU-106, "Procedure and Work Instruction Use and Adherence."

Review the Procedure to verify segments have been completed.

1.0 PERSONNEL RESPONSIBILITY The Radiological Assessment Coordinator shall implement this procedure. In the absence of a Radiological Assessment Coordinator, the Emergency Plant Manager, or Emergency Director shall delegate this function.

2.0 PURPOSE This procedure provides basic instruction for performing offsite dose assessment using the Unified RASCAL Interface (URI) "Detailed" dose assessment method during an emergency event involving an actual or potential release of radioactivity to the environment. Additional details for using the URI dose assessment program are contained in Entergy Procedure EN-EP-313, "Offsite Dose Assessment using the Unified RASCAL Interface."

3.0 REFERENCES

3.1 SOURCE DOCUMENTS 3.1.1 NUREG 0654, Section J, "Protective Response" 3.1.2 Palisades Site Emergency Plan Section 6, "Emergency Measures" 3.1.3 Emergency Implementing Procedure EI-6.1, "Release Rate Determination from Stack Gas Monitors" 3.1.4 Emergency Implementing Procedure EI-6.2, "Release Rate Determination from Steam Line Monitors RIA-2323 and RIA-2324 for Steam Releases Through Atmospheric Dump Valves" 3.1.5 Emergency Implementing Procedure EI-6.3, "Release Rate Determination from High Range Effluent Monitors"

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: AUTOMATED DOSE ASSESSMENT PROGRAM Proc No EI-6.9 Revision 8 Page 2 of 11 3.1.6 Emergency Implementing Procedure EI-6.4, "Release/Potential Release Determination from Containment High-Range Monitors" 3.1.7 Emergency Implementing Procedure EI-6.6, "Gamma E Determination" 3.1.8 Emergency Implementing Procedure EI-6.8, "Backup and Supplemental Meteorology" 3.1.9 Emergency Implementing Procedure EI-6.1 0, "Offsite Dose Calculation - Straight Line Gaussian (Manual Method)"

3.2 REFERENCE DOCUMENTS 3.2.1 Emergency Implementing Procedure EI-1, "Emergency Classification and Actions" 3.2.2 Entergy Procedure EN-EP-305, "Emergency Planning 10CFR50.54(q) Review Program" 3.2.3 Entergy Procedure EN-EP-313, "Offsite Dose Assessment using the Unified RASCAL Interface" 3.2.4 Entergy Procedure EN-HU-106, "Procedure and Work Instruction Use and Adherence" 4.0 DEFINITIONS 4.1 CDE...........

Committed Dose Equivalent: 50-year integrated dose to organs or tissues due to an intake at time zero.

4.2 CEDE..

Committed Effective Dose Equivalent: The dose committed to an individual over the next 50 years due to intake of radioactive material, weighted (by organ) to represent a risk equivalent to that of whole body external exposure.

4.3 DDE.....

Deep Dose Equivalent: Dose equivalent due to external radiation at 1 cm tissue depth.

4.4 TEDE..

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: AUTOMATED DOSE ASSESSMENT PROGRAM Proc No EI-S.9 Revision 8 Page 3 of 11 Total Effective Dose Equivalent: Sum of deep dose equivalent due to external radiation exposure and committed effective dose equivalent due to internal exposure. When no other designator is applied to dose in units of rem, TEDE is implied.

4.5 RELEASE OF RADIOACTIVE MATERIAL Any discharge of radioactive material to the environment that is the result of, or associated with, the emergency event.

4.6 UNIFIED RASCAL INTERFACE (URI)

Computer software based on the NRC issued RASCAL dose assessment program with a modified user interface for input of dose assessment parameters.

4.7 PROJECTED DOSE In regards to dose assessment, projected dose is the dose that would be received by members of the public if protective actions were not implemented.

4.8 COOLANT SPIKING Term used by the URI dose assessment program to signify a fast or hard reactor shutdown condition ( 2:. 15% per hour since the start of the event) which may cause an increase in reactor coolant concentration of certain radionuclides.

5.0 INITIAL CONDITIONS ANDIOR REQUIREMENTS This procedure shall be implemented when there is a potential for, or an actual significant release of radioactive materials from the Plant site, per Emergency Implementing Procedure EI-1, "Emergency Classification and Actions."

Two methods are available to perform dose assessment functions. The preferred method is the use of the Unified RASCAL Interface (URI) automated dose assessment program. The alternate method is the manual dose assessment procedures which are used as backup to the preferred method.

All EI-6 Emergency Implementing Procedures pertain to dose assessment functions and making protective action recommendations. Not all procedures are applicable for all dose calculations.

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: AUTOMATED DOSE ASSESSMENT PROGRAM Proc No EI-6.9 Revision 8 Page 4 of 11 6.0 PROCEDURE 6.1 6.1.1 6.1.2 6.1.3 6.1.4 6.2 6.2.1 6.2.2 REFERENCE USE Procedure and Procedure Precautions and Limitations are at the work location for reference.

Review and understand segments before performing any steps.

Signoff steps are completed, when included, before starting the next step.

Place keep in accordance with EN-HU-106, "Procedure and Work Instruction Use and Adherence."

Review the Procedure to verify segments have been completed.

