ML20071G833

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Emergency Plan, Revision 80
ML20071G833
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 03/11/2020
From: Emily Larson
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO2020/00011
Download: ML20071G833 (230)
v • d • e


Text

  • Entergy
  • ~w... Entergy Operations, Inc.

P.O. Box756 Port Gibson, Mississippi 39150 Eric A. Larson Site Vice President Grand Gulf Nuclear Station Tel: 601 -437-7500 10 CFR 50.54(q)(5)

GNRO2020/00011 March 11, 2020 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Emergency Plan, Revision 80 Grand Gulf Nuclear Station, Unit 1 NRG Docket No. 50-416 Renewed Facility Operating License No. NPF-29

Dear Sir or Madam:

In accordance with 10CFR50 Appendix E(V), 10 CFR 50.54(q)(5), 10 CFR 50.4(b)(5)(i),

10 CFR 72.44(f) and 10 CFR 72.4, Entergy Operations Inc. (Entergy) hereby submits Revision 80 to the Grand Gulf Nuclear Station (GGNS) Emergency Plan, including a summary and analysis of the changes, which became effective February 28, 2020.

The changes to the GGNS Emergency Plan were evaluated by Entergy and determined to not reduce the effectiveness of the plan. Attachment 1 contains the Summary and Analysis of the Emergency Plan Changes. Attachment 2 contains the GGNS Emergency Plan Revision 80.

This letter contains no new commitments.

If you have any questions concerning this submittal, please contact Mr. Mike Lewis, Manager Emergency Planning, at (601) 437-2166.

Sincerely,

~~/wi-Eric A. Larson EAUrm Attachments: 1. Summary and Analysis of the GGNS Emergency Plan Changes

2. Grand Gulf Nuclear Station Emergency Plan Revision 80

GNAO2020/00011 Page 2 of 2 NRC Region IV - Regional Administrator NRC Senior Resident Inspector, Grand Gulf Nuclear Station State Health Officer, Mississippi Department of Health NRA Project Manager Director, Division of Spent Fuel Storage & Transportation, Office of Nuclear

Attachment 1 To GNAO2020/00011 Summary and Analysis of the GGNS Emergency Plan Changes

Attachment 2 Page 1 of 4 1 0CFR50.54(Q)j 3) Screening Procedure/Document Number: Emergency Plan IRevision: 80 Equipment/Facility/Other: GGNS

Title:

Implement NRC Approved Rev 6 EALs Part I. Description of Activity Being Reviewed (This is generally changes to the emergency plan, EALs, EAL bases, etc. - refer to Section 3.0 Step 6):

The following are changes to the GGNS EPlan 1

__Ql ange # Paoe \ Description of Change 1 1-2 Changed definition of EAL to match NEI 99-01 Rev 6 approved

- - change 2 1-4 Changed definition of HOSTILE ACTION to match NEI 99-01 1 Rev 6 approved cha129e.

3 1-7 Changed definition of UNUSUAL EVENT to match NEI 99-01 Rev 6 a~~roved change.

4 4-1 f Removed EAL charts from Emergency plan. 1O-S-01-1 is now referenced as the home for EALs. A summary of ICs is included in Table 4-1 of the E Plan -

5 4-3 Changed GENERAL EMERGENCY description to match the

- definition IAW NEI 99-01 Rev 6 a~~roved change.

6 J Table Complete re-write of Table 4-1. Just the ICs, no longer the EAL

- 4-1 charts themselves.

7 A-3 Modified cross reference for Table 4-1 to be the EAL ICs, not EAL charts themselves.

8 I A-3 I Added 10-S-01-1 as a reference to section 4.1 0YES NO Part II. Activity Previously Reviewed? 50.54(q)(3) Continue to Evaluation is next part Is this activity fully bounded by an NRC approved 10CFRS0.90 submittal or NOT required.

Alert and Notification System Design Report? Enter justification If YES, identify bounding source document number/approval reference and below and complete Part ensure the basis for concluding the source document fully bounds the VI.

proposed change is documented below:

Justification: Changes 1, 2, 3, and 5 are fully bounded in GNRI 2019-00029- NRC Approval of Rev 6 EALs.

Changes 4, 6, 7 and 8 are not bounded by an NRC document.

D Bounding document attached (optional)

Part Ill. Applicability of Other Regulatory Change Control Processes Check if any other regulatory change processes control the proposed activity.(Refer to EN-Ll-100)

N/A EN-EP-305 R008

Attachment 2 Page 2 of 4 10CFRS0.54(O)( 3) Screening Procedure/Document Number: Emergency Plan I Revision: 80 Equipment/Facility/Other: GGNS

Title:

Implement NRC Approved Rev 6 EALs APPLICABILITY CONCLUSION 18111 there are no other controlling change processes, continue the 10CFA50.54(q)(3) Screening.

D One or more controlling change processes are selected; however, some portion of the activity involves the emergency plan or affects the implementation of the emergency plan: continue the 10CFR50.54(q)(3) Screening for that portion of the activity. Identify the applicable controlling change processes below.

D One or more controlling change processes are selected and fully bounds all aspects of the activity. 1OCFA50.54(q)(3)

Evaluation Is NOT required . Identify controlling change processes below and complete Part VI.

CONTROLLING CHANGE PROCESSES 10CFR50.54(q)

Part IV. Editorial Change YES 181 NO 50.54{q)(3) Continue to Evaluation is next part Is th is activity an editorial or typographical change such as formatting, paragraph NOT required.

numbering, spelling, or punctuation that does not change intent? Enter justification Justification: " No" is checked because this activity contains other changes that are and continue not editorial. " to next part or complete Part Change 8 only adds a reference to a procedure which is an editorial change. VI as applicable.

Part V. Emergency Planning Element/Function Screen (Associated 10CFR50.47(b) planning standard function identified in brackets) Does this activity affect any of the following, including program elements from NUREG-0654/FEMA REP-1 Section II?

1. Responsibility for emergency response is assigned. [1]

D

2. The response organization has the staff to respond and to augment staff on a continuing basis (24/7 staffing) in accordance with the emergency plan . [1]

D

3. The process ensures that on shift emergency response responsibilities are staffed and assigned. [2)

D

4. The process for timely augmentation of on-shift staff is established and maintained . (2)

D

5. Arrangements for requesting and using off site assistance have been made. [3) 6.

State and local staff can be accommodated at the EOF in accordance with the emergency plan. [3)

7. A standard scheme of emergency classification and action levels is in use . [4]

~

8. Procedures for notification of State and local governmental agencies are capable of alerting them of the declared emergency within 15 minutes after declaration of an emergency and providing follow-up notifications. [5) 9.

Administrative and physical means have been established for alerting and providing prompt instructions to the public w ithin the plume exposure pathway. (5)

10. The public ANS meets the design requirements of FEMA*AEP- 10, Guide for Evaluation of Alert and Notification Systems for Nuclear Power Plants or complies with the licensee 's FEMA-approved ANS design report and supporting FEMA approval letter. [5)

EN-EP-305 ROOS

Attachment 2 Page 3 of 4 1 0CFR50.54{Q)(3) Screenina Procedure/Document Number: Emergency Plan Revision: 80 I Equipment/Facility/Other: GGNS

Title:

Implement NRC Approved Rev 6 EALs 11 . Systems are established for prompt communication among principal emergency response organizations. (6)

12. Systems are established for prompt communication to emergency response personnel. [6)
13. Emergency preparedness information is made available to the public on a periodic basis within the plume exposure pathway emergency planning zone (EPZ). [7)
14. Coordinated dissemination of public information during emergencies is established . (7)
15. Adequate facilities are maintained to support emergency response. [8)
16. Adequate equipment is maintained to support emergency response . (8)
17. Methods, systems, and equipment for assessment of radioactive releases are in use. [9)
18. A range of public PARs is available for implementation during emergencies . (1 O}
19. Evacuation time estimates for the population located in the plume exposure pathway EPZ are available to support the formulation of PARs and have been provided to State and local governmental authorities . (10]

20 . A range of protective actions is available for plant emergency workers during emergencies, including those for hostile action events.[10)

EN-EP-305 R00B

Attachment 2 Page 4 of 4 10CFR50.54(Q)(3) Screening Procedure/Document Number: Emergency Plan Revision: 80 I Equipment/Facility/Other: GGNS

Title:

Implement NRC Approved Rev 6 EALs 21 . The resources for controlling radiological exposures for emergency workers are established. [11]

22. Arrangements are made for medical services for contaminated, injured individuals. [12)
23. Plans for recovery and reentry are developed . [13)
24. A drill and exercise program (including radiological, medical, health physics and other program areas) is established. [14)
25. Drills, exercises, and training evolutions that provide performance opportunities to develop, maintain, and demonstrate key skills are assessed via a formal critique process in order to identify weaknesses . [14]
26. Identified weaknesses are corrected. (14)
27. Training is provided to emergency responders . [15]
28. Responsibility for emergency plan development and review is established . [16)
29. Planners responsible for emergency plan development and maintenance are properly trained. [161 APPLICABILITY CONCLUSION
J If no Part V criteria are checked, a 10CFA50.54(q)(3) Evaluation is NOT required; document the basis for conclusion below and complete Part VI.

X If any Part V criteria are checked, complete Part VI and perform a 10CFR50.54(q)(3) Evaluation.

BASIS FOR CONCLUSION Change items 1, 2, 3, and 5 are fully bounded in GNRI 2019-00029 - NRC Approval of Rev 6 EALs.

Change item 8 is an editorial change. These items do not require further evaluation.

Screening has determined that Planning Element 10 CFR 50.47(b)[4] is potentially affected by removing the Emergency Action Levels from the GGNS Emergency Plan.

A 10 CFR 50.54(0)(3) Evaluation will be perfo rmed on change items 4, 6, and 7 to determine whether or not the effectiveness of the emergency plan is red uced , and prior NRC approval is requ ired .

Part VI. Signatures:

Preparer Name (Print) Date:

Dennis M. Coulter 1---------~~---- li.,.:..._;_~-.:=- ---------+=---... I* t'f*

.;,.;;~~~o (Optional) Reviewer Name (Print) Reviewer Signature Date; Reviewer Name (Print) Date:

James J. Lewis Nuclear EP Project Manager Approver Name (Print) Date:

Michael L. Lewis EN-EP-305 R00B

Attachment 3 Page 1 of 3 10CFR50.54(Q)(3 ) Evaluation Procedure/Document Number: Emergency Revision: 80 Plan Equipment/Facility/Other: GGNS

Title:

Implement NRC Approved Rev 6 EALs Part I. Description of Proposed Change:

The following are changes to the GGNS EPlan Change# Page Description of Change 4 4-1 Removed EAL charts from Emergency plan. 10-S-01-1 is now referenced as the home for EALs. A summary of ICs is included in Table 4-1 of the E Plan 6 Table Complete re-write of Table 4-1. Just the ICs, no longer the EAL 4-1 charts themselves.

7 A-3 Modified cross reference for Table 4-1 to be the EAL ICs, not EAL charts themselves.

Part II. Description and Review of Licensing Basis Affected by the Proposed Change:

Manually reviewed sections 1, 4 and Appendix A of the Grand Gulf Emergency Plan. No additional relevant or affected plan content was identified. A historical search of previous revisions is not applicable in this case because this revision implements NRC approval of the NEI 99-01 Rev 6 EALs for GGNS for the first time.

EAL content in previous revisions of the emergency plan is no longer relevant.

Part Ill. Describe How the Proposed Change Complies with Relevant Emergency Preparedness Regulation(s) and Previous Commitment(s) Made to the NRC:

10 CFR 50.47(bH4l - A Standard Scheme of Emergency Classification and Action Levels is in Use -

A standard emergency classification and action level scheme, the bases of which include facility system and effluent parameters, is in use by the nuclear facility licensee, and State and local response plans call for reliance on information provided by facility licensees for determinations of minimum initial offsite response measures. The EALs remain resident in procedure 10-S-01-1 "Activation of the Emergency Plan."

Procedure 10-S-01 -1 is an implementing procedure of the GGNS Emergency Plan. The procedure also contains the EAL Bases and the EAL Flowcharts used by Operations and certain ERO personnel in classifying accidents. Removing the EALs from the GGNS Emergency Plan and revising the Initiating Conditions per NRC Approval in GNRI 2019-00029 has no effect on having a standard scheme of Emergency Classification and Action Levels.

Previous NRC Commitments - Commitments made in AECM 89-0202, GNRO 97-00080, and the GGNS On-Shift Staffing Analysis Report were reviewed. Commitments in AECM 89-0202 were related to tracking due dates of Emergency Planning training to ensure ERO personnel remain qualified while actively on the ERO. The commitment in GNRO 97-00080 is related to clearly defining responsibilities of the on-shift radiological assessment function. Removing EALs from the GGNS Emergency Plan does not affect these commitments. All current NRC commitments continue to be maintained and fulfilled under this emergency plan revision.

EN-EP-305 ROOS

Attachment 3 Page 2 of 3 10CFR50.54(Q)(3) Evaluation Procedure/Document Number: Emergency Revision: 80 Plan Equipment/Facility/Other: GGNS

Title:

Implement NRC Approved Rev 6 EALs Part IV. Description of Emergency Plan Planning Standards, Functions and Program Elements Affected by the Proposed Change:

10 CFR 50.47(b)(4) - A Standard Scheme of Emergency Classification and Action Levels is in Use - A standard emergency classification and action level scheme, the bases of which include facility system and effluent parameters, is in use by the nuclear facility licensee, and State and local response plans call for reliance on information provided by facility licensees for determinations of minimum initial offsite response measures.

10 CFR 50 Appendix E Section IV.B 1-2 require a licensee to develop EALs that are used for notification and participation of State and Local Agencies.

NUREG 0654 Section I1.J.7 requires licensees to include Emergency Action Levels corresponding to projected dose to the population-at-risk.

Part V. Description of Impact of the Proposed Change on the Effectiveness of Emergency Plan Functions:

Note: The Initiating Conditions approved by the NRC In GNRI 2019-00029 are being revised in the GGNS Emergency Plan. However, the EALs are being removed .

Evaluation of removing the EALs from the GGNS Emergency Plan -

Changes 4, 6, and 7 remove EALs from the GGNS Emergency Plan. The GGNS Emergency Plan is a Licensing Basis Document that describes how the sixteen 10 CFR 50.47 planning standards are being implemented. It is not a "hands-on" procedure used by Emergency Personnel during a drill or actual event.

It is excessive detail and redundant having the EALs in the Emergency Plan . It is appropriate to remove the EALs from the Emergency Plan and replace the EALs with a reference to the implementing procedure where the EALs are located. Removing this excessive detail from the Emergency Plan has no effect in implement ing planning standard 10 CFR 50.47(b}(4l . The emergency plan effectiveness is not reduced because the EAL technical bases in revision 132 of procedure 10-S-01-1 are treated as emergency plan content in accordance with Entergy fleet procedure EN-EP-305, Emergency Planning 10CFR50.54(q)

Review Program. These technical bases contain the description of all EALs within the GGNS NEI 99-01 Rev 6 EAL scheme. Revision 132 of 10-S-01-1 is being issued concurrently with revision BO of the emergency plan.