"DETAILED" DOSE ASSESSMENT The "Detailed" Dose Assessment interface is intended for use by qualified Dose Assessors during an emergency event that requires the calculation of offsite doses due to an actual or potential release of radioactivity near or beyond the site boundary.

The URI program contains many features and functions that are not applicable for dose assessment purposes at Palisades. This procedure provides the features and functions of URI applicable to Palisades to achieve timely dose assessment calculations.

URI can only calculate dose for a single release pathway at one time. IF releases are occurring via multiple pathways, THEN individual dose assessments will need to be performed for each release pathway then added together using the summation process within URI. Refer to Section 6.6, "Quick Guide for Summation Assessment. "

URI contains many reports and operations that can be useful when running or evaluating dose assessment data that are not detailed in this procedure. Additional details for using the URI dose assessment reports and operations are contained in Entergy Procedure EN-EP-313, "Offsite Dose Assessment using the Unified RASCAL Interface."

QUICK GUIDE FOR MONITORED RELEASE ASSESSMENT Select the URI icon. from the computer desktop.

Select Detailed Assessment icon I e;) ~iJed I located at top of startup window.

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: AUTOMATED DOSE ASSESSMENT PROGRAM Proc No EI-6.9 Revision 8 Page 5 of 11 6.2.3 Select applicable source term (eg, Normal Coolant, Reactor Core Accident, Spent Fuel Accident, Gas Decay Tank).

6.2.4 Input additional information for selected source term (eg, spiking factor, clad damage or melt, fuel age new or old}.

6.2.5 Select meteorological data source (eg, on site 10 meter tower) 6.2.6 Enter wind speed.

6.2.7 Enter wind direction (degrees from).

6.2.8 Select stability class.

6.2.9 Select precipitation type.

6.2.10 Select reactor status (or last irradiated if spent fuel accident was selected for source term) editing date and time as needed.

6.2.11 Enter release duration or use program default of 2.00 hours0 days 0 hours 0 weeks 0 months .

6.2.12 Select release pathway button to right of pathway bar to open release pathway selection window.

6.2.13 Select applicable release pathway button from pathway selection window.

6.2.14 Select ACCEPT button from bottom of pathway selection window.

6.2.15 Select "Monitored" TAB located upper right of display window.

6.2.16 Select valid monitor.

6.2.17 Enter selected monitor reading.

6.2.18 Enter release point flow rate if applicable (some monitors do not require a flow rate).

6.2.19 Select the 10 or 50 mile Process Assessment button (a green progress bar will be displayed).

6.2.20 Results for dose assessment by distance will be displayed.

6.2.21 Select the GLOBE icon below the Monitored tab to view PAR graphic.

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: AUTOMATED DOSE ASSESSMENT PROGRAM Proc No EI*6.9 Revision 8 Page 6 of 11 6.2.22 IF the output graphic indicates that "PAGs ARE EXCEEDED," THEN:

6.2.23 6.3 6.3.1 6.3.2 6.3.3 6.3.4 6.3.5 6.3.6 6.3.7 6.3.8 6.3.9 6.3.10 6.3.11 6.3.12 6.3.13

a.

Print the Detailed Dose Assessment report by selecting the PRINTER icon located below the Monitored tab.

b.

Immediately notify the Radiological Assessment Coordinator and/or Emergency Director that PAGs are exceeded.

Continue to perform calculations by changing any or all input values as needed and select the 10 mile or 50 mile button again. If only changing one field, it may be necessary to click out of that field or click the Force Recalculation button to get the 10 mile or 50 mile process buttons to appear.

QUICK GUIDE FOR CONTAINMENT LEAKAGE ASSESSMENT Select the URI icon. from the computer desktop.

Select Detailed Assessment icon I t;J ~taiJedllocated at top of startup window.

Select applicable source term (eg, Normal Coolant, Reactor Core Accident).

Input additional information for selected source term (eg, spiking factor, clad damage or melt).

Select meteorological data source (eg, on site 10 meter tower).

Enter wind speed.

Enter wind direction (degrees from).

Select stability class.

Select precipitation type.

Select reactor status (eg, reactor shutdown or not) editing date and time as needed.

Enter release duration or use program default of 2.00 hours0 days 0 hours 0 weeks 0 months .

Select release pathway button to right of pathway bar to open release pathway selection window.

Select applicable release pathway button from pathway selection window.

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: AUTOMATED DOSE ASSESSMENT PROGRAM Proc No EI-S.9 Revision 8 Page 7 of 11 6.3.14 Select ACCEPT button from bottom of pathway selection window.

6.3.15 Select "Containment Leakage" TAB located upper right of display window.

6.3.16 Select method for magnitude of the source entering percent of fuel damage or containment monitor with valid monitor reading.

6.3.17 Select release mode from containment entering percent of leakage per day or calculated leak rate in CFM.

6.3.18 Select the 10 or 50 mile Process Assessment button (a green progress bar will be displayed).

6.3.19 Results for dose assessment by distance will be displayed.

6.3.20 Select the GLOBE icon below the Monitored tab to view PAR graphic.

6.3.21 IF the output graphic indicates that "PAGs ARE EXCEEDED," THEN:

a.

Print the Detailed Dose Assessment report by selecting the PRINTER icon located below the Monitored tab.

b.

Immediately notify the Radiological Assessment Coordinator and/or Emergency Director that PAGs are exceeded.

6.3.22 Continue to perform calculations by changing any or all input values as needed and select the 10 mile or 50 mile button again. If only changing one field, it may be necessary to click out of that field or click the Force Recalculation button to get the 10 mile or 50 mile process buttons to appear.

6.4 QUICK GUIDE FOR REACTOR COOLANT SYSTEM (RCS) LEAKAGE ASSESSMENT 6.4.1 6.4.2 6.4.3 6.4.4 6.4.5 Select the URI icon II from the computer desktop.

Select Detailed Assessment icon Ie;. Oetailedllocated at top of startup window.

Select applicable source term (eg, Normal Coolant, Reactor Core Accident).

Input additional information for selected source term (eg, spiking factor, clad damage or melt).

Select meteorological data source (eg, on site 10 meter tower).

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: AUTOMATED DOSE ASSESSMENT PROGRAM 6.4.6 Enter wind speed.

6.4.7 Enter wind direction (degrees from).

6.4.8 Select stability class.

6.4.9 Select precipitation type.

Proc No EI-S.9 Revision 8 Page 8 of 11 6.4.10 Select reactor status (eg, reactor shutdown or not) editing date and time as needed.

6.4.11 Enter release duration or use program default of 2.00 hours0 days 0 hours 0 weeks 0 months .

6.4.12 Select release pathway button to right of pathway bar to open release pathway selection window.

6.4.13 Select applicable release pathway button from pathway selection window.

6.4.14 Select ACCEPT button from bottom of pathway selection window.

6.4.15 Select "RCS Leakage" TAB located upper right of display window.

6.4.16 Select method for magnitude of the source entering percent of fuel damage or containment monitor with valid monitor reading.

6.4.17 Select release mode for leakage from the Reactor Coolant System.

6.4.18 Select the 1 0 or 50 mile Process Assessment button (a green progress bar will be displayed).

6.4.19 Results for dose assessment by distance will be displayed.

6.4.20 Select the GLOBE icon below the Monitored tab to view PAR graphic.

6.4.21 IF the output graphic indicates that "PAGs ARE EXCEEDED," THEN:

a.

Print the Detailed Dose Assessment report by selecting the PRINTER icon located below the Monitored tab.

b.

Immediately notify the Radiological Assessment Coordinator and/or Emergency Director that PAGs are exceeded.

6.4.22 Continue to perform calculations by changing any or all input values as needed and select the 10 mile or 50 mile button again. If only changing one field, it may be necessary to click out of that field or click the Force Recalculation button to get the 10 mile or 50 mile process buttons to appear.

6.5 6.5.1 6.5.2 6.5.3 6.5.4 6.5.5 6.5.6 6.5.7 6.5.8 6.5.9 6.5.10 6.5.11 6.5.12 6.5.13 6.5.14 6.5.15 6.5.16 6.5.17 6.5.18 6.5.19 PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: AUTOMATED DOSE ASSESSMENT PROGRAM QUICK GUIDE FOR FIELD TEAM ASSESSMENT Select the URI icon. from the computer desktop.

Proc No EI-S.9 Revision 8 Page 9 of 11 Select Detailed Assessment icon 1.):t>e~ilfH:illocated at top of startup window.

Select applicable source term (eg, Normal Coolant, Reactor Core Accident).

Input additional information for selected source term (eg, spiking factor, clad damage or melt).

Select meteorological data source (eg, on site 10 meter tower).

Enter wind speed.

Enter wind direction (degrees from).

Select stability class.

Select precipitation type.

Select reactor status (eg, reactor shutdown or not) editing date and time as needed.

Enter release duration or use program default of 2.00 hours0 days 0 hours 0 weeks 0 months .

Select release pathway button to right of pathway bar to open release pathway selection window.

Select applicable release pathway button from pathway selection window.

Select ACCEPT button from bottom of pathway selection window.

Select "Field Team" TAB located upper right of display window.

Enter downwind distance (in miles) of survey location.

Enter gamma survey dose rate (in mR/hr).

If available, enter 1-131 concentration (in uCi/cc).

Edit date and time survey was performed.

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: AUTOMATED DOSE ASSESSMENT PROGRAM Proc No EI-6.9 Revision 8 Page 10 of 11 6.5.20 Select the 10 or 50 mile Process Assessment button (a green progress bar will be displayed).

6.5.21 Results for dose assessment by distance will be displayed.

6.5.22 Select the GLOBE icon below the Monitored tab to view PAR graphic.

6.5.23

!E the output graphic indicates that "PAGs ARE EXCEEDED," THEN:

6.5.24 6.6 6.6.1

a.

Print the Detailed Dose Assessment report by selecting the PRINTER icon located below the Monitored tab.

b.

Immediately notify the Radiological Assessment Coordinator and/or Emergency Director that PAGs are exceeded.

Continue to perform calculations by changing any or all input values as needed and select the 10 mile or 50 mile button again. If only changing one field, it may be necessary to click out of that field or click the Force Recalculation button to get the 10 mile or 50 mile process buttons to appear.