Conclusion

EN-EP-305 ROOS

Attachment 3 Page 3 of 3 1 OCFRSO.54(0)(3) Evaluation Procedure/Document Number: Emergency Revision: 80 Plan Equipment/Facility/Other: GGNS

Title:

Implement NRC Approved Rev 6 EALs Part VI. Evaluation Conclusion Answer the following questions about the proposed change.

I. Does the proposed change comply with 10CFR50.47(b) and 10CFR50 iZ!YES ONO Appendix E?

2. Does the proposed change maintain the effectiveness of the emergency plan iZ!YES ONO (i.e., no reduction in effectiveness)?
i. Does the proposed change constitute an emergency action level scheme change? "No" is checked because the Initiating Conditions added to the YES iZ! NO emergency plan and revised definitions reflect information that received pre-NRC approval.

If questions 1 or 2 are answered NO, or question 3 answered YES, reject the proposed change, modify the proposed change and perform a new evaluation or obtain prior NRC approval under provisions of 10CFR50.90. If questions 1 and 2 are answered YES, and question 3 answered NO, implement applicable change process(es). Refer to Section 6. 7 Step 8.

Part VII. Signatures Preparer Name (Print) 0 Dennis M. Coulter  ;:: 1-+

  • t<J (Optional) Reviewer Name (Print) Reviewer Signature Date:

Reviewer Name (Print)

James J. Lewis

. Date:

Nuclear EP Project Manager (~7-2--.?D Approver Name (Print) Date:

Michael L. Lewis Emergency Planning Manager or designee I 2.~ l.OZO EN-EP-305 ROOS

Attachment 2 Page 1 of 3 10CFR50.54(Q)(3) Screenino Procedure/Document Number: Emergency Plan Revision: 80 I EquipmenUFacility/Other: GGNS

Title:

Implement NRC Approved Rev 6 EALs Part I. Description of Activity Being Reviewed (This is generally changes to the emergency plan. EALs, EAL bases, etc. - refer to Section 3.0 Step 6):

The following are changes to the GGNS EPlan Change# Page Description of Change 1 1-4 Revised definition of HOSTILE ACTION " from " ... owner controlled area" to " ... SECURITY OWNER CONTROLLED AREA" 2 Table Revised Hazard Alert Initiating Condition from "HOSTILE 4-1 ACTION within the OWNER CONTROLLED AREA ... " to "HOSTILE ACTION within the SECURITY OWNER CONTROLLED AREA. .. "

3 G-14 Revised "Other persons who may be in the public access areas J.1.d on or passing through the site or within the owner controlled area" to read "Other persons who may be in the public access areas on or passing through the site or within the EP owner controlled area" YES ~NO Part II. Activity Previously Reviewed? 50.54(q)(3) Conlinue lo Evalualion is nexl part Is this activity fully bounded by an NRC approved 10CFRS0.90 submittal or NOT required .

Alert and Notif1cat1on System Design Report? Enler justification If YES, identify bounding source document number/approval reference and below and complete Part ensure the basis for concluding the source document fully bounds the VI.

proposed change is documented below:

Justification: The use of the term "Security Owner Controlled Area" was previously reviewed. Change 3 was not previously reviewed. "No" Is checked here with a basis for conclusion for all three changes provided In Part V.

0 Bounding document attached (optional)

Part Ill. Applicability of Other Regulatory Change Control Processes Check if any other regulatory change processes control the proposed activity.(Refer to EN-Ll-100)

N/A i

APPLICABILITY CONCLUSION i

I 181 If there are no other controlling change processes, continue the 10CFR50.54(q)(3) Screening 0 One or more controlling change processes are selected; however, some portion of the activity involves the emergency plan or affects the Implementation of the emergency plan: continue the 10CFR50.54(q)(3) Screening for that portion of the activity. Identify the applicable controlling change processes below.

0 One or more controlling change processes are selected and fully bounds all aspects of the activity. 10CFRS0.54(q)(3J Evaluation is NOT required . Identify controlling change processes below and complete Part VI.

CONTROLLING CHANGE PROCESSES 10CFR50.54(q)

EN-EP-305 R008

Attachment 2 Page 2 of 3 10CFR50.54{Q)(3) Screenina Procedure/Document Number: Emergency Plan Revision: 80 I Equipment/Facility/Other: GGNS

Title:

Implement NRC Approved Rev 6 EALs Part IV. Editorial Change YES [81 NO 50.54(q)(3) Continue to Evaluation is nelCI part Is this activity an editorial or typographical change such as formatting, paragraph NOT required.

numbering, spelling, or punctuation that does not change intent? Enter justif1calion Justification: and continue to next part or complete Part I:

VI as applicable Part V. Emergency Planning Element/Function Screen (Associated 10CFR50.47(b) planning standard funclion identified in brackets) Does this activity affect any of the following, including program elements from NUREG-0654/FEMA REP-1 Section II?

1. Responsibility for emergency response is assigned. {1)
2. The response organization has the staff to respond and to augment staff on a continuing basis (24/7 staffing) in accordance with the emergency plan [1)
3. The process ensures that on shift emergency response responsibilities are staffed and assigned. [2)
4. The process for timely augmentation of on-shift staff is established and maintained, [21 5, Arrangements for requesting and using off site assistance have been made. {3)
6. State and local staff can be accommodated at the EOF in accordance with the emergency plan. [31 I 7. A standard scheme of emergency classification and action levels is in use. {4}

i 8, Procedures for notification of State and local governmental agencies are capable of alerting them of the declared emergency within 15 minutes after declaration of an emergency and providing follow-I up notifications. {SJ

9. Administrative and physical means have been established for alerting and providing prompt instructions to the public within the plume exposure pathway. [5)
10. The public ANS meets the design requirements of FEMA-REP-10, Guide for Evaluation of Alert and Notification Systems for Nuclear Power Plants or complies with the licensee's FEMA-approved ANS design report and supporting FEMA approval letter. [5]

11 . Systems are established for prompt communication among principal emergency response organizations . {6}

12. Systems are established for prompt communication to emergency response personnel. [6]
13. Emergency preparedness information is made available to the public on a periodic basis within the plume exposure pathway emergency planning zone (EPZ). [7)
14. Coordinated dissemination of public information during emergencies is established. (7)
15. Adequate facilities are maintained to support emergency response. (BJ LJ
16. Adequate equipment is maintained to support emergency response. [BJ
17. Methods, systems, and equipment for assessment of radioactive releases are in use. (9)
18. A range of public PARs is available for implementation during emergencies . [10]
19. Evacuation time estimates for the population located in the plume exposure pathway EPZ are available to support the formulation of PARs and have been provided to State and local governmental authorities. (10) I EN-EP-3O5 ROOS

Attachment 2 Page 3 of 3 10CFR50.54{Q)(3) Screening Procedure/Document Number: Emergency Plan IRevision: 80 Equipment/Facility/Other: GGNS Tltle: Implement NRC Approved Rev 6 EALs

20. A range of protective actions is available for plant emergency workers during emergencies , including those for hostile action events.(10]

21 . The resources for controlling rad iological exposures for emergency workers are established . (11]

22 . Arrangements are made for medical services for contaminated, injured individuals . (12]

23 . Plans for recovery and reentry are developed . (13) 24 . A drill and exercise program (including radiological, medical, health physics and other program areas) is established. (14) 25 . Drills , exercises , and training evolutions that provide performance opportunities to develop, maintain , and demonstrate key skills are assessed via a formal critique process in order to identify weaknesses . (14]

26 . Identified weaknesses are corrected . (14]

27 . Training is provided to emergency responders . (15]

28. Responsibility for emergency plan development and review is established . (16)
29. Planners responsible for emergency plan development and maintenance are properly trained. (16]

APPLICABILITY CONCLUSION X If no Part V criteria are checked , a 10CFR50.54(q)(3) Evaluation is NOT required; document the basis for conclu sion below and complete Part VI.

.J If any Part V criteria are checked , complete Part VI and perform a 10CFR50.54(q){3) Evaluation .

BASIS FOR CONCLUSION Changing the location of where a HOSTILE ACTION is defined from "OWNER CONTROLLED AREA" to

' SECUR ITY OWNER CONTROLLED AREA" for change numbers 1 and 2 aligns the emergency plan with the NRC-approved GGNS Rev 6 EAL submittal letter GNRO-2018/00048 dated October 10, 2018 . This letter depicts the use of the Security Owner Controlled Area for this application . For change number 3, changing Appendix G J.1.d from

  • owner controlled area" to "EP owner controlled area" more precisely defines the intended location and provides agreement with a previously defined term in the emergency p lan in section 1.22 The proposed changes do not change the intent of the GGNS Emergency Plan A 10 CFR 50.54(Q )( 3) Evaluation is not requ ired . The changes to the GGNS Emergency Plan may be implemented w ithout further review.

, Part VI. Signatures:

Preparer Name (Print) Date :

Dennis M. Coulter ;L.

  • I 7* 2.o (Optional) Reviewer Name (Print) Reviewer Signature Date:

Reviewer Name (Print) Date :

James J . Lewis Nuclear EP Project Manager Approver Name (Print) Date:

Michael L. Lewis Emergency Planning Manager or deslgnee EN-EP-3O5 ROOS

Attachment 2 to GNRO2020/00011 Grand Gulf Nuclear Station Emergency Plan Revision 80

Gran d Gulf Nucl ear Stati on Eme rgen cy Plan Revision 80

  • ~ Entergy CONTROLLED COPY 1

GG Revision 80 FSAR 02 / 2020 GRAND GULF NUCLEAR ST ATION EMERGENCY PLAN RECORD OF REVISION Revision/Change Number Date Entered Entered By Keep this sheet in the front of your copy of the GGNS Emergency Plan as a record of incorporation of periodic revisions and change

GG Revision 80 FSAR 02 / 2020 LIST OF EFFECTIVE PAGES Note: New revisions are intended to be a complete re-issue of the plan and pages will not be changed out individually.

Revision bars are used in this revision only to indicate changes that were not cosmetic in nature.

Section Revision Section Revision i 80 Appendix A 80 ii 80 Appendix B 80 iii 80 Appendix C 80 iv 80 Appendix D 80 V 80 Appendix E 80 vi 80 Appendix F 80 vii 80 AppendixG 80 viii 80 Appendix H 80 ix 80 X 80 xi 80 Section 1 80 Section 2 80 Section 3 80 Section 4 80 Section 5 80 Section 6 80 Section 7 80 Section 8 80 Section 9 80 ii

GG Revision 80 FSAR 02 / 2020 Contents 1 DEFINITIONS ... ...... .............................................. ............................................... ... ... ...................... .... ... . 1-1 2 SCOPE AND APPLICABILITY .................. ................... .. .......................... ..... ......... ....... .................. .... .... .. ... 2-1 2.1 Criterion for Grand Gulf Nuclear Station Emergency Plan Development ... ...... ................. .... ... ..... ... 2-1 2.2 Applicability of the Emergency Plan .. .... .... .. ... ..... ... .. ...... ....... .... ........... .. .. .... .. ........... ... ... ... .. .... ... .... 2-1 2.2.1 General Information and Site Description ....... ................. .. .... .......... .............. ... ....... .......... .. .. . 2-1 2.2.2 Population and Population Distribution ... .. ... .... ............................... ..... ........ ... ................. ...... 2-2 2.2.3 Emergency Planning Zones ............ ...... .................................................. .. ............................... 2-3 2.3 Scope of the Emergency Plan ........................ ...................................... ... .... ..... ............................... 2-4 2.3.1 Regulatory Requirements .............. .... ....... .... ............................ .... ......... .. ............................... 2-4 2.3.2 Objectives of the Emergency Plan .. .. ..... ............. ................. ... ........ ... ..... ...... ..... ................ ... ... 2-4 2.4 Emergency Plan Interrelationships ..... ... ... .............. ...... ..... ....... ........... .. ... .... .. .. ... .... ........... ....... ..... 2-5 2.4.1 Emergency Plan Procedures ........... ... .... ........... .... ... .. ... ... .............. ..... ..... ... ... .. ....... .... ...... .. .... 2-5 2.4.2 Related Plans, Programs and Procedures .......................................... ... .... .. .... ................... ...... 2-5 2.4.3 Participating Governmental Agencies ........................................ .... ......... ......... .... ... ................ 2-6 3

SUMMARY

OF EMERGENCY PLAN ............ ...... ... ....... ............ .... .... ... ....... .. ... ........... ... .. ...... ..................... 3-1 3.1 Emergency Planning ....... ................ ... .... ... .. ........ ... ........................ ........ .... ...... .. .............. ............... 3-1 3.2 Emergency Plan Steps ..... ............ ..... ..... .. .... .. .............. .... .................. ... .... .. ... ........ ........ ....... .. ........ 3-1 3.3 Emergency Direction and Assignments .. .......... ...... ... ..................... .......... .. .... ......... .... .... ................ 3-2 4 EMERGENCY CONDITIONS ................... .. ............. ................................... ... ... ... ..... .. ..... ..... ... .. ........ ......... 4-1 4.1 Emergency Classification System .......... ........... ............. .... .... .............. .......... .. .......... .... ... ..... .......... 4-1 4.1.1 Unusual Event .................... ................. ....... ... ................... .... ...... ... ...... ............. ...... ....... ....... .. 4-2 4.1.2 Alert ...... ............................. ........... ... ..... ................... .... .. .................. .. ..................... .... ........... 4-2 4.1.3 Site Area Emergency ........................ .... ...... .. .. ... ..... ... .. .. ... ..... ..... ........... ... .... ........... ...... ....... ... 4-3 4.1.4 General Emergency ...... .. ..... ..... .... ...... ... ............................ .... ..... .... .... .. ...... .......... ... ..... .......... 4-3 4.2 Classification of Postulated Accidents .. .... .............. ............. ..... ... ...... ..... .... ..... .... ..... ...... .... ............. 4-4 5 ORGANIZATIONAL CONTROL OF EMERGENCIES ... ... ...... .. ... ... .... ......... ... .. .. .... ........ ... ..... ...... .. ................. 5-1 5.1 GGNS Organization ................... .. .................. .. .. ..... ................. ....... ... .... ........ ......... ...... .. ................. 5-1 5.2 Normal Station Organization .... ............ .. .......... ........ ...................... ......... ... ....... ...... ...... ........ ......... 5-1 5.2.1 General Manager, Plant Operations ...... ...... .. .......... .. .... .. .. ... .. ..... .. ... .. ... ...... ....... .......... ..... ...... 5-1 5.2.2 Senior Manager, Operations ... ... .............. .... ... ... ............. ..... .. .. ...... ......... .. .. ....... ..................... 5-1 5.2.3 Senior Manager, Maintenance ...... .... ..... ............................... ....... ... .... ............ ....... ........ ......... 5-2 iii