QUICK GUIDE FOR SUMMATION ASSESSMENT Select the URI icon H from the computer desktop.

6.6.2 Select blue SIGMA icon SumAssessments located at top of startup window.

6.6.3 Select the "Browse" on first line of the summation form.

6.6.4 From the "Open Dose Assessment Results File" window, open the folder of interest containing dose assessment results (file folders are dated).

6.6.5 Double click the selected dose assessment file ensuring it is added to the summation table.

6.6.6 Repeat Steps 6.6.3 through 6.6.5 to add additional dose assessment results to the summation table (10 mile and 50 mile results cannot be intermixed, the program will not sum results correctly).

6.6.7 To clear a file from the summation table, select the applicable Red X 6.6.8 There is no Process Assessment button for Summation. When there are no errors in the file selections, the program will automatically sum.

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: AUTOMATED DOSE ASSESSMENT PROGRAM Proc No EI*6.9 Revision 8 Page 11 of 11 6.6.9 Results for Summation Dose Assessment by distance and PAR graphic will be displayed.

6.6.10 IF the output graphic indicates that "PAGs ARE EXCEEDED," THEN:

6.6.11 7.0

a.

Print the Summation Dose Assessment report by selecting the PRINTER icon.

b.

Immediately notify the Radiological Assessment Coordinator and/or Emergency Director that PAGs are exceeded.

Continue to perform calculations and Summation Assessments as needed.

ATTACHMENTS AND RECORDS None 8.0 SPECIAL REVIEWS The scope of this procedure does not include activities that require a 50.59 review.

Therefore, changes to this procedure do not require a 50.59 review.

Revisions of this procedure require a 50.54(q) review per Entergy Procedure EN-EP-305, "Emergency Planning 10CFR50.54(q) Review Program."

Procedure No EI-6.10 Revision 7 Effective Date 01/28/16 PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: OFFSITE DOSE CALCULATION - STRAIGHT LINE GAUSSIAN (MANUAL METHOD)

Approved: DGMalone 1

Procedure Sponsor I Process Applicability Exclusion D

New Procedure/Revision Summary:

Rev 7, Editorial Correction Specific Changes:

Revision 7

- 3.2.1 and 5.0 Updated procedure EI-6.0 from "Rapid Dose Calculation Offsite Dose Calculation and Recommendations for Protective Actions" to "Rapid Dose Calculation"

- 3.2.5 Removed reference to the EN-OM-119, "On-Site Safety Review Committee" 01/21/16 Date

- 8.0 Removed references to the "Plant Operating Review Committee" and "On-Site Safety Review Committee" under the Special Reviews section. (DRN-13-00962, DRN-15-01432)

Revision 6 - Editorial Incorporated PCR-01051546 & DRN-09-02049 Minor editorial changes to Emergency Personnel titles to align with Emergency Planning Standard Organization.

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE Proc No EI-6.10 Revision 7 Page i TITLE: OFFSITE DOSE CALCULATION - STRAIGHT LINE GAUSSIAN (MANUAL METHOD)

Table of Contents 1.0 PERSONNEL RESPONSIBILITY.................................................................................. 1 2.0 PURPOSE...................................................................................................................... 1

3.0 REFERENCES

............................................................................................................... 1 3.1 SOURCE DOCUMENTS................................................................................ 1 3.2 REFERENCE DOCUMENTS......................................................................... 1 4.0 DEFINITIONS................................................................................................................. 2 4.1 CDE................................................................................................................ 2 4.2 CEDE............................................................................................................. 2 4.3 DOE................................................................................................................ 2 4.4 TEDE.............................................................................................................. 2 4.5 RELEASE OF RADIOACTIVE MATERIAL................................................... 2 5.0 INITIAL CONDITIONS ANDIOR REQUiREMENTS....................................................... 2 6.0 PROCEDURE................................................................................................................. 3 7.0 ATTACHMENTS AND RECORDS................................................................................. 3 7.1 ATTACHMENTS............................................................................................ 3 7.2 RECORDS..................................................................................................... 3 8.0 SPECIAL REVIEWS...................................................................................................... 3 ATTACHMENTS, "Manual Dose Work Sheet"

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE Proc No EI-6.10 Revision 7 Page 1 of 3 TITLE: OFFSITE DOSE CALCULATION - STRAIGHT LINE GAUSSIAN (MANUAL METHOD)

INFORMATIONAL USE Procedure is available and referenced for review, but not necessarily at the work location.

Procedure may be performed from memory or referred to as needed.

User remains responsible for procedure adherence.

1.0 PERSONNEL RESPONSIBILITY The Radiological Assessment Coordinator is responsible for the implementation of this procedure. In the absence of a Radiological Assessment Coordinator, the Emergency Plant Manager or Emergency Director shall delegate this responsibility.

2.0 PURPOSE This procedure implements the same equations and assumptions as used in the automated dose calculations. All calculations are performed manually through the use of precalculated dose factors for whole body dose rates and thyroid dose rates.

Results from this procedure can be used to check the dose calculations performed in the automated dose assessment program "Offsite."

3.0 REFERENCES

3.1 SOURCE DOCUMENTS 3.1.1 NUREG 0654 Section I, "Accident Assessment" 3.1.2 EPA-400 Manual, "Protective Action Guideline and Protective Actions for Nuclear Incidents" 3.2 REFERENCE DOCUMENTS 3.2.1 Emergency Implementing Procedure EI-6.0, "Rapid Dose Calculation" 3.2.2 Emergency Implementing Procedure EI-1, "Emergency Classification and Actions" 3.2.3 Entergy Procedure EN-AD-103, "Document Control and Records Management Programs" 3.2.4 Entergy Procedure EN-EP-305, "Emergency Planning 1 OCFR50.54(q) Program"

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE Proc No EI-6.10 Revision 7 Page 2 of 3 TITLE: OFFSITE DOSE CALCULATION - STRAIGHT LINE GAUSSIAN (MANUAL METHOD) 4.0 DEFINITIONS 4.1 CDE Committed Dose Equivalent: 50-year integrated dose to organs or tissues due to an intake at time zero.

4.2 CEDE Committed Effective Dose Equivalent: The dose committed to an individual over the next 50 years due to intake of radioactive material, weighted (by organ) to represent a risk equivalent to that of whole body exposure.

4.3 DOE Deep Dose Equivalent: Dose equivalent due to external radiation at 1 cm tissue depth.

4.4 TEDE Total Effective Dose Equivalent: Sum of deep dose equivalent due to external radiation exposure and committed effective dose equivalent due to internal exposure. When no other designator is applied to dose in units of rem, TEDE is implied.

4.5 RELEASE OF RADIOACTIVE MATERIAL Any discharge of radioactive effluent to the environment that is the result of or associated with the emergency event.

5.0 INITIAL CONDITIONS ANDIOR REQUIREMENTS This procedure shall be implemented per Emergency Implementing Procedure EI-6.0, "Rapid Dose Assessment," when there is a potential for, or an actual significant release of radioactive materials from the Plant site (as specified by Emergency Implementing Procedure EI-1, "Emergency Classification and Actions"),

and the automated dose assessment program "Offsite" is not available.

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE Proc No EI-S.1 0 Revision 7 Page 3 of 3 TITLE: OFFSITE DOSE CALCULATION - STRAIGHT LINE GAUSSIAN (MANUAL METHOD) 6.0 PROCEDURE INFORMATIONAL USE Procedure is available and referenced for review, but not necessarily at the work location.

Procedure may be performed from memory or referred to as needed.

User remains responsible for procedure adherence.

6.1 From the attached work sheets, select the one corresponding to the current Pasquill stability category (A - G).

6.2 Record the required input information in Items 1 through 6, for any applicable page of each stability class.

6.3 Complete dose calculations per instructions on the work sheet.

6.4 All completed attachments should be forwarded to the Radiological Assessment Coordinator or designee for review.

7.0 ATTACHMENTS AND RECORDS 7.1 ATTACHMENTS, "Manual Dose Work Sheet" 7.2 RECORDS Records generated by this procedure shall be filed in accordance with Entergy Procedure EN-AD-103, "Document Control and Records Management Programs."

8.0 SPECIAL REVIEWS The scope of this procedure does not include activities that require a 50.59 review.

Therefore, changes to this procedure do not require a 50.59 review.

Revisions of this procedure require a 50.54(q) review per Entergy Procedure EN-EP-305, "Emergency Planning 10CFR50.54(q) Program."

MANUAL DOSE WORK SHEET GROUND LEVEL RELEASE Stability A Proc No EI-6.10 Revision 7 Page 1 of 7

1.

Noble Gas Release Rate (Ci/sec)

(A)

2.

Iodine Release Rate (Ci/sec)

3.

Wind Speed (mph)

4.

Stability Class (A-G)

5.

Release Duration (hours)

6.

Average Energy (Mev)

Wholebody DDE Dose Factor Wholebody Dose Rate (mrem/hr)

(A x G x F)/C Wholebody Dose (mrem)

HxE Thyroid CDE Factor Thyroid CDE Rate (mrem/hr)

(B x J)/C Thyroid CDE (mrem)

KxE TEDE Rate (mrem/hr)

H + (K/30)

TEDE (mrem)

I + (L/30)

(B)

(C)

A (D)

(E) (Default = 2 hrs)

(F) (Default = 0.7)

Downwind Distances (Miles) 0.5 Mi 2 Mi 10 Mi 9.780E+00 3.434E-01 5 Mi 1.723E-01 9.275E-02 (G)

(H)

(I) 1.837E+04 4.760E+02 1.875E+02 9.037E+01 (J)

(K)

(L)

(M)

(N)

Above doses based on actual/potential (circle one) releases.

Date: ____ Time: ____ Completed By: __________ _

MANUAL DOSE WORK SHEET GROUND LEVEL RELEASE Stability B Proc No EI-6.10 Revision 7 Page 2 of7

1.

Noble Gas Release Rate (Cilsec)

(A)

2.

Iodine Release Rate (Ci/sec)

3.

Wind Speed (mph)

4.

Stability Class (A-G)

5.

Release Duration (hours)

6.