GG Revision 80 FSAR 02 I 2020 5.2.4 Manager, Radiation Protection ............................................................................................... 5-2 5.2.5 Senior Manager, Production ................................................................................................... 5-2 5.2.6 Manager, Training .................................................................................................................. 5-2 5.2.7 Shift Technical Advisor ............................................................................................................ 5-2 5.2.8 Manager, Supply Chain ........................................................................................................... 5-3 5.2.9 Director, Regulatory & Performance and Improvement.. ........................................................ 5-3 5.3 Normal Station Shift Staffing .......................................................................................................... 5-3 5.4 Emergency Organization ................................................................................................................ 5-3 5.4.1 Normal Station Shift ............................................................................................................... 5-4 5.4.2 EDF Emergency Director {ED) ................................................................................................. 5-4 5.4.3 EDF Manager .......................................................................................................................... 5-4 5.4.4 Radiological Assessment Coordinator {RAC) ............................................................................ 5-5 5.4.5 Technical Advisor {TA) ............................................................................................................ 5-5 5.4.6 Admin. & Logistics Coordinator ............................................................................................... 5-5 5.4.7 Public Information Liaison ...................................................................................................... 5-6 5.4.8 Offsite Communicator ............................................................................................................ 5-6 5.4.9 EDF Communicator ................................................................................................................. 5-6 5.4.10 Lead Offsite Liaison ................................................................................................................ 5-6 5.4.11 Offsite Liaison .................................... .. ................................................................................... 5-6 5.4.12 Dose Assessor ......................................................................................................................... 5-7 5.4.13 Offsite Team Coordinator {OTC) .............................................................................................. 5-7 5.4.14 Offsite Monitoring Team {OMT) .............................................................................................. 5-7 5.4.15 Information Technology {IT) Specialist- EDF ........................................................................... 5-7 5.4.16 EDF Log Keeper ...................................................................................................................... 5-8 5.4.17 Emergency Plant Manager {EPM) ........................................................................................... 5-8 5.4.18 TSC Manager .......................................................................................................................... 5-8 5.4.19 TSC Communicator ................................................................................................................. 5-9 5.4.20 Security Coordinator ............................................................................................................... 5-9 5.4.21 ENS Communicator ................................................................................................................. 5-9 5.4.22 Maintenance Coordinator ....................................................................................................... 5-9 5.4.23 Engineering Coordinator ....................................................................................................... 5-10 5.4.24 Radiological Coordinator ...................................................................................................... 5-10 5.4.25 Operations Coordinator ........................................................................................................ 5-10 iv

GG Revision 80 FSAR 02 / 2020 5.4.26 Engineers {Mechanical/ l&C/ Electrical) ................................................................................ 5-10 5.4.27 Reactor Engineer .................................................................................................................. 5-11 5.4.28 OSC Manager ....................................................................................................................... 5-11 5.4.29 Log Keeper OSC .................................. .. ................................................................................ 5-11 5.4.30 Operations Support ................................ .. ............................................................................ 5-11 5.4.31 Work Control Coordinator ............ .. .. ............ .............................. .. .................... .... .. .... ..... ..... 5-12 5.4.32 Mechanical /I & C /Electrical Coordinator ...................................................... ...... .. .... .. ..... .... 5-12 5.4.33 Rad Chem Coordinator ........................................................................................ .. .... .. .... .. .. . 5-12 5.4.34 Company Spokesperson ........................ ............................... .. .................... .......... .. .... .. ...... .. 5-12 5.4.35 Technical Advisor -JIC ............................................................................................... ............ 5-13 5.4.36 JIC Manager............................................................................................ ...... .. ...................... 5-13 5.4.37 Log Keeper-JIC ................................................................................ .. .. ........ .. ................ .. .... .. 5-13 5.4.38 Inquiry Response Coordinator .................... ............................................ ............ .... ............. . 5-13 5.4.39 Press Release Writer ........................ .. .... .............................................. ...... .. ........ .... .. .. ......... 5-13 5.5 Recovery Organization .................................... ............................................................................. 5-14 5.6 Local Services Support ................................ .. ................................................................................ 5-14 5.6.1 Medical Support ................................................................................................................... 5-14 5.6.2 Fire Support ............... .. ......................................................................................................... 5-15 5.6.3 Law Enforcement Agencies .. ................ .. .......................................... ..................................... 5-16 5.7 Coordination with Governmental Agencies ........................................ .. ........... ........ ..................... 5-16 5.7 .1 Mississippi Emergency Management Agency (MEMA) and Mississippi State Department of Health/Division of Radiological Health (DRH) ...................................................................................... . 5-17 5.7.2 Louisiana Department of Environmental Quality (LDEQ) and Governor's Office of Homeland Security and Emergency Preparedness (GOHSEP) ................................................................................ 5-18

5. 7.3 Port Gibson/Claiborne County Civil Defense ...................................... ................................... 5-19 5.7.4 Tensas Parish Office of Homeland Security and Emergency Preparedness ............................ 5-19
5. 7.5 Nuclear Regulatory Commission (NRC) ............ ..................................................................... 5-20 5.7.6 Department of Energy (DOE) .............. .. ................................................................................ 5-20 5.7.7 Institute of Nuclear Power Operations (INPO) ....................................................................... 5-21 5.7.8 U.S. Coast Guard ................................... ................................................................................ 5-21 5.8 Contractor Assistance .............................................................................. .................................... 5-21 5.9 Support for Federal Response ...................................................................................................... 5-21 6 EMERGENCY MEASURES ........................................ .... ...... ...................... .. ......... ..................................... 6-1 6.1 Initiating Emergency Measures .. ... .. .... ...... ................ .. .. .......... ...... .. ........ ...... ...... .. ............ ............. 6-1 V

GG Revision 80 FSAR 02 / 2020 6.1.1 Emergency Suspension of Normal Quality Assurance Procedures and Administrative Controls.

License Conditions. and Technical Specifications .................................................................................... 6-1 6.1.2 Suspension of Normal Emergency Actions for Security Emergencies ....................................... 6-1 6.2 Activation of Emergency Organization ................................................. .... ....................................... 6-2 6.2.1 Control Room Operators ........................................................................................................ 6-2 6.2.2 Shift Manager ......................................................................................................................... 6-2 6.2.3 Shift Technical Advisor ..................................................................... .... ...... ............................. 6-2 6.2.4 Emergency Director ................................................................................................................ 6-3 6.3 Assessment Actions ........................................ ................................................................................ 6-4 6.3.1 Assessment Actions During Unusual Events ............................................................................ 6-4 6.3.2 Assessment Actions During Alerts ..... ........................................... ........................................... 6-4 6.3.3 Assessment Actions During Site Area Emergencies ................................................................. 6-5 6.3.4 Assessment Actions During General Emergencies ................................................................... 6-5 6.4 Corrective Actions .......................................................................................................................... 6-5 6.5 Protective Actions .......................................................................................................................... 6-5 6.5.1 Protective Cover, Evacuation, Personnel Accountability .......................................................... 6-6 6.6 Contamination Control Measures ...................................................................... ............................. 6-8 6.7 Aid to Affected Personnel. .............................................................................................................. 6-8 6.7.1 Emergency Personnel Exposure .............................................................................................. 6-9 6.7.2 Decontamination and First Aid ............................................................................................. 6-10 6.7.3 Medical Transportation ............................ .......................................... ... ..... .......................... 6-10 6.7.4 Medical Treatment .................................... ........................................................................... 6-11 7 EMERGENCY RESPONSE FACILITIES AND EQUIPMENT ............................................................................ 7-1 7.1 Facilities and Equipment ................................................................................................................ 7-1 7.2 Control Room ................................................................................................................................. 7-1 7.3 Emergency Response Facilities .. .............. .................................... .......... ......................................... 7-1 7.3.1 Technical Support Center {TSC) ............................................................................................... 7-1 7.3.2 Operations Support Center {OSC) ........................................................................................... 7-3 7.3.3 Emergency Operations Facility {EOF) ................................................ ...................................... 7-3 7.3.4 Backup Emergency Operations Facility {BEOF) ................................ .......... ............................. . 7-4 7.3.5 Media Centers ........................................................................................................................ 7-5 7.3.6 Alternate Facilities .................................................................................................................. 7-5 7.4 County and State Emergency Centers ............................................................................................. 7-5 vi

GG Revision 80 FSAR 02 / 2020 7.4.1 Claiborne County Emergency Operations Center .. .............. .. .. .. .. .. .. .. .... ............................ .. .... 7-5 7.4.2 Mississippi State Emergency Operations Center .. .. .. ...... .......... .. ............................................. 7-6 7.4.3 Tensas Parish Emergency Operations Center .. ........ .. .. ........ .. .. .... .. .... .. .................................... 7-6 7.4.4 Louisiana State Emergency Operations Center ............ .. .............. .. .. .... .................................... 7-6 7.5 Communications Systems .................. .. .... .. ............ .... .. ............ .. ........ .. .... .. .. ................................... 7-7 7.5.1 Telephone System ......... ............. .. ...... .... .... .. ...... ................ .. ...... .... .... .. .. ...... .. .................. .. .. .. 7-7 7.5 .2 Plant Paging System & Sound Powered Phones .. ... .. .. .................... ...... ................ ................... 7-7 7.5.3 Emergency Communications Equipment.. .......... .. .............. .... .. .......................... .............. ....... 7-8 7.5.4 Alert Notification System .. .. .. .... ...... ...... .... ...... .. ........................ ............ ................................ 7-10 7.6 Assessment Facilities ...... .................... ...................... .. .................................................................. 7-11 7.6.1 Onsite Systems and Equipment ........ .. .. .......... .. ............. .. ...... ........ .... ................................... 7-11 7.6.2 Offsite Monitoring Equipment and Facilities .. .... ............. .. ................. ..... .. .. ........................ .. 7-17 7.6.3 Radiological Assessment Laboratories .. .............. ...... .............. .. .. .. ...... ...... .. .. .......... .. .... ........ 7-18 7.6.4 Post-Accident Sampling Capability ... ................. .............. .. .. .............. .. .................................. 7-19 7.7 Protective Facilities ............................ .. ................ .............................. .... .... .... ........................ .... .. 7-20 7.8 First Aid and Medical Facilities ..................................................................................................... 7-20 7.9 Rescue and Damage Control Equipment.. ............................................... ...................................... 7-21 7.10 Personal Protective Equipment .......... .......... ...... ...... .............. ............. .................... .................. .. . 7-21 8 MAINTAINING EMERGENCY PREPAREDNESS .......... .. ...... .. ........................ ...... .. ...................................... 8-1 8.1 Organizational Preparedness ....................... ............. ... ... .. .. .. .. .. ............... ... ....... ... .. ........ .. ........ .. .. .. 8-1 8.2 Training ............ ............................ .......... .. ................ ........ .. ........ .......... .... ........ .. .... .. .. .................... 8-1 8.2.1 General Emergency Plan Training .......... .. ............................................. ................... .. .... ... ...... 8-2 8.2.2 Emergency Preparedness Training Specialized and Emergency Plan Procedure Training .. .. .. ... 8-2 8.2.3 Orientation and Training Program for Offsite Support Agencies .. .......... .. .............. ... .......... .. ... 8-3 8.3 Drills and Exercises .. ...... ... ... .. .... ... ............... .. .. .......... ............... .. ... ...... .. .. .... ........ .... .............. ........ . 8-4 8.3 .1 Drill and Exercise Scenarios ......... ........................ .. .................. ............ ........ .. ................ .. .... .. . 8-4 8.3.2 Drill and Exercise Schedule ... ... .... .... ... .. .. ............. .. .......... .. ........................ .. .. ..... ......... .... .... .. . 8-6 8.3 .3 Scenario Variety Documentation . .. .. .... .. ........................................ .. .... .................................. . 8-9 8.4 Responsibilities ................ .. ................ .......... .. ...................................... .......................................... 8-9 8.5 Review and Updating ofthe Emergency Plan and Emergency Plan Procedures ............................. 8-10 8.6 Maintenance and Inventory of Emergency Equipment and Supplies ............................................. 8-11 8.7 Educational Information to the Public .... ................ .............. ......... .................. ............................. 8-11 8.8 News Media Information .. .. ... ..... .. .. ...... .... .. .. .......... ... .. .. ....... ........ .. .. .. .... .. .... .... .. .. ....... ... ....... ....... 8-12 vii

GG Revision 80 FSAR 02 / 2020 9 RECOVERY ............................................................................................................................................. 9-1 9.1 Recovery Operations ...................................................................................................................... 9-2 9.2 Reentry Operations ........................................................................................................................ 9-2 viii

GG Revision 80 FSAR 02 / 2020 LIST OF APPENDICES APPENDIX TITLE Emergency Plan Cross Reference & List of Procedures that A

Implement the Emergency Plan List of Emergency Equipment and Supplies for Emergency 8

Facilities and Hospitals C Reserved D Letters of Agreement E Executive Summary Evacuation Time Estimate Study E-1 F List of Supporting Plans F-1 G NU REG 0654 Cross Reverence News Media Emergency Information Programs for GGNS &

H H-1 Public Education and Information Programs for GGNS ix

GG Revision 80 FSAR 02 / 2020 LIST OF TABLES Table 2-1: Public Facilities and Institutions .................................................................................................... 2-8 Table 2-2: Resident Population Distribution in Evacuation Area by Sector* ................................................... 2-9 Table 2-3: Permanent Resident Population and Vehicles by PAS/PAA ......................................................... 2-10 Table 4-1: Emergency Action Levels .............................................................................................................. 4-5 I Table 4-2: Classification of FSAR Design Bases Accidents ............................................................................. 4-12 Table 5-1: Shift Staffing and Augmentation Capabilities .............................................................................. 5-22 Table 6-1: Protective Actions Guides for the Early Phase of a Nuclear Incident ............................................ 6-12 Table 7-1: GGNS ORO Notification System ................................................................................................... 7-22 X