Average Energy (Mev)

Wholebody (DDE) Dose Factor Wholebody Dose Rate (mrem/hr)

(A x G x F)/C Wholebody Dose (mrem)

HxE Thyroid CDE Factor Thyroid CDE Rate (mrem/hr)

(B x J)/C Thyroid CDE (mrem)

KxE TEDE Rate (mrem/hr)

H + (K/30)

TEDE (mrem) 1+ (L/30)

(B)

(C)

B (D)

(E) (Default = 2 hrs)

(F) (Default = 0.7)

Downwind Distances (Miles) 0.5 Mi 2 Mi 5 Mi 10 Mi 3.199E+01 2.979E+00 6.071 E-01 1.616E-01 (G)

(H)

(I) 8.185E+04 4.827E+03 6.987E+02 1.575E+02 (J)

(K)

(L)

(M)

(N)

Above doses based on actual/potential (circle one) releases.

Date: ____ Time: ____ Completed By: __________ _

MANUAL DOSE WORK SHEET GROUND LEVEL RELEASE Stability C Proc No EI-S.10 Revision 7 Page 3 of7

1.

Noble Gas Release Rate (Ci/sec)

(A)

2.

Iodine Release Rate (Cilsec)

3.

Wind Speed (mph)

4.

Stability Class (A-G)

5.

Release Duration (hours)

6.

Average Energy (Mev)

Wholebody (DDE) Dose Factor Wholebody Dose Rate (mrem/hr)

(A x G x F)/C Wholebody Dose (mrem)

HxE Thyroid CDE Factor Thyroid CDE Rate (mrem/hr)

(B x J)/C Thyroid CDE (mrem)

KxE TEDE Rate (mrem/hr)

H + (K/30)

TEDE (mrem) 1+ (L/30)

(B)

(C)

C (D)

(E) (Default = 2 hrs)

(F) (Default = 0.7)

Downwind Distances (Miles) 0.5 Mi 2 Mi 5 Mi 10 Mi 5.496E+01 7.591 E+OO 1.976E+00 6.343E-01 (G)

(H)

(I) 1.792E+05 1.403E+04 2.410E+03 6.180E+02 (J)

(K)

(L)

(M)

(N)

Above doses based on actual/potential (circle one) releases.

Date: ____ Time: ____ Completed By: __________ _

MANUAL DOSE WORK SHEET GROUND LEVEL RELEASE Stability D Proc No EI-6.10 Revision 7 Page 4 of7

1.

Noble Gas Release Rate (Ci/sec)

(A)

2.

Iodine Release Rate (Ci/sec)

3.

Wind Speed (mph)

4.

Stability Class (A-G)

5.

Release Duration (hours)

6.

Average Energy (Mev)

Wholebody (DDE) Dose Factor Wholebody Dose Rate (mrem/hr)

(A x G x F)/C Wholebody Dose (mrem)

HxE Thyroid CDE Factor Thyroid CDE Rate (mrem/hr)

(B x J)/C Thyroid CDE (mrem)

KxE TEDE Rate (mrem/hr)

H + (K/30)

TEDE (mrem)

I + (L/30)

(B)

(C)

D (D)

(E) (Default = 2 hrs)

(F) (Default = 0.7)

Downwind Distances (Miles) 0.5 Mi 2 Mi 5 Mi 10 Mi 9.378E+01 2.070E+01 7.572E+00 3.578E+00 (G)

(H)

(I) 4.298E+05 5.087E+04 1.184E+04 3.875E+03 (J)

(K)

(L)

(M)

(N)

Above doses based on actual/potential (circle one) releases.

Date: ____ Time: ____ Completed By: __________ _

MANUAL DOSE WORK SHEET GROUND LEVEL RELEASE Stability E Proc No EI-S.10 Revision 7 Page 50f7

1.

Noble Gas Release Rate (Ci/sec)

(A)

2.

Iodine Release Rate (Ci/sec)

3.

Wind Speed (mph)

4.

Stability Class (A-G)

5.

Release Duration (hours)

6.

Average Energy (Mev)

Wholebody (DDE) Dose Factor Wholebody Dose Rate (mrem/hr)

(A x G x F)/C Wholebody Dose (mrem)

HxE Thyroid CDE Factor Thyroid CDE Date (mrem/hr)

(B x J)/C Thyroid CDE (mrem)

KxE TEDE Rate (mrem/hr)

H + (K/30)

TEDE (mrem) 1+ (L/30)

(B)

(C)

E (D)

(E) (Default = 2 hrs)

(F) (Default = 0.7)

Downwind Distances (Miles) 0.5 Mi 2 Mi 5 Mi 10 Mi 1.328E+02 3.498E+01 1.429E+01 7.427E+00 (G)

(H)

(I) 7.506E+05 1.060E+05 2.755E+04 9.916E+03 (J)

(K)

(L)

(M)

(N)

Above doses based on actual/potential (circle one) releases.

Date: ____ Time: ____ Completed By: __________ _

MANUAL DOSE WORK SHEET GROUND LEVEL RELEASE Stability F Proc No EI-6.10 Revision 7 Page 6 of 7

1.

Noble Gas Release Rate (Ci/sec)

(A)

2.

Iodine Release Rate (Ci/sec)

3.

Wind Speed (mph)

4.

Stability Class (A-G)

5.

Release Duration (hours)

6.