GG Revision 80 FSAR 02 / 2020 LIST OF FIGURES Figure 2-1 : General Area Surrounding the Grand Gulf Nuclear Station ........................................................... 2-11 Figure 2-2 : Site Layout .. ..... .... ..... ... ....... ....................................................................................................... 2-12 Figure 2-3: Permanent Resident Population Distribution ................................................................................ 2-13 Figure 2-4: Ten-Mile Emergency Planning Zone ... .......... ..... .. .. ....... ... ...... ..................................................... 2-14 Figure 2-5 : Fifty Mile Emergency Planning Zone .. .............. .... ... ........... .... .................................................... 2-15 Figure 5-1 : Figure Deleted .... ... ....... ....... ...... .......................... ..................................................................... 5-24 Figure 5-2: Normal Station Organization ......... ..... ...... ........... ........ ... .. ... ... ................................................... 5-25 Figure 5-3 : Emergency Organization ........ ....... ....... ... ........ ... .. ... ... ... ....... .. ................................................... 5-26 Figure 5-4: Emergency Organization .... ... ... ..... .... ...... ....... .. .. .. .... .. .. ........ .... ................................................. 5-27 Figure 5-5 : Interrelationships of Emergency Response Organization ..... ..... ................................................. 5-28 Figure 5-6 : Federal Response Management Diagram .. .. .... ... ......... ..... .... .. ................................................... 5-29 Figure 6-1: Figure Deleted ... ... ....... ...... ..... ...... .. .. .......... .. .. .......... ........ ... ... .................................................. 6-13 Figure 6-2: Example of the GGNS Emergency Notification Form .......... .. ............. .. .... ................................... 6-14 Figure 7-1: EMERGENCY FACILITIES ...... ........... ... ...................... .......................... .. .. ..................................... 7-23 Figure 7-2: TECHNICAL SUPPORT CENTER .. ... ............................................................ .................................. 7-24 Figure 7-3: OPERATIONS SUPPORT CENTER ......................................... .... .... ........ ....................................... 7-25 Figure 7-4: EMERGENCY OPERATIONS FACILITY LEVEL 1.. ....... .. ......................... .. ......................................... 7-26 Figure 7-5: EMERGENCY OPERATIONS FACILITY LEVEL 11 ................................... ... .... .................................... 7-27 Figure 7-6: EMERGENCY OPERATIONS FACILITY LOCATION .. .. ......... ..... .............. .... ..................................... 7-28 Figure 7-7 : BACKUP EMERGENCY OPERATIONS FACILITY ......... ....... .. .. .. ....... .. ..... .... ... .................................. 7-29 Figure 7-8 : ALTERNATE FACILITIES .... .. .... ... ..... ..... ...... ... ..... ............................ .. .. ......................................... 7-30 Figure 7-9 : JOINT INFORMATION CENTER LAYOUT ... .. .. .. .. .. ........... .. .. .. ... ... .... .... ... .... ................................... 7-31 Figure 7-10: Deleted .. ....... .. .... ...... ....... ........ .... .... .............. .... ........... ..... ... ... .. ........ .. .. ................................. 7-32 Figure 7-11: Deleted .. .. .. ............................................................................................................................. 7-32 Figure 7-12: COMMUNICATION INTERFACES............................................................................................... 7-33 Figure 7-13: SIREN LOCATIONS ................................................................................................................... 7-34 xi

GG Revision 80 FSAR 02 / 2020 1 DEFINITIONS This section provides definitions which include various terms that are unique or given connotations that differ from normally accepted usage. The list below includes terns used throughout this Emergency Plan along with the definitions that are applied to these terms. This section provides definitions which include various terms that are unique or given connotations that differ from normally accepted usage. The list below includes terns used throughout this Emergency Plan along with the definitions that are applied to these terms.

1.1 Accident -An unintentional or unexpected event resulting in radiological exposure or physical injury to individuals and/or physical damage to property.

1.2 Activation -Actions taken to staff and setup an emergency facility for operation. Includes notification of emergency personnel, equipment setup and equipment operability testing.

1.3 Affected Persons - individual(s) who have been radiologically exposed or physically injured as a result of an accident to a degree requiring special attention, e.g., protective actions, decontamination, first aid, or medical services.

1.4 Alarm -An indication of abnormal plant conditions and/or equipment status.

1.5 Alert - An emergency classification in which 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 Environmental Protection Agency (EPA) Protective Action Guideline exposure levels.

1.6 Annual - As used for scheduling purposes, means that the event will be scheduled no tater than 12 months after the previous event's original schedule date. If the event is not completed within 15 months of the previous events original schedule date, it will be considered late. This definition does not apply to ERO Training. ERO Training frequency is described and defined in Training & Qualifications procedure TQ-1I 0.

1. 7 Assessment Action - Those actions taken during or after an accident to obtain and process information that is necessary to make decisions to implement specific emergency measures 1.8 Augmentation -Actions taken to support onshift personnel prior to emergency facilities becoming fully operational.

1 .9 COE-Committed Dose Equivalent 1-1

GG Revision 80 FSAR 02 / 2020 1.10 Control Room - The location at the GGNS from which the reactor and most of its auxiliary systems are normally controlled.

1. 11 Control Room Personnel - Shift Manager, Senior Reactor Operator (SRO), Reactor Operators (RO), Auxiliary Operators, and Shift Technical Advisor (STA).
1. 12 Corrective Actions - Those emergency measures taken to lessen the severity of or terminate an emergency situation at or near the source of the problem in order to prevent or control a release of radioactive material or to minimize the damage to plant equipment, e.g., shutting down equipment, firefighting, repair and damage control.

1.13 County - Claiborne County or Tensas Parish; same as "local."

1.14 Design Basis Accident (DBA) - One of the most important parts of the site criteria is the requirement to identify the worst case accident based on detailed analysis of hypothesized accidents. As part of the Final Safety Analysis Report (FSAR), the licensee is required to assume a fission product release from the core based upon a major accident, hypothesized for purposes of site analysis, or postulated from considerations of possible accident hazards not exceeded by those from any accident considered credible.

1.15 Decontamination - The removal of surface radioactive material from individuals, equipment, surfaces, food stuffs, etc.

1.1 6 Emergency -A sudden, urgent, usually unforeseen occurrence or occasion requiring immediate action. It may result from accidental causes, natural causes, or malicious man-made actions. There are four classes of emergencies considered: Unusual Event, Alert, Site Area Emergency, and General Emergency 1.17 Emergency Action Levels (EAL)- One of a set of names or titles established by the US Nuclear Regulatory Commission (NRC) for grouping off-normal events or conditions according to (1) potential or actual effects or consequences, and (2) resulting onsite and offsite response actions. The emergency classification levels, in ascending order of severity, are:

  • Unusual Event (UE)
  • Alert
  • Site Area Emergency (SAE)
  • General Emergency (GE) 1.18 Emergency Director - An individua l designated onsite having the authority and responsibility to initiate the Emergency Plan and coordinate efforts to reduce the consequences of the event und bring it under control (Equivalent to the position of Emergency Coordinator referenced in NU REG 0654 Rev. 1). The Shift Manager will assume this responsibility at the declaration of an Emergency.

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GG Revision 80 FSAR 02 / 2020 1.19 Emergency Operations Facility (EOF) - A near-site emergency center from which the offsite emergency support activities are controlled.

1.20 Emergency Plan Procedures - Procedures providing the means to implement the Emergency Plan.

1.21 Emergency Planning Zone (EPZ) -Areas designated for which planning is provided to assure that prompt and effective action is initiated to protect the public in the event of an emergency.

1.22 Emergency Preparedness Owner Controlled Area (EPOCA) - The area at the site which is owned and controlled by the station for which the station has the responsibility to evacuate except for any defied areas covered by agreements with State or other governmental agencies.

1.23 Emergency Plant Manager- An individual designated the responsibility for accident mitigation at the plant.

1.24 EOF Emergency Director - An individual designated the responsibility for the total emergency response effort and is the central figure for the emergency organization. The EOF Emergency Director relieves the Shift Manager of the Emergency Director responsibilities at which time the Shift Manager resumes Control Room duties.

1.25 Exclusion Area - The area surrounding the plant owned by the reactor licensee in which he has the authority to detemline all activities including exclusion or removal of persons and property from the area during accident conditions.

1.26 Fitness for Duty (FFD) - A company policy implementing requirements under 10CFR26 that provides reasonable assurance that employees and other individuals directly associated with GGNS facilities will perform their tasks in a reliable and trustworthy manner. This is accomplished in part by assuring they are not under influence of any substance, legal or illegal, or mentally or physically impaired from any cause. which in any way adversely affects their ability to safely and competently perform their duties. This policy provides measures for early detection of persons who are not fit to perform their assigned duties.

1.27 General Emergency-An emergency classification in which 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.

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GG Revision 80 FSAR 02 / 2020 1.28 Hostile Action -An act toward GGNS or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidate the licensee to achieve an end.

This includes attack by air, land, or water using guns, explosives, PROJECTILES, vehicles, or other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included. Hostile action should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on GGNS. Non-terrorism-based EALs should be used to address such activities (i.e., this may include violent acts between individuals in the SECURITY OWNER CONTROLLED AREA).

1.29 Hostile Force - One or more individuals who are engaged in a determined assault, overtly or by stealth and deception, equipped with suitable weapons capable of killing, maiming, or causing destructions.

1.30 Ingestion Exposure Pathway - An area with a radius of about 50 miles from the reactor site. Predetermined protective action plans are in place for this EPZ and are designed to avoid or reduce dose from potential ingestion of radioactive materials. These actions include a ban of contaminated food and water.

1.31 Joint Information Center (JIC) - An area designated outside the protected area that provides a location for the media so that communication and information can be disseminated concerning plant conditions and emergency operations.

1.32 Low Population Zone (LPZ) - As defined in 10CFRl00.3, the area immediately surrounding the exclusion area which contains residents, the total number and density are such that appropriate protective measures could be taken in their behalf in the event of a serious accident. The low population zone for the Grand Gulf Site is the area within a 2-mile radius from the plant.

1.33 Monitor and Prepare* A type of precautionary action intended to advise the public within the EPZ that a serious emergency at the nuclear power plant exists and that it should monitor the situation and prepare for the possibility of evacuation, Shelter In Place (SIP),

or other protective actions.

1.34 Non-Essential Personnel - Employees not having emergency assignments (ERO), visitors, contractors/construction personnel, and members of the public who may be in public access areas within the Exclusion Area or Emergency Preparedness Owner Controlled Area. Non-essential personnel and non-emergency personnel are equivalent and used interchangeably.

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GG Revision 80 FSAR 02 / 2020 1 .35 Offsite - As used for accountability purposes, any area outside the GGNS protected area.

As used for plume tracking survey purposes, all areas beyond the site boundary.

1.36 Onsite -As used for accountability purposes, the area within the GGNS protected area. As used for plume tracking survey purposes, all areas external to the power block, out to and including the site boundary.

1.37 Operational - Status of an emergency facility declared by the appropriate facility manager upon determining that the facility is adequately staffed, and equipment is setup and available to assume perform the emergency functions assigned to that facility.

1.38 Operations Support Center (OSC) - location from which onsite non-control room activities are staged and implemented.

1.39 Pathway - Method by which radiological exposure is received .

1.40 Plan - The Grand Gulf Nuclear Station Emergency Plan.

1.41 Plume Exposure Pathway - The process by which a person receives exposure from direct interaction with the products of a radiological release. This includes receiving direct gamma radiation from sources external to the body, both instantaneous and short term due to being in the presence of the products of the release. It also includes direct gamma, beta, and alpha radiation from sources inside the body due to inhalation.

1.42 Plume Tracking Survey - Onsite or offsite surveys performed to support offsite dose assessments which are ultimately used to provide state and local agencies with Protective Action Recommendations.

1.43 Population-at-Risk - Those persons for whom protective actions are being or would be taken upon implementation of the plan.

1.44 Population Center- A densely populated area with 25,000 or more inhabitants.

1.45 Protective Actions -Those emergency measures taken, either in anticipation or after a release of radioactive material has occurred, for the purpose of preventing or minimizing radiological exposure to individuals.

1.46 Protective Action Guides (PAGs) - Guidelines for protective action recommendations to state and local agencies based on predetermined projected radiological dose or dose commitment values to individuals in the general population that warrant protective action in anticipation of or following a release of radioactive material.

1.47 Protected Area* As defined in 10CFR73.2, an area encompassed by physical barriers to which access is controlled for security purposes.

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GG Revision 80 FSAR 02 / 2020 1.48 Rapidly Progressing Severe Accident -A significant reactor event with immediate or near-immediate offsite consequences that is intended by the regulator to be easily recognizable. If the decision maker is not sure whether or not such an event is occurring, then they should assume that a rapidly progressing severe accident is not in progress.

1 .49 Recovery Action - Those actions taken after the emergency to restore the plant as nearly as possible to pre-emergency conditions.

1.50 Restricted Area -As defined in 10CFR20. 1003, any area to which access is controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive material.

1.51 Security Owner Controlled Area - SOCA. The Security area between the OCA detection fence and the protected area boundary.

1.52 SDE - Shallow Dose Equivalent 1.53 Shift Manager - The senior management representative in charge of overall plant operations during each shift.

1. 54 Site Area Emergency -An emergency classification in which events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public or Hostile Action that result in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to likely failure of or, (2) prevents 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.

1.55 State - The State of Mississippi or Louisiana.

1.56 Station-The Grand Gulf Nuclear Station .

1 .57 Technical Support Center {TSC) - An area which accommodates personnel acting in support of the command and control functions but separate* from the control room.

These personnel under the guidance of the Emergency Plant Manager, supply in-depth diagnostic and corrective engineering and radiological assistance to the plant operations staff.

1 .58 TEDE - Total Effective Dose Equivalent 1-6

GG Revision 80 FSAR 02 / 2020 1.59 Unrestricted Area -As defined in 10CFR20.1003, any area to which access is not controlled by the licensee for the purpose of protection of individuals from exposure to radioactive materials.

1.60 Unusual Event - Events are in progress or have occurred which indicate a potential degradation in 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.

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GG Revision 80 FSAR 02 / 2020 2 SCOPE AND APPLICABILITY 2.1 Criterion for Grand Gulf Nuclear Station Emergency Plan Development The Grand Gulf Nuclear Station Emergency Plan (the Plan) has been developed in accordance with NUREG -0654/FEMA*REP-1, Rev. 1, 11 Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants." The format parallels the guidance given in NRC Regulatory Guide 1.101, "Emergency Planning for Nuclear Plants;" Revision 1, dated March, 1977.

2.2 Applicability of the Emergency Plan 2.2.1 General Information and Site Description The Grand Gulf Nuclear Station is a nuclear power plant operated by Entergy Operations, Inc. An area map showing the geographical location of the facility is provided in Figure 2-1.

The design of the Grand Gulf Nuclear Station is that of a boiling water nuclear steam.

supply system supplied by the General Electric Company. A diagram identifying the station facilities is provided in Figure 2*2.

The plant is located in Claiborne County, Mississippi. The site is on the east bank of the Mississippi River, approximately 25 miles south, southwest of Vicksburg and 37 miles north-northeast of Natchez. The Grand Gulf Military Park borders a portion of the north side of the property, and the small community of Grand Gulf is approximately 1-1/2 miles to the north. The town of Port Gibson is about 6 miles southeast of the site.

Two lakes, Gin Lake and Hamilton Lake, are located in the western portion of the site.

These lakes were once the channel of the Mississippi River and average about eight to ten feet in depth.

The site and its environs consist primarily of woodlands divided between two physiographic regions. The western half of the site is in the alluvial plain of the Mississippi River; the eastern half is in the Loess or Bluff Hills. The elevation of the site varies between. 60 and 80 feet above mean sea level in the alluvial plain region, while the Loess Hills portion varies from 80 to more than 200 feet above mean sea level (MSL).

The plant site property boundary encompasses approximately 2100 acres of property that makes up the Grand Gulf Nuclear Station (GGNS) plant site. System Energy 2-1

GG Revision 80 FSAR 02 / 2020 Resources, Inc. (SERI), South Mississippi Electric Power Association {SM EPA), and Entergy -Mississippi own the plant site property as noted in Section 2.1.1.2 of the GGNS FSAR.

There are no unrelated industrial, commercial, institutional or residential structures, with the exception of a Branch Office for Riverland Credit Union, located within the site boundary. Riverland Credit Union Branch Office is located in the Site Processing Facility which is inside the exclusion area.

The boundary lines of the plant exclusion area consist of semicircles drawn from the center of each containment joined by tangent straight lines. The minimum distance from each reactor to the exclusion area is 696 meters. This is the closest distance from the center of Unit 1 containment to the plant property line.

There are no railroads or waterways that traverse the site. One county road runs through the site; Bald Hill Road traverses the exclusion area and cuts through the south-southeast, south, south-southwest, and southwest sectors.

The site area is accessible by two major highways. U.S. Highway 61 and State Highway 18 connect Port Gibson (6 miles southeast of the site) with Natchez, Jackson and Vicksburg.

There are no military installations located near the site urea und no known missile sites in either Mississippi or Louisiana. The nearest military facility is England Air Force Base in Alexandria, Louisiana, about 100 miles to the southwest.

The Independent Spent fuel Storage Installation (ISFSI) is located within the protected area boundary for interim dry storage of spent fuel. The HOLTEC spent fuel storage casks are designed to ensure protection of public health and safety through the use of physical barriers to guard against the uncontrolled release of radioactivity and through the use of shielding to minimize radiation dose to the public from both normal and off

-normal conditions of operation. The analysis summarized in the HOL TEC Cask FSAR demonstrate that under assumed accident conditions, the consequences of accidents challenging the integrity of the barriers will not exceed limits established in 10 CFR 72.106.

2.2.2 Population and Population Distribution The individuals residing in the LPZ are distributed such that appropriate measures could be taken in their behalf in the event of a serious accident.

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GG Revision 80 FSAR 02 / 2020 Figure 2-3 illustrates the LPZ and indicates population distribution within a 10-mile radius of the site. Table 2-1 lists the facilities and institutions within approximately ten miles of the GGNS which may requ ire special consideration in preparing emergency plans.

Seasonal and peak daily transient population within the LPZ is mainly due to recreational use of the Grand Gulf Military Park, hunting and sport fishing.

The closest population center is Vicksburg, Mississippi, located approximately 25 miles north-northeast of the site, with a 2010 population of 23,856. The nearest major city is Jackson, Mississippi. Jackson is located about 55 miles east-northeast of the site and has a population of 173,514 according to a 2010 population survey. Table 2-2 shows the resident population distribution in evacuation area by sector.

2.2.3 Emergency Planning Zones In defining the Emergency Planning Zones (EPZs), Grand Gulf Nuclear Station has taken into consideration such things as organizational capabilities, method of implementation for various emergency plans and the availability of onsite and offsite emergency facilities and equipment. EPZs are designated areas for which planning is recommended to assure that prompt and effective actions are taken to protect the public in the event of an emergency.

Two primary zones have been identified for the purpose of development and implementation of emergency planning. The first Emergency Planning Zone has a 10-mile radius. This EPZ is established in response to the possible direct exposure to the plume. Within this zone, shelter, evacuation and consideration of prophylactic use of potassium iodide are the protective actions recommended for the general public, as necessary. The principal concern in the 10 mile EPZ is the plume exposure pathway.

The counties within the 10 mile EPZ are Claiborne County and Warren County, in Mississippi, and Tensas Parish in Louisiana (refer to figure 2-4). Beyond a ten mile radius the effect of direct exposure to the plume is no longer of significant concern because the plume is sufficiently dispersed so as not to present an immediate hazard.

The second EPZ has a fifty mile radius. This EPZ is established in response to possible exposure to deposited radionuclides, whether in water or on the ground or vegetation. The principal concern in the 50 mile EPZ is the ingestion exposure pathway. This may necessitate monitoring of such pathways as crops, dairy cows, farm animals, and pastures. Those counties in Mississippi within the SO-mile EPZ include Issaquena, Sharkey, Yazoo, Warren, Madison, Hinds, Rankin, Copiah, Simpson, Lincoln, 2-3

GG Revision 80 FSAR 02 I 2020 Amite, Franklin, Adams, Jefferson, Wilkinson, and Claiborne. Those parishes in Louisiana within the SO-mile EPZ include East and West Carol, Richland, Madison, Tensas, Catahoula, Concordia, Franklin, and Caldwell (refer to Figure 2-5). Figure 2-4 is a detailed 10-mile sector map.

2.3 Scope of the Emergency Plan The principles of effective emergency preparedness incorporate not only the emergency response for systems but also include response for people. Engineered safety systems at the Station are designed to ensure that the consequences of a major malfunction are to be mitigated prior to any adverse effect on the general public or the Station. The basis for emergency planning is to provide human emergency response in much the same way as safety systems do for the physical plant.

2.3.1 Regulatory Requirements 10CFRS0, "Licensing of Production and Utilization Facilities," requires that each application for a license to operate a facility include in a Final Safety Analysis Report (FSAR), along with other information, the applicant's plans for coping with emergencies, including the items specified in 10CFRS0.34, 10CFRS0.47, and 10CFR Part 50, Appendix E. 10CFRl00.3 "Reactor Site Criteria," in the definition of Exclusion Area and Low Population Zone, establishes additional criteria for plans to cope with emergencies and serious accidents. Specific requirements of the Nuclear Regulatory Commission are detailed in NUREG 0654/FEMA-REP-l, Rev. 1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants."

2.3.2 Objectives of the Emergency Plan The objectives of the Emergency Plan are:

a. Enable classification of the emergency
b. Assign responsibilities
c. Provide for assessment of onsite and offsite radiological. conditions during and/or following an emergency.
d. Outline the most effective course of action required to safeguard the public and plant personnel in the event of an emergency.
e. Recommend implementation of any protective actions deemed appropriate.
f. Enable mitigation of the radiological. consequences of an emergency both onsite and offsite.

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GG Revision 80 FSAR 02 / 2020 2.4 Emergency Plan Interrelationships The Plan is designed to be compatible with radiological incident plans developed by local, state and Federal agencies through establishment of communication channels with these agencies, and by setting criteria for the notification of such authorities.

The Plan should not, in itself, be considered the sole working document to be used during an emergency. The purpose of the Plan is to classify emergencies according to their severity, to assign responsibilities for actions, and to establish the lines of authority and communication so that the most effective course of action can be developed to safeguard the public and plant personnel in the event of an emergency. Detailed instructions and guidelines for emergency actions are included in various emergency procedures. The principal emergency facilities that the major groups function from, are shown in Figure 7-1. including general locations from GGNS.

2.4.1 Emergency Plan Procedures Detailed procedures required to implement the Plan have been developed. Emergency Plan Procedures (EPPs), which direct the actions of emergency organization, are safety related and located in Volume 10 of the GGNS Plant Operating Procedures Manual.

An index of these procedures is included in Appendix A. Detailed implementing procedures for emergencies considered to be special events, such as civil disturbances, bomb threats, and breaches in security are included as part of the GGNS Physical Security Plan. Separate emergency procedures are not provided for activities already covered by plant or section operating procedures (i.e., calibration of survey instruments). The Plan incorporates certain aspects of the plant's operating procedures, radiation protection procedures, fire procedures and security procedures, where they are required for clarification.

2.4.2 Related Plans, Programs and Procedures Several plans, programs and procedures have been developed to assure the safe operation of the Station. The Plan and Emergency Plan Procedures have been written to coordinate with these other plans, programs and procedures. During emergency situations, the coordination and utilization of all plans and procedures is essential.

The Security Plan and procedures have been coordinated with the Plan and Emergency Plan Procedures to minimize the consequences of an emergency situation.

Security Procedures contain an explanation of the duties and responsibilities for security personnel in the event of an emergency.

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GG Revision 80 FSAR 02 / 2020 Provisions for radiological control at the Station have been covered in Administrative and Radiation Protection Procedures. These Procedures establish controls and protective measures to be placed on work being conducted within the Restricted Area.

A number of emergency operating procedures have been developed to control plant operation during emergency situations. These emergency operating procedures work in conjunction with the Emergency Plan Procedures and are safety related procedures.

A site fire plan for the control of fires has also been developed and procedurally implemented to assure the safe operation of the station. Fire Plan procedures are referenced in the Emergency Plan Procedures.

2.4.3 Participating Governmental Agencies Participating governmental agencies whose plans are interrelated with this plan for action include the following:

a. Mississippi Emergency Management Agency (MEMA)

Charged with direct responsibility for the planning and coordination of the activities of State and local government agencies in the event of a radiological emergency.

b. Mississippi State Department of Health (MSDH)

Has overall responsibility to protect the public health and safety of the general populace from the hazards of radiation. The Division of Radiological Health (DRH) is that division within the MSDH which is assigned the specific responsibility with regard to the hazards of radiation.

c. Louisiana Department of Environmental Quality (LDEQ)

Has overall responsibility for planning as well as the lead technical response role in the event of a radiological emergency.

d. Governor's Office of Homeland Security and Emergency Preparedness (GQHSEP)

Has responsibility for coordination of state agencies as well as logistical and resource support lo local governments in the event of a radiological emergency.

e. Department of Energy (DOE)

The DOE, a Federal agency, provides radiological monitoring assistance. There are trained personnel on staff to provide additional expertise onsite/offsite during a radiological accident.

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GG Revision 80 FSAR 02 / 2020

f. Nuclear Regulatory Commission (NRC)

The role of the NRC during a radiological emergency is that of verifying that emergency plans and procedures have been implemented, assuring that the public health and safety are protected , and conducting investigative activities associated with the incident. The NRC assists in the coordination of Federal response resources and provide to the licensee. state, and local agencies advisory assistance associated with assessing and mitigating hazards to the public. The NRC's actions are governed by NUREG-728. "NRC Incident Response Plan" and NUREG-0845, "Agency Procedures for the NRC Incident Response Plan."

g. County and Parish Emergency Services Claiborne County in Mississippi and Tensas Parish in Louisiana are the local governmental jurisdictions within the 10 mile radius of the Grand Gulf Nuclear Station . They have developed plans to be implemented in the event of a radiological emergency. Claiborne County Civil Defense and Tensas Parish Office of Homeland Security and Emergency Preparedness have communication centers which serve as the means for notifying various support services (fire and rescue, transportation, law enforcement).

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GG Revision 80 FSAR 02 / 2020 Table 2-1: Public Facilities and Institutions Facility Distance from Reactor Direction Centerline (mi.)

Port Gibson Middle School 5.1 SE Port Gibson High School 6.5 ESE Watson Elementary School 4.1 SE Richardson (MAP) Headstart 4.5 SE Chamberlain-Hunt Academy 5.5 SE Claiborne Education Foundation 5.3 SE Alcorn State University 10.5 SSW Patient's Choice Medical Center 5.5 SE Claiborne County Health Center 4.9 SE Claiborne County Courthouse 4.7 SE Grand Gulf Military Park 1.5 N Lake Bruin State Park 9.5 WSW Port Gibson City Hall 5.2 SE 2-8

GG Revision 80 FSAR 02 / 2020 Table 2-2: Resident Population Distribution in Evacuation Area by Sector*

Sector 0-1 1-2 2-3 3-4 4-5 5-10 10-15 Total A 0 11 0 0 0 0 0 11 B 0 0 0 0 0 0 325 325 C 0 7 0 0 24 101 422 554 D 0 1 0 35 94 125 74 329 E 0 0 0 9 17 111 247 384 F 0 5 0 0 417 821 547 1790 G 0 0 0 8 573 1992 655 3228 H 0 0 4 40 0 577 755 1376 J 0 0 0 4 0 38 426 468 K 0 0 2 0 0 2765 95 2862 L 0 0 4 0 0 74 92 170 M 0 0 0 0 0 1520 4 1524 N 0 0 0 0 0 310 7 317 p 0 0 0 0 0 1210 106 13116 Q 0 0 0 0 0 68 0 68 R 0 0 0 0 0 0 0 0

  • Cente rline of Sector in Degrees True North 22 1/2 0 from Facility Sector 0&360 A 22 1/2 B 45 C 67 1/2 D 90 E 112 1/2 F 135 G 157 1/2 H 180 J 202 1/2 K 225 L 2471/2 M 270 N 292 1/2 p 315 Q 337 1/2 R NOTES: 1. The letters I and O have been omitted from sector designators so as to eliminate possible confusion between letters and numbers
2. Source of data: 2012 Grand Gulf Evacuation Time Estimate Study, pages 3-6 & 3-8 2-9

GG Revision 80 FSAR 02 / 2020 Table 2-3: Permanent Resident Population and Vehicles by PAS/PAA PAS/PAA 2010 Population 2010 Resident Vehicles 1 43 24 2A 305 166 2B 151 83 3A 961 519 3B 388 209 4A 2,407 1,298 4B 453 248 SA 138 75 SB 356 193 6 2,629 1,686 7 28 15 8 126 71 9 1,185 642 10 394 214 11 1,403 755 12 TOTAL 10,967 6,198 2-10

GG Revision 80 FSAR 02 / 2020 Figure 2-1: General Area Surroun ding the Grand Gulf Nuclear Station GG FSAR

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GG Revision 80 FSAR 02 / 2020 Figure 2-2: Site Layout c:::; 1 En8gj Saw:es Cmer 2 lki2WillmJSe 3 C31s!nm aiklir,;i 4~

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GG Revision 80 Figure 2-4: Ten-Mile Emergency Planning Zone LEGEND EMERGENCY PLANNING N ZONE BOUNQII.RY PROTECTIVE ACTION

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GG Revision 80 FSAR 02 / 2020 3

SUMMARY

OF EMERGENCY PLAN 3.1 Emergency Planning In accordance with the requirements of 10CFRS0.47 and Appendix E to 10CFRS0 and supplemented by the guidance issued by the Nuclear Regulatory Commission in NUREG-0654 and other documents, the Plan and its associated Emergency Plan Procedures have been established to cope with the various types of emergencies in an orderly and effective manner.

Grand Gulf Nuclear Station maintains the capability to assess, classify, and declare an emergency condition within 15 minutes after the availability of indications to plant operators that an emergency action level has been exceeded and shall promptly declare the emergency condition as soon as possible following identification of the appropriate emergency classification level.

The Plan shall be implemented by the appropriate procedures in Appendix A whenever a real or potential plant emergency is identified that meets the Emergency Action Level criteria described in Section 4.0. The details of the Emergency Plan Procedures are not included herein, but the information contained within the Plan includes a description of procedures to an extent sufficient to demonstrate that the Plan provides assurance that appropriate actions can be taken by the Station and support agencies to protect Station personnel and the general public during emergencies.

The Plan establishes the concepts, evaluation and assessment criteria, and protective actions that are necessary to mitigate the consequences of any of the four classes of emergencies.

The Plan also provides the necessary pre-arrangements, directions, and organizations so that all Station emergencies can be effectively resolved in order to safeguard Station personnel, property, and the general public.