Average Energy (Mev)

Wholebody (DDE) Dose Factor Wholebody Dose Rate (mrem/hr)

(A x G x F)/C Wholebody Dose (mrem)

HxE Thyroid CDE Factor Thyroid CDE Rate (mrem/hr)

(8 x J)/C Thyroid CDE (mrem)

KxE TEDE Rate (mrem/hr)

H + (K/30)

TEDE (mrem)

I + (L/30)

(8)

(C)

F (D)

(E) (Default = 2 hrs)

(F) (Default = 0.7)

Downwind Distances (Miles) 0.5 Mi 2 Mi 5 Mi 10 Mi 1.775E+02 6.136E+01 2.769E+01 1.537E+01 (G)

(H)

(I) 1.251 E+06 2.287E+05 6.508E+04 2.484E+04 (J)

(K)

(L)

(M)

(N)

Above doses based on actual/potential (circle one) releases.

Date: ____ Time: ____ Completed 8y: __________ _

MANUAL DOSE WORK SHEET GROUND LEVEL RELEASE Stability G Proc No EI-6.10 Revision 7 Page 7 of7

1.

Noble Gas Release Rate (Ci/sec)

(A)

2.

Iodine Release Rate (Ci/sec)

3.

Wind Speed (mph)

4.

Stability Class (A-G)

5.

Release Duration (hours)

6.

Average Energy (Mev)

Wholebody (DDE) Dose Factor Wholebody Dose Rate (mrem/hr)

(A x G x F)/C Wholebody Dose (mrem)

HxE Thyroid CDE Factor Thyroid CDE Rate (mrem/hr)

(B x J)/C Thyroid CDE (mrem)

KxE TEDE Rate (mrem/hr)

H + (K/30)

TEDE (mrem) 1+ (L/30)

(B)

(C)

G (D)

(E) (Default = 2 hrs)

(F) (Default = 0.7)

Downwind Distances (Miles) 0.5 Mi 2 Mi 5 Mi 10 Mi 1.810E+02 9.741 E+01 4.940E+01 2.871 E+01 (G)

(H)

(I) 1.833E+06 5.007E+05 1.557E+05 6.094E+04 (J)

(K)

(L)

(M)

(N)

Above doses based on actual/potential (circle one) releases.

Date: ____ Time: ____ Completed By: __________ _

Procedure No EI-12.1 Revision 19 Effective Date 1/26/16 PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: PERSONNEL ACCOUNTABILITY AND ASSEMBLY Approved: MEFields 1

1/21/16 Procedure Sponsor Date I Process Applicability Exclusion New Procedure/Revision Summary:

Rev 19, Editorial Correction Specific Changes DRN-13-00948, 15-01456 Removed reference to Plant Operating Review Committee and On Site Safety Review Committee under Special Reviews Removed reference to EN-OM-119 Revision 18 DRN-11-00597: Removed reference to SIP-21. Changed language under Records to None.

Revision 16 - Editorial DRN-09-02070 Titles for the Emergency Response Organization members were changed to reflect standardization to the Entergy Fleet Standard Organization chart.

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE Proc No EI-12.1 Revision 19 Page i TITLE: PERSONNEL ACCOUNTABILITY AND ASSEMBLY Table of Contents 1.0 PERSONNEL RESPONSIBILITY.................................................................................. 1 2.0 PURPOSE...................................................................................................................... 1

3.0 REFERENCES

............................................................................................................... 2 3.1 SOURCE DOCUMENTS................................................................................ 2 3.2 REFERENCE DOCUMENTS......................................................................... 2 4.0 INITIAL CONDITIONS ANDIOR REQUiREMENTS....................................................... 2 5.0 PROCEDURE................................................................................................................. 3 5.1 ACCOUNTABILITY........................................................................................ 3 5.2 ASSEMBLY................................................................................................... 4 5.3 REVIEW OF ACCOUNTABILITY INSTRUCTIONS.......................................4 6.0 ATTACHMENTS AND RECORDS................................................................................. 4 6.1 ATTACHMENTS............................................................................................ 4 6.2 RECORDS........................................................................,............................ 5 7.0 SPECIAL REVIEWS...................................................................................................... 5

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE Proc No EI-12.1 Revision 19 Page 1 of 5 TITLE: PERSONNEL ACCOUNTABILITY AND ASSEMBLY REFERENCE USE Procedure and Procedure Precautions and Limitations are at the work location for reference.

Review and understand segments before performing any steps.

Signoff steps are completed, when included, before starting the next step.

Place keep in accordance with EN-HU-106, "Procedure and Work Instruction Use and Adherence."

Review the Procedure to verify segments have been completed.

1.0 PERSONNEL RESPONSIBILITY 1.1 The Security Manager has overall responsibility for accounting of all personnel inside the Protected Area.

1.2 Emergency facility leaders (within the Protected Area) are responsible for ensuring personnel in their facility use the accountability proximity card readers or, in the event the card readers are unavailable, completing manual accountability and reporting results to Security in a timely manner.

1.3 Individual employees and contractors are responsible for reporting to the appropriate Assembly Area when the emergency siren is sounded and/or when directed by a public address announcement.