3.2 Emergency Plan Steps In general, the Plan encompasses the following:

a. Detection of the emergency
b. Classification of the emergency
c. Activation of the responding organization(s)
d. Assessment of the event
e. Initiation of corrective actions
f. Recommend initiation of protective actions
g. Aid to affected persons
h. Recovery 3-1

GG Revision 80 FSAR 02 / 2020 3.3 Emergency Direction and Assignments At the onset of all station emergencies, the Shift Manager shall assume the position of Emergency Director and is responsible for initiating the immediate actions required to safeguard the public, onsite personnel and equipment. Utilizing the Emergency Plan Procedures, he orders the activation of the necessary portions of the Emergency Organization.

Upon notification of an Unusual Event from the Shift Manager, the EOF Emergency Director may report to the plant and assume the position of Emergency Director as deemed necessary.

Upon notification of an Alert or higher emergency classification, the EOF Emergency Director reports to the site and assumes the position of Emergency Director from the Shift Manager.

The Shift Manager will resume control room duties upon relief by the augmenting EOF Emergency Director when the EOF is declared operational. Section 5.0 describes, in detail, the assignments and duties of key Emergency Organization Personnel.

The criteria which are to be considered for the safe operation of the plant and/or for actions during an emergency are summarized below:

a. Protection of plant personnel and the general public has the highest priority. Plant system and equipment protection is secondary.
b. Whenever there is doubt as to the classification of the emergency condition, the more conservative case shall be considered.
c. Operators are to believe and respond conservatively to all alarms. Alarms and instrumentation are only to be considered erroneous if proven so by 2 independent indications.
d. Alarms shall be promptly acknowledged, and the required response action taken.
e. Indications of situations and actions taken are to be made a matter of record.

Notifications to personnel and/or offsite agencies ate also to be made a matter of record .

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GG Revision 80 FSAR 02 / 2020 4 EMERGENCY CONDITIONS 4.1 Emergency Classification System There are four classes of emergency conditions used in emergency planning. These four classes cover the entire spectrum of possible emergency situations. from minor local incidents to hypothetical major radiological emergencies, and allow for classification of an accident, notification of the appropriate offsite agencies and support groups, and the activation of emergency organizatlons. The system also provides for the notification and implementation of actions immediately applicable to a specific condition, and for upgrading the response to the appropriate level of classification in the event of a change in the severity of the condition. These actions are further described in Section 6.0.

Emergency Action Levels (EALs} are used to provide indication that an initiating condition exists. These levels are composed of a combination of plant parameters (such as instrument readings and system status) that can be used to give relatively quick indication to the Station operating staff of the severity of the accident situation. The purpose of the EALs is to provide the earliest possible indication of actual or potential accident situations. In most cases further assessment action is conducted both onsite and offsite before actual protective actions are initiated. EALs associated with radiological releases are related to the Environmental Protection Agency's Protective Action Guides (PAGs) summarized in EPA 400-R-92-001 "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents." A determination by the station emergency organization, along with state and local support agencies, of the potential of reaching or exceeding the PAGs is performed in accordance with dose assessment procedures in the event of a radiological release to the environment.

A summary of the ICs discussed in this section are found in Table 4-1. The EALs, wallcharts and basis are maintained in procedure 10-S-01-1. The EALs were developed from guidance in NEI 99-01, Revision 6 "Methodology for Development of Emergency Action Levels" and from accidents analyzed in the GGNS final Safety Analysis Report. When EALs are observed in conjunction with plant or equipment status due to planned maintenance or testing activities.

an emergency condition may or may not exist and the situation must be evaluated on a case by case basis.

The four emergency classes that comprise the emergency classification system are:

a. Unusual Event
b. Alert
c. Site Area Emergency
d. General Emergency 4-1

GG Revision 80 FSAR 02 / 2020 4.1.1 Unusual Event The Unusual Event classification is an emergency in which events are in process or have occurred which ind icate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated. No release of radioactive material requiring offsite response or monitoring arc expected unless further degradation of safety systems occurs.

The EALs Table 4-1, while comprehensive. are not meant to be all inclusive. The Emergency Director may declare an Unusual Event based on other plant conditions and the potential for the degradation of these conditions.

Training of the Emergency Organization members should emphasize the need to evaluate the potential for more serious plant conditions to occur at a future time.

4.1.2 Alert The Alert classification is an emergency classification in which 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. Because of the increased potential for more serious offsite consequences. the emergency organization is activated, as well as notification of key offsite authorities and the news media. The Alert classification also addresses limited releases of radioactive material and therefore might require some radiological monitoring and assessment actions by the emergency organizations.

The Alert class assures that emergency personnel are readily available to respond to a change in plant conditions and to provide assessment support as requ ired .

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GG Revision 80 FSAR 02 I 2020 4.1.3 Site Area Emergency Site Area Emergency is an emergency classification in which events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public or Hostile Action that result in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to likely failure of or; (2) prevent effective access to equipment needed for the protection of the public.

Immediate protective actions are not required upon notification of a Site Area Emergency condition; however, preliminary steps are initiated in anticipation of possible protective actions. These preliminary steps include complete activation of the emergency organization, alerting and/or mobilizing of monitoring teams, and notification of all offsite authorities and the news media. The Site Area Emergency class includes accidents which have a significant potential for the release of radioactive material.

Unlike the two previously described classes of emergencies, the Site Area Emergency is very likely to involve some radiation exposure to the near-site public. Also, many of the accidents included in this class have the potential for escalation to the General Emergency class.

4.1.4 General Emergency The most severe emergency class used in emergency planning is the General Emergency.

General Emergency is an emergency classification in which 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 PAG exposure levels for more than the immediate site area.

Protective actions shall be recommended upon declaration of the General Emergency, as the accidents considered could result in the exceeding of the lower limits of the PAGs. The General Emergency EALs that require dose projections offsite use actual meteorology rather than the adverse meteorology assumptions used in the Site Area Emergency action levels.

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GG Revision 80 FSAR 02 / 2020 None of the accidents analyzed in the FSAR would normally be classified as a General Emergency. However. the Loss of Coolant Accident (LOCA) within the reactor coolant pressure boundary analyzed in the FSAR could lead to a General Emergency classification in a situation where there was a subsequent loss of plant safety systems leading to a possible core melt and fai lure of containment. Criteria to be used for declaration of a General Emergency includes core and containment status as well as actual radiation release data.

4.2 Classification of Postulated Accidents A thorough analysis of each of the postulated accidents is included in the Grand Gulf Nuclear Station Final Safety Analysis Report (FSAR). All of the postulated accidents could be classified into one of the four emergency classes (See Table 4-2). In classifying each of the postulated accidents. the conservative assumptions used in the FSAR analysis were considered. It is possible that occurrence of some of the postulated accidents results in a classification lower in severity.

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GG Revision 80 FSAR 02 / 2020 Table 4-1: Summary of Initiating Conditions r

fateH~ A.-A~nor-mal RaEl@ti~r::i !,,.e_~els/RadiolQ~if:~1 IMfluents I

The Initiating Conditions within this category are as follows:

General Emergency Site Area Emergency Alert Unusual Event Release of gaseous radioactivity Release of gaseous radioactivity Release of gaseous or liquid Release of gaseous or liquid resulting in offsite dose greater resulting in offsite dose greater radioactivity resulting in offsite radioactivity greater than 2 than 1,000 mrem TEDE or 5,000 than 100 mrem TEDE or 500 dose greater than 10 mrem times the ODCM limits for 60 mrem thyroid CDE mrem thyroid CDE TEDE or 50 mrem thyroid CDE minutes or longer Spent fuel pool level cannot be Spent fuel pool level at the top Significant lowering of water UNPLANNED loss of water level restored to at least the top of of the fuel racks level above, or damage to, above irradiated fuel the fuel racks for 60 minutes or irradiated fuel longer Radiation levels that IMPEDE access to equipment necessary N/A N/A N/A for normal plant operations, cooldown or shutdown 4-5

GG Revision 80 FSAR 02 / 2020 Table 4-1: Summary of Initiating Conditions Categorv C - Cold Shutdown/Refueling The Initiating Conditions within this category are as follows :

General Emergency Site Area Emergency Alert Unusual Event Loss of RPV inventory Loss of RPV inventory Significant Loss of RPV UNPLANNED loss of RPV inventory affecting fuel clad integrity affecting core decay heat inventory with Containment challenged removal capability Loss of all offsite and all Loss of all but one AC power source to N/A N/A onsite AC power to ESF buses ESF buses for 15 minutes or longer for 15 minutes or longer Inability to mainta in plant in N/A N/A UNPLANNED rise in RCS temperature cold shutdown Loss of Vital DC power for 15 minutes N/A N/A N/A or longer Loss of all onsite or offsite N/A N/A N/A communications capabilities Hazardous event affecting N/A N/A SAFETY SYSTEMS needed for N/A the current operating mode 4-6

GG Revision 80 FSAR 02 / 2020 Table 4-1: Summary of Initiating Conditions Catego!'.:X E- ISFSI The Initiating Conditions within this category are as follows :

General Emergency Site Area Emergency Alert Unusual Event Damage to a loaded cask N/A N/A N/A CONFINEMENT BOUNDARY The Initiating Conditions within this category are as follows :

General Emergency Site Area Emergency Alert Unusual Event Loss of any two barriers and loss Any loss or any potential Loss or potential loss of any two or loss of either Fuel Clad or N/A barriers potential loss of third barrier RCS 4-7

GG Revision 80 FSAR 02 / 2020 Table 4-1: Summary of Initiating Conditions Categorv H - Hazards The Initiating Conditions within this category are as follows :

General Emergency Site Area Emergency Alert Unusual Event HOSTILE ACTION within the SECURITY OWNER HOSTILE ACTION within the Confirmed SECURITY CONDITION or N/A CONTROLLED AREA or PROTECTED AREA threat airborne attack threat within 30 minutes Seismic event greater than QBE N/A N/A N/A levels N/A N/A N/A Hazardous event FIRE potentially degrading the level N/A N/A N/A of safety of the plant Gaseous release IMPEDING access to equipment N/A N/A necessary for normal plant N/A operations, cooldown or shutdown Inability to control a key safety Control Room evacuation N/A function from outside the resulting in transfer of plant N/A Control Room control to alternate locations Other conditions exist that in Other conditions exist that in Other conditions exist that in Other conditions exist that in the The judgment of the the judgment of the Emergency the judgment of the judgment of the Emergency Emergency Director Director warrant declaration of Emergency Director warrant Director warrant declaration of a warrant declaration of a a SITE AREA EMERGENCY declaration of an ALERT UE GENERAL EMERGENCY 4-8

GG Revision 80 FSAR 02 / 2020 Table 4-1: Summary of Initiating Conditions Categor-v S - System M!)lf~nction The Initiating Conditions within this category are as follows :

General Emergency Site Area Emergency Alert Unusual Event Prolonged loss of all offsite Loss of all offsite power and all Loss of all but one AC power Loss of all offsite AC power and all onsite AC power to ESF onsite AC power to ESF uses for source to ESF buses for 15 capability to ESF buses for 15 buses 15 minutes or longer minutes or longer minutes or longer Loss of all ESF AC and vital DC Loss of all vital DC power for 15 power sources for 15 minutes N/A N/A minutes or longer or longe r UNPLANNED loss of Control Room indications for 15 minutes or longer with a UNPLANNED loss of Control Room N/A N/A significant transient in indications for 15 minutes or longer progress RCS activity greater than Technical N/A N/A N/A Specification allowable limits RCS leakage for 15 minutes or N/A N/A N/A longer Automatic or manual scram fail s to N/A N/A N/A shut down the reactor 4-9

GG Revision 80 FSAR 02 / 2020 Table 4-1: Summary of Initiating Conditions Catego[Y S - System Malfunction The Initiating Conditions within this category are as follows :

General Emergency Site Area Emergency Alert Unusual Event Automatic or manual scram fails to shut down the reactor Inability to shut down the and subsequent manual reactor causing a challenge to actions taken at the reactor Automatic or manual scram fails to N/A RPV water level or RCS heat control consoles are not shut down the reactor removal successful in shutting down the reactor Loss of all onsite or offsite N/A N/A N/A communications capabilities Hazardous event affecting SAFETY SYSTEMS needed for N/A N/A N/A the current operating mode 4-10

GG Revision 80 FSAR 02 / 2020 4-11

GG Revision 80 FSAR 02 / 2020 Table 4-2: Classification of FSAR Design Bases Accidents Design Bases Accident Classification Seizure of one recirculation pump Unusual Event Recirculation pump shaft break Unusual Event Rod drop accident Alert Instrument line break Unusual Event Steam system pipe break outside containment Site Area Emergency LOCA within reactor coolant pressure boundary Site Area Emergency Feedwater line break outside containment Site Area Emergency Main condenser Off Gas treatment system failure Site Area Emergency Liquid radwaste tank failure Alert Fuel handling accident outside primary containment Site Area Emergency fuel handling accident inside primary containment Alert 4-12

GG Revision 80 FSAR 02 I 2020 5 ORGANIZATIONAL CONTROL OF EMERGENCIES 5.1 GGNS Organization The Grand Gulf Nuclear Station operating, and licensing activities are under the control of the Site Vice President. The Site Vice President reports directly to the Chief Operating Officer. The Site Vice President is also assisted by the Director, Regulatory and Performance Improvement and the General Manager, Plant Operations.

5.2 Normal Station Organization The General Manager, Plant Operations is responsible forthe overall management of the station. The operating organization is in conformance with GGNS Technical Specification 5.3.1 and includes personnel encompassing both the management and operating units. An organizational chart showing the functional levels is given in Figu re 5-2. The administrative and technical support personnel staffing the GGNS organization are normally onsite daily Monday through Friday, holidays and off Fridays excluded. Plant Operations, Security, Maintenance, Chemistry, and Radiation Protection personnel are on duty 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day.

The Senior Manager, Operations; Senior Manager, Maintenance; Senior Manager, Production; Manager, Radiation Protection; Manager Chemistry report directly to the General Manager, Plant Operations, who, in turn, reports to the Site Vice President.

Figure 5-3 indicates the emergency positions usually filled by these individuals.

5.2.1 General Manager, Plant Operations The General Manager, Plant Operations is responsible for the technical and administrative management of the day-to-day physical operation and maintenance of the plant as carried out by the Operations, Maintenance, Radiation Protection and Chemistry Departments.

5.2.2 Senior Manager, Operations The Senior Manager, Operations is responsible for the functional. safe and efficient day to day operation of the plant in accordance with established procedures and the Technical Specifications. He reports to the General Manager, Plant Operations and is assisted by the Operations Manager, Shift; Operations Manager, Support; and Manager. Shift Ops. Training.

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GG Revision 80 FSAR 02 / 2020 5.2.3 Senior Manager, Maintenance The Senior Manager, Maintenance is responsible for the maintenance of all plant components I equipment and plant modifications and construction. He reports to the General Manager, Plant Operations and is assisted by the Superintendents from Mechanical, Electrical, I & C, Support and FIN Teams.

5.2.4 Manager, Radiation Protection The Manager, Radiation Protection is responsible for establishing and implementing the GGNS Radiation Protection program. The Manager, Radiation Protection reports to the General Manager, Plant Operations and is assisted by Radiation Protection Supervisors.

5.2.5 Senior Manager, Production The Senior Manager, Production manages and directs the activities of daily maintenance scheduling, ongoing scheduling evaluations and site integrated schedule activities. He is assisted by the Superintendent, Online Maintenance Scheduling, Supervisor Planning and Outage Manager. The Senior Manager, Production reports to the General Manager, Plant Operations.

5.2.6 Manager, Training The Manager, Training is responsible for the overall administration and documentation of the GGNS Training program. He reports to the Director, Regulatory and Performance Improvement with a direct line of communication to the Site Vice President and is assisted by the Training Superintendents.

5.2.7 Shift Technical Advisor The Shift Technical Advisor (STA) provides advanced technical assistance to the operating shift complement during normal and abnormal operating conditions.

During his shift, the STA is available to perform the general duties described in GGNS FSAR Section 13 .1. The Shift Technical Advisor reports directly to the Shift Manager.

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GG Revision 80 FSAR 02 / 2020 5.2.8 Manager, Supply Chain The Manager Materials, Purchasing and Contracts is responsible for the coordination of Material Management, Purchasing and Contracts. Although this is a Corporate function, this position has a direct line of communication with the General Manager, Plant Operations. The Supervisor, Procurement; and Supervisor, Materials; report directly to the Manager Materials, Purchasing and Contracts.

5.2.9 Director, Regulatory & Performance and Improvement The Director, Regulatory Performance and Improvement is responsible for all licensing activities, administering the Corrective Action Program, and overseeing Emergency Preparedness activities. He reports to the Site Vice President and is assisted by the Manager, Regulatory Assurance; Manager, Performance Improvement; and Manager, Emergency Planning.

5.3 Normal Station Shift Staffing During off-hour shifts, the plant is manned to maintain continuous operation as required by GGNS Technical Specifications.

5.4 Emergency Organization In the event of an emergency as defined in Section 4.0, the Emergency Organization is activated. The organization has predefined primary and alternate personnel for the various positions specified to provide for an automatic manning of the Emergency Organization within the time necessary to respond to the emergency.

The Emergency Organization is shown in Figure 5-3. The prerequisites for personnel who fill the emergency positions are listed in EN-TQ-110-01. The Site Vice President, through GGNS Management, designates personnel for these emergency positions. The extent to which the Emergency Organization is activated depends upon the classification of the emergency (see Section 6.2).

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GG Revision 80 FSAR 02 / 2020 5.4.1 Normal Station Shift The initial Emergency Organization consists of the normal operating shift with the Shift Manager serving as the Emergency Director. When the designated Emergency Organization personnel are available to augment the normal shift complement, the Shift Manager is relieved as EOF Emergency Director and the organizational control of the emergency shifts from the Shift Manager to the EOF Emergency Director. Shift staffing and augmentation capabilities are shown in Table 5-1.

5.4.2 EOF Emergency Director (ED)

The ED is responsible for the direction of the total emergency response. The ED's responsibilities include:

a. Activation/operation of the EOF. assuming responsibility from the Shift Manager;
b. Classification of the emergency (non-delegable):
c. Recommend protective action recommendations {PAR's) to the offsite agencies (non-delegable):
d. Notification of the event to the offsite agencies (non-delegable):
e. Coordinate accident information with offsite governmental agencies:
f. Request assistance from offsite agencies to support recovery operations:
g. Authorize radiation exposure in excess of 10CFR limits for the EOF personnel;
h. Approve press releases (non-delegable);
i. Direct the activities of the EOF organization in support of the Technical Support Center and offsite agencies.

5.4.3 EOF Manager The EOF Manager reports to the ED and oversees the activities in the EOF, Responsibilities include:

a. Assures timely activation of the EOF:
b. Obtains additional resources as necessary to support EOF activities .:
c. Assists the Radiological Assessment Coordinator with EOF Habitability:
d. Assist offsite authorities responding to the EOF;
e. Ensures the offsite notifications are conducted within the regulatory requirements.

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GG Revision 80 FSAR 02 / 2020 5.4.4 Radiological Assessment Coordinator (RAC)

The Radiological Assessment Coordinator is responsible for conducting assessment activities for offsite radiological conditions. During operation of the EOF. The Radiological Assessment Coordinator reports to the ED. Responsibilities include:

a. Direct the activities of the Dose assessment/radiological field monitoring.
b. Provide input to the ED regarding protective actions.
c. Provide radiological /radiation protection support to the EOF.
d. Keep the ED appraised of offsite radiological conditions.
e. Provide overall liaison and coordination of efforts in the area of field team data with State Radiological Personnel.
f. Contact for NRC on Health Physics Network (HPN) Line (Can be designated to a RP staff member) 5.4.5 Technical Advisor (TA)

The Technical Advisor reports to the ED. Responsibilities include:

a. Maintaining contact with the TSC and Control Room and obtains current plant status and emergency operations.
b. Monitor plant computer system parameters.
c. Recommend actions on classification of emergencies.

5.4.6 Admin. & Logistics Coordinator The Admin. & Logistics Coordinator is responsible for providing support to the EOF Manager and the TSC Emergency Response Organization. Responsibilities include:

a. Manage logistics for supporting the onsite and offsite emergency response such as additional support personnel or equipment meals. lodging, etc.
b. Manage 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> staffing for ERF's 5-5

GG Revision 80 FSAR 02 / 2020 5.4.7 Public Information Liaison The Public Information Liaison reports to the EOF Manager and provides the primary interface between the JIC and EOF. Responsibilities include:

a. Ensuring JJC is provided with current plant status.
b. Reviews press releases and provide to the ED for approval 5.4.8 Offsite Communicator The Offsite Communicator reports to the ED. Responsibilities include:
a. Transmitting information to the offsite agencies as required by regulations.
b. Ensuring ED approves all notification forms to State/Local agencies.

5.4.9 EOF Communicator The EOF Communicator reports to the EOF Manager, Responsibilities include:

a. Transmitting and receiving information from onsite ERF's.
b. Reviewing plant data and ensuring the EOF is notified of changing plant conditions.

5.4.10 Lead Offsite Liaison The Lead Offsite Liaison reports to the EOF Manager. Responsibilities include obtaining plant information and ensuring the offsite agencies located in the EOF and the offsite liaisons are briefed on the plant conditions.

5.4.11 Offsite Liaison The Offsite Liaison reports to the Lead Offsite Liaison. Responsibilities include:

a. Obtaining plant information and ensuring the offsite agencies located in the EOC are briefed on the plant conditions.
b. Clarifying plant conditions, responding to questions, etc. for the offsite agencies.

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GG Revision 80 FSAR 02 / 2020 5.4.12 Dose Assessor The Dose Assessor reports to the Radiological Assessment Coordinator.

Responsibilities include:

a. Calculate offsite dose projections.
b. Provide offsite dose projection information to the RAC.

5.4.13 Offsite Team Coordinator (OTC)

The Offsite Coordinator reports to the Radiological Assessment Coordinator.

Responsibilities include:

a. Maintain communications with offsite monitoring teams (OMT).
b. Direct OMT based on radiological/met information.
c. Log communications with OMT to include dose /air sample survey results.
d. Ensure radiological information is communicated to the RAC for possible modifications to the dose calculations.

5.4.14 Offsite Monitoring Team (OMT)

The Offsite monitoring team reports to the Offsite Team Coordinator (OTC}.

Responsibilities include:

a. Perform activities directed by the OTC to support plume tracking and measurements.
b. Monitor self-reading dosimeters and report results back to the OTC.

5.4.15 Information Technology (IT) Specialist - EOF The Information Technology (IT) Specialist reports to the Admin. & Logistics Coordinator and is responsible for monitoring facility equipment (computer related and communications) to ensure adequate operation.

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GG Revision 80 FSAR 02 / 2020 5.4.16 EOF Log Keeper The EOF Log keeper reports to the ED. Responsibilities include

a. Maintain facility log
b. Ensure timeliness of facility briefs
c. Support the EOF Manager/ED as requested.

5.4.17 Emergency Plant Manager (EPM)

The EPM has the direct responsibility for accident mitigation at the plant and performs these duties from the Technical Support Center {TSC). The EPM reports to the EOF ED . Responsibilities include:

a. Provide information and recommendations to the ED regarding the declaration of an emergency.
b. Coordinate the activities of the CR, TSC and OSC.
c. Direct personnel assembly, accountability and evacuation of non-essential personnel.
d. Provide information and recommendations to the ED regarding plant activities.
e. Direct the organization and coordination of repair corrective action teams.
f. Initiate protective actions at the site.
g. Authorize radiation exposure in excess of 10CFR20 limits to onsite personnel.
h. Make operational decisions involving the safety of the plant and its personnel and make recommendations to the Control Room Personnel.

5.4.18 TSC Manager The TSC Manager reports to the EPM. Responsibilities include:

a. Perform technical assessments and communicating the conclusions to the EPM.
b. Assures staffing/timely activation of the TSC.
c. Set priorities for the Engineering and Technical personnel.
d. In conjunction with the EPM, make operational decisions concerning the safety of the plant.

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GG Revision 80 FSAR 02 / 2020 5.4.19 TSC Communicator The TSC Communicator reports to the TSC Manager. Responsibilities include:

a. Maintain facility log
b. Ensure timeliness of facility briefs
c. Support the EPM/TSC Manager as requested.

5.4.20 Security Coordinator The Security Coordinator is located in the Incident Command Post and reports to the EPM. Responsibilities include:

a. Overall coordination of the offsite assistance for the security related response.
b. Designated NIMS Liaison between the Incident Command Post and Site Organization.

5.4.21 ENS Communicator The ENS Communicator reports to the TSC Manager. Responsibilities include:

a. Establishes and maintains communications with the NRC via the ENS phone.
b. Monitor plant computer parameters and provide plant status to the NRC as requested.

5.4.22 Maintenance Coordinator The Maintenance Coordinator reports to the TSC Manager. Responsibilities include:

a. Communicate the request for repair and corrective teams lo the OSC Work Control Coordinator.
b. Prioritizes the requests with the TSC Manager.

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GG Revision 80 FSAR 02 / 2020 5.4.23 Engineering Coordinator The Engineering Coordinator reports to the TSC Manager. He is responsible for coordinating Engineering work requests with the Engineering support team.

5.4.24 Radiological Coordinator The Radiological Coordinator reports to the TSC Manager. Responsibilities include:

a. Radiological assessments and the development of radiological plans.
b. Keeping the TSC Manager informed of the radiological conditions.
c. Advise the TSC, OSC and EOF of changes in radiological release status.
d. Coordinate with the Security Coordinator to determine the routes to be used for evacuation of non-essential personnel and BRE's.
e. Arranging for additional radiation protection personnel, as necessary 5.4.25 Operations Coordinator The Operations Coordinator reports to the TSC Manager. Responsibilities include:
a. Coordinate TSC efforts in determining the nature and extent of emergencies pertaining to equipment and plant facilities in support of Control Room actions.
b. Assist the EPM in evaluating changes in event classification.
c. Ensure the Control Room, TSC, and EOF is informed of significant changes in event status.
d. Coordinate operations activities outside of the Control Room with the TSC Manager and OSC Manager.

5.4.26 Engineers {Mechanical/ l&C/ Electrical)

The Engineers report to the Engineering Coordinator. The Engineers are responsible for responding to engineering requests form the Engineering Coordinator.

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GG Revision 80 FSAR 02 / 2020 5.4.27 Reactor Engineer The Reactor Engineer reports to the TSC Manager. Responsibilities include:

a. Support the TSC in calculating and tracking core reactivity (core damage assessment).
b. Assist in Severe Accident Procedure implementation.

5.4.28 OSC Manager The OSC Manager has the overall responsibility for the activation and operation of the Operational Support Center. The OSC Manager reports to the EPM located in the TSC. Responsibilities Include:

a. Direct the activation, operation and deactivation of the OSC.
b. Ensures timely dispatching of the repair/corrective action teams, search and rescue teams, onsite monitoring teams and mobilizing other required support personnel.
c. Ensures work task priorities are being maintained.
d. Maintain OSC accountability.

5.4.29 Log Keeper OSC The Log Keep - OSC reports to the OSC Manager. Responsibilities include:

a. Maintain facility log.
b. Ensure timeliness of facility briefs.
c. Support the OSC Manager as requested.

5.4.30 Operations Support The Operations Support position reports to the OSC Manager and is manned by a spare Non-Licensed Operator. The Operations Support is responsible for supporting the OSC in locations of plant equipment. This position is filled as needed.

a. Supports OSC, as needed.
b. Ensures Shift Manager is informed of OSC teams and activiti.es.
c. Identifies potential operational support needs.

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GG Revision 80 FSAR 02 / 2020 5.4.31 Work Control Coordinator The Work Control Coordinator reports to the OSC Manager. Responsibilities include:

a. Direct the formation, briefing and debriefing of repair and corrective action teams and offsite monitoring teams.
b. Maintain communications with the Maintenance Coordinator in the TSC.

5.4.32 Mechanical /I & C /Electrical Coordinator The Mechanical, l&C, and Electrical Coordinators report to the Work Control Coordinator. Responsibilities include:

a. Assist the conduct of the briefing and debriefing for the assigned tasks.
b. Ensures communications with repair and corrective action teams.

5.4.33 Rad Chem Coordinator The Rad Chem Coordinator reports to the Work Control Coordinator.

Responsibilities include:

a. Determining emergency radiological survey requirements.
b. Ensure use of protective clothing, respiratory protection, and access control within the plant is deemed appropriate to control personnel exposures.
c. Ensures the dispatching of the onsite monitoring teams.
d. Ensures habitability of the OSC
e. Conduct/provide assistance for the rad briefings to support the dispatching of the repair/corrective action teams and chemistry/ RP sampling.
f. Communicate rad/chemistry sample results to the TSC and CR.

5.4.34 Company Spokesperson The Company Spokesperson is responsible for overall public information.

Responsibilities include:

a. Obtain briefing from the EOF ED to ensure timely development of news releases .

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GG Revision 80 FSAR 02 / 2020

b. Ensures that news media briefings are held regularly during the course of the emergency.
c. Serves as spokesperson at media briefings.

5.4.35 Technical Advisor-JIC The Technical Advisor reports to the Company Spokesperson and is responsible for answering technical questions from the news media regarding the emergency situation.

5.4.36 JIC Manager The JIC Manager reports to the Company Spokesperson. Responsibilities include:

a. Overall activation and operation of the Joint Information Center.
b. Notify the Corporate Emergency Center.

5.4.37 Log Keeper-JIC The Log keeper- JIC reports to the JIC Manager. Responsibilities include:

a. Maintain facility log.
b. Support the RC Manager as requested.

5.4.38 Inquiry Response Coordinator The Inquiry Response Coordinator reports to the JIC Manager. Responsibilities include:

a. Ensures activation of rumor control activities for response to questions from the general public.
b. Monitor the public/media inquiry calls and track trends.