2.0 PURPOSE 2.1 This procedure is written to provide guidelines for conducting personnel accountability within the Protected Area, and assembly in the Assembly Areas outside the Protected Area.

2.2 The purpose for Accountability and Assembly are:

a.

To provide some level of radiological protection in the event that a radiological release is in progress or is imminent.

b.

To gather personnel in preparation for evacuation.

c.

To provide the Emergency Plant Manager with a list of personnel within the Protected Area that may be missing or injured.

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE Proc No EI-12.1 Revision 19 Page 2 of 5 TITLE: PERSONNEL ACCOUNTABILITY AND ASSEMBLY

3.0 REFERENCES

3.1 SOURCE DOCUMENTS 3.1.1 Site Emergency Plan, Section 6, "Emergency Measures" 3.1.2 NUREG 0654, Section J, "Protective Measures" 3.2 REFERENCE DOCUMENTS 3.2.1 Entergy Procedure EN-AD-103, "Document Control and Records Management Programs" 3.2.2 Entergy Procedure EN-EP-305, "Emergency Planning 1 OCFR50.54(q) Program" 3.2.3 Palisades Administrative Procedure 10.41, "Site Procedure Process" 3.2.4 Entergy Procedure EN-HU-106, Procedure and Work Instruction Use and Adherence" 4.0 INITIAL CONDITIONS ANDIOR REQUIREMENTS 4.1 The Control Room has sounded the emergency siren (2-minute continuous siren),

and/or a public address announcement has been made directing personnel to report to their assigned Assembly Areas.

4.2 Some key plant personnel may be outside the Protected Area when the emergency siren is sounded and/or the public address announcement is made. They may be allowed to process into the Protected Area before accountability is complete.

4.3 In the event the Proximity Card reader system is unavailable, manual accountability will be performed.

4.4 Emergency Response Organization (ERO) personnel shall report to their designated emergency facility unless directed otherwise.

4.5 Individuals whose Assembly Area is within the Protected Area shall present their Identification Badge to the proximity card reader.

4.6 If necessary, personnel can contact Security and report their name, badge number, and location.

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE Proc No EI-12.1 Revision 19 Page 3 of 5 TITLE: PERSONNEL ACCOUNTABILITY AND ASSEMBLY 5.0 PROCEDURE REFERENCE USE Procedure and Procedure Precautions and Limitations are at the work location for reference.

Review and understand segments before performing any steps.

Signoff steps are completed, when included, before starting the next step.

Place keep in accordance with EN-HU-106, "Procedure and Work Instruction Use and Adherence."

Review the Procedure to verify segments have been completed.

5.1 ACCOUNTABILITY 5.1.1 Accountability is the process of identifying all personnel inside the Protected Area following the declaration of an Alert or higher. Accountability should be completed in approximately 30 minutes.

5.1.2 Assembly Areas inside the Protected Area are:

a.

Assembly Area I (Control Room)

b.

Assembly Area II (Technical Support Center)

c.

Assembly Area V (Operations Support Center)

d.

Assembly Area VI (Men's Locker Room - Service Building)

e.

Assembly Area VIII (Security Building, Administrative Area) 5.1.3 The Emergency Facility Leader or designee shall ensure accountability is completed in their Assembly Area.

In the event the Proximity Card reader system is not available, manual accountability shall be completed and results delivered to Security. If radiological conditions prohibit hand carrying the list, it may be reported by faxing to Security or by telephone.

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE Proc No EI-12.1 Revision 19 Page 4 of 5 TITLE: PERSONNEL ACCOUNTABILITY AND ASSEMBLY 5.1.4 The Security Supervisor shall ensure the Accountability results are reported to the Emergency Plant Manager.

5.1.5 Plant employees and contractors should remain in the Assembly Area until:

a.

Directed to return to their work area

b.

Directed to evacuate the site 5.2 ASSEMBLY 5.2.1 Assembly is the process of gathering personnel in designated areas outside the Protected Area following the declaration of an Alert or higher.

5.2.2 Assembly Areas outside the Protected Area are:

a.

Assembly Area III (Training Building, 2nd Floor, Classroom H)

b.

Assembly Area VII (Support Building Lunchroom) 5.2.3 Plant employees and contractors should remain in the Assembly Area until:

a.

Directed to return to their work area

b.

Directed to evacuate the site 5.3 REVIEW OF ACCOUNTABILITY INSTRUCTIONS At least quarterly, Emergency Planning should review the manual accountability instructions and make changes as needed.

6.0 ATTACHMENTS AND RECORDS 6.1 ATTACHMENTS None

PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE Proc No EI-12.1 Revision 19 Page 50f5 TITLE: PERSONNEL ACCOUNTABILITY AND ASSEMBLY 6.2 RECORDS None 7.0 SPECIAL REVIEWS 7.1 The scope of this procedure does not include activities that require a 50.59 review per Palisades Administrative Procedure 10.41, "Site Procedure Process."

Therefore, changes to this procedure do not require a 50.59 review.

7.2 Revisions to this procedure require a 50.54(q) review per Entergy Procedure EN-EP-305, "Emergency Planning 10CFR50.54(q) Program."

=::- Entergy PNP 2016-012 February 16, 2016 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Entergy Nuclear Operations, Inc.