5.4.39 Press Release Writer The Press Release Writer reports to the JIC Manager and generates press releases as directed by the JIC Manager.

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GG Revision 80 FSAR 02 / 2020 5.5 Recovery Organization Recovery after an emergency condition is handled by the Emergency Organizations. The EOP Emergency Director and Emergency Plant Manager may relieve personnel of their emergency duties and return them to their normal responsibilities retaining such personnel ns necessary to staff a recovery organization.

The recovery organization depends upon the nature of the emergency and the situation which exists after the emergency. Specific organization structure and staffing is the responsibility of the Site Vice President at the time the recovery organization is instituted.

Authority and responsibility of individuals who fill key positions in the recovery organization are the same as that held in the respective emergency organizations.

5.6 Local Services Support The potential nature of some emergencies may warrant the utilization of offsite individuals, organizations, and agencies. As a result, local support service arrangements have been made with offsite groups to provide aid in the event of an emergency situation, including hostile action situations, at Grand Gulf. Support services encompass such things as medical assistance, fire control, evacuation, ambulance services, and law enforcement.

Since it is imperative that the availability of these support agencies be on short notice, written agreements have been entered into with the organizations. The agencies, in the Letters of Agreement, have outlined their responsibilities, assuring their response to a call for aid. Copies of the appropriate Letters of Agreement have been included in Appendix D.

The local services support groups are described in the following subsections.

5.6.1 Medical Support In certain instances, medical emergencies may require the transport of an injured person from the Station to an offsite medical facility. Transportation of injured persons to the medical facility is normally provided by the regional ambulance service. In the event that these services are unavailable, provisions are in place to transport injured persons in company owned or private vehicles. Ambulances are equipped with radios to maintain communications with the hospital. The primary medical facility for injured personnel, with or without contamination, is the Claiborne County Medical Center (also referred to as Claiborne County Hospital) located in Port Gibson approximately six miles from the plant site. This Medical Center has agreed to accept injured personnel and/or victims of radiation-related accidents for emergency medical and surgical treatment and observation. River 5-14

GG Revision 80 FSAR 02 I 2020 Region Medical Center has agreed to serve as a back-up, with the same emergency medical capabilities as Claiborne County Medical Center.

Hospital emergency kits for treatment of contaminated. personnel are maintained at these facilities.

If medical treatment of the injured and/or contaminated personnel requires assistance or medical expertise beyond the capabilities of the local facilities, the patients would be transferred to a support hospital. GGNS has an agreement with The Ochsner Clinic to provide hospital and medical services for injured/

contaminated or overexposed personnel.

5.6.2 Fire Support When it is determined by emergency management personnel that offsite fire support is needed, the Claiborne County Fire Department, located approximately six miles from the plant and available 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day, is alerted.

Notification of a need for offsite firefighting assistance is made by means of a telephone call.

The Claiborne County Fire Department has an informal aid pact with the Port Gibson Fire Department. These two firefighting groups have agreed, upon request, to furnish each other with firefighting personnel, resources, and facilities and to render such fire protection services which may be necessary to suppress any fire or disaster which goes beyond the control of either of the agencies. In all cases where additional fire support groups would be brought in to assist at the Station, the Claiborne County Fire Department Fire Chief directs all offsite firefighting personnel, while the GGNS Emergency Director retains overall responsibility for onsite emergency response. In instances where offsite firefighting assistance is needed to fight a fire involving radioactive materials, radiological information and assistance is provided by knowledgeable members of the Emergency Organization.

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GG Revision 80 FSAR 02 / 2020 5.6.3 Law Enforcement Agencies The nature of a radiological emergency at the Grand Gulf Nuclear Station may require that the local law enforcement agencies be activated to assist in the emergency effort. Because it is essential that they be available during certain emergency situations, the Claiborne County Sheriff's Department and the Port Gibson Police Department have agreed to provide the following emergency support:

a. Controll ing matters of civil disorder within Claiborne County (provided by Sheriff's Department) and within the city limits of Port Gibson (provided by Sheriff's Department and Port Gibson Police Department)
b. Communications
c. Furnishing personnel and equipment in accordance with Security Plans.
d. Controlling access to areas affected by the emergency
e. Directing area evacuation.

5.7 Coordination with Governmental Agencies The close coordination between the local, State, and Grand Gulf Nuclear Station Emergency Plans serves to better ensure the safety and health of the general public. It also enables all emergency organizations to participate in the emergency effort with a minimum of confusion and hesitation. All participating agencies must have a clear picture of their responsibilities during an emergency effort, including hostile actions, which is provided for in their respective emergency plans and procedures.

Figure 5-5 depicts the interrelationships among some of the various state and federal organizations which may respond to an emergency at GGNS. The Federal Response Management Organization is shown in Figure 5-6.

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GG Revision 80 FSAR 02 / 2020 5.7.1 Mississippi Emergency Management Agency (MEMA) and Mississippi State Department of Health/Division of Radiological Health (DRH)

The Mississippi Emergency Management Agency is the designated Stale authority and as such, has the responsibility for the general planning and coordination of the State of Mississippi's response to nuclear plant accidents as detailed in the "Mississippi Radiological Emergency Preparedness Plan Volume Ill to the Mississippi Comprehensive Emergency Management Plan". Some of the functions of MEMA are (1) development and maintenance of State Plans and Procedures. (2) operation of the State Emergency Operation Center (EOC). (3) notification and warning in coordination with the Mississippi Highway Safety Patrol and the operators of fixed nuclear facilities. (4) communications. (5) assist local governments in the development and maintenance of plans and procedures. (6) public information. (7) training. (8) providing personnel for the Radiological Emergency Response Teams and (9) providing continuity of technical, administrative, and material resources. A letter (see Appendix D) from the Governor of Mississippi which implements the Mississippi Radiological Emergency Plan is a commitment from all state agencies to perform their functions delineated in the State plan as required by Mississippi law.

The Mississippi State Department of Health/Division of Radiological Health is charged with the responsibility to protect the public health and safety of the general populace from the hazards of radiation. With respect to radiological hazards resulting from incidents involving fixed nuclear facilities, the functions of DRH include (1) act as lead agency for technical Response. (2) accident assessment. (3) provide personnel and equipment for the Radiological Emergency Response Team. (4) advise Slate and local officials on implementation of protective actions based on accident assessment. (5) establish radiological exposure controls, (6) access/egress and reentry criteria. (7) Laboratory services. (8) coordinate offsite decontamination activities.

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GG Revision 80 FSAR 02 / 2020 5.7.2 Louisiana Department of Environmental Quality (LDEQ) and Governor's Office of Homeland Security and Emergency Preparedness (GOHSEP)

The Secretary of the Louisiana Department of Environmental Quality under Act 97 of 1983 (L.R.S. 30:2001 et. seq.), also known as the Louisiana Environmental Quality Act, and specifically L.R.S. 30:2109, has the authority to develop and implement a statewide radiological emergency preparedness plan and coordinate the development of specific emergency plans for nuclear power facilities, including planned protective action for the population and the establishment of appropriate boundaries for which planning for nuclear emergencies is undertaken; to respond to any emergency which involves possible or actual release of radioactive material; to coordinate offsite decontamination efforts; to issue relocation and evacuation recommendations; and to otherwise protect the public welfare and safety in any manner deemed necessary and appropriate. As a result, the "Louisiana Peacetime Radiological Response Plan," which includes Attachment 2 for the Grand Gulf Nuclear Station, has been developed. Federal, State and local agencies are notified as required to provide assistance in evaluating the radiological hazard and providing implementation of appropriate protective actions in accordance with this plan. The Secretary of the LDEQ or his designee is responsible for notifying the public that a radiological incident has occurred and for providing an evaluation of the incident in terms of public health. If protective actions are indicated, specific guidance can be provided, and the information released.

The Governor's Office of Homeland Security and Emergency Preparedness (GOHSEP) is responsible for coordinating all emergency actions of the various State and local agencies in the event that evacuation is necessary. Local law enforcement agencies, rescue squads, medical facilities and other parish and municipal agencies provide assistance pursuant to their agreements with local civil defense organizations as delineated in the local civil defense plans . The GOHSEP immediately notifies LDEQ in the event of a radiological emergency. A letter (see Appendix D) from the Governor of Louisiana to implement the Louisiana Peacetime Radiological Response Plan is a commitment from all State agencies to perform their functions as delineated in the State plan as required by Louisiana law.

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GG Revision 80 FSAR 02 / 2020 5.7.3 Port Gibson/Claiborne County Civil Defense The Port Gibson/Claiborne County Civil Defense Director is the designated County authority and as such, has executive authority and responsibility for the planning and coordination of the County's emergency response. The Director has delegated responsibilities and tasks to the local support agencies and has established operating procedures to implement the "Port Gibson/Claiborne County - Radiological Emergency Preparedness Plan." Upon notification of a major emergency at the Grand Gulf Nuclear Station, the Civil Defense Director, as a primary duty, provides direction within the County boundaries. This duty includes, if required, the coordination with other agencies to inform the public in affected portions of the County to take protective actions.

The Port Gibson/Claiborne County Civil Defense Director is responsible for activation of the Claiborne County Emergency Operations Center (EOC).

5.7.4 Tensas Parish Office of Homeland Security and Emergency Preparedness The President of the Tensas Parish Police Jury as the Chief Executive of Tensas Parish is responsible by law for emergency preparedness operations. The Emergency Preparedness Coordinator acts as his Chief of Staff and ensures continuity of resources for sustained emergency operations. The Emergency Preparedness Coordinator is responsible for initiating the manning of the Tensas Parish Emergency Operations Center and for coordinating the involved agencies during the course of the radiological emergency as detailed in the "Tensas Parish Radiological Emergency Implementing Plan for Grand Gulf Nuclear Station."

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GG Revision 80 FSAR 02 / 2020 5.7.5 Nuclear Regulatory Commission (NRC)

The United States Nuclear Regulatory Commission, Region IV dispatches an Initial Response Site Team (IRST) to GGNS upon declaration or a Site Area Emergency or General Emergency and may dispatch the team upon declaration of an Alert.

Members of the team are assigned to the TSC, EOF and ENMC. Primary functions of the IRST are:

a. Oversee licensed activities to ensure a reasonable effort is being made to mitigate the accident.
b. Evaluate protective actions taking place and make an independent evaluation of recommended protective actions.
c. Evaluate direction being given to reactor operators to bring the plant to a stable condition, and
d. Oversee GGNS's ability to provide information to the news media and the public concerning information about the status of the plant and the offsite consequences, The IRST has the capability to arrive at GGNS in approximately 4 - 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Once notified, the plant shall maintain an open continuous communication channel with the NRC Operations Center via the NRC Emergency Notification System until terminated by the NRC Operations Center. The NRC Operations Center can be activated within 15

- 30 minutes during normal working hours and within 1 -2 hours after normal working hours.

5.7.6 Department of Energy (DOE)

The Department of Energy assists during an emergency by providing monitoring assistance through their Radiological Assistance Plan (RAP) and lnteragency Radiological Assistance Plan (IRAP) when requested in support of state and local mon itoring operations. In addition, the Emergency Director may also request this assistance. Some of the specialized equipment and services that DOE can provide are:

alpha detection equipment, low energy gamma detectors and special aircraft monitoring. The Department of Energy can also assist in the radiation monitoring of food, water, livestock, and agricultural products. When deemed necessary, the DOE makes available special aerial radiological surveys and meteorological services. The estimated arrival time to the GGNS area for the DOE Region Ill Oak Ridge Operations team is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

5-20

GG Revision 80 FSAR 02 / 2020 5.7.7 Institute of Nuclear Power Operations (INPO)

The Institute of Nuclear Power Operations provides emergency response as requested by GGNS. INPO can provide assistance in the following areas:

a. Location of sources of emergency manpower and equipment
b. Analysis of the operational aspects of the event
c. Organization of industry experts who could advise GGNS on technical matters.
d. INPO may be contacted by means of its 24-hour telephone number in the event of a radiological emergency at GGNS.

5.7.8 U.S. Coast Guard.

The U.S. Coast Guard has jurisdiction over the traffic on the Mississippi River. Upon notification by the Mississippi State Emergency Management Agency of an emergency requiring traffic exclusion, the Captain of the Port exercises his authority to control marine traffic through the establishment of a safety zone in the immediate area.

5.8 Contractor Assistance GGNS has made provisions with General Electric (NSSS Supplier), to provide both routine and emergency technical assistance and support in accordance with GE Services Letter GE-SIL-324.

5.9 Support for Federal Response Office and communications facilities are provided for responding NRC personnel within the TSC, EOF, and JIC, and for responding DOE personnel within the EOF. Additional State and County (Parish) resources available to support the Federal response, such as air fields, emergency operations centers, and communications capabilities are described in Grand Gulf Nuclear Station Supporting Emergency Response Plans.

5-21

GG Revision 80 FSAR 02 I 2020 Table 5-1: Shift Staffing and Augmentation Capabilities Major Emergency Tasks Position Title or Expertise Location On Capability for Additions Functional Area Shift(e) 90 Min (h)

Emergency Direction and Control {f) Shift Manager {SRO) CR 1 --

Emergency Director CR/EOF -- l(g)

Control Room Supervisor (SRO) CR 1 --

Nuclear Operator A (RO) CR 3(i) --

Plant Operations and Assessment of Auxil iary Operator (AO) CR 3 --

Operational Aspects Firefighting, firefighting Sh ift Personnel (Operations) CR Provided by Claiborne S{a) communications County/ Port Gibson Technical Support and Core thermal Shift Technical Advisor CR Hydraulics(d) l(c) -

Core thermal Hydraulics Reactor Engineers/SRO/STA TSC/CR -- l(g)

Offsite Notifications (State, Local, CR/EOF Notification/ Federal) and maintain Communicator 2 2(g)

Communication communications, Notification of Plant On-Call emergency personnel Rad iological Accident EOF Direction and Control Senior Management EOF -- 1 Assessment and Support Offsite Dose Assessment Radiological Assessment CR/EOF l(a) l(g) of Operational Accident Assessment Chem istry/Radio-Chemistry Chemist osc 1 1 Electrical TSC/OSC -- 1 Plant System Engineering Technical Support Mechan ical TSC/OSC -- 1 Mechanical Maintenance osc l{a) 2 Radwaste Operator osc l(a) 1 Repair and Corrective Electrical Maintenance! l&C osc Actions Maintenance 2 --

Electrical Ma intenance osc -- 2 l&C Maintenance osc -- 1 5-22

GG Revision 80 FSAR 02 / 2020 Major Emergency Tasks Position Title or Expertise Location On Capability for Additions Functional Area Shift(e) 90 Min (h)

Radiation Protection

  • Access Control
  • HP coverage for repair, corrective actions, search and rescue/first-aid, and firefighting Health Physicist EOF/OSC 2 ll(b)
  • Personnel monitoring
  • Dosimetry
  • Surveys (offsite, onsite, and in-plant surveys on as needed basis only)

Rescue / First aid Rescue and First Aid Provided by Claiborne DSC 2(a)

County/ Port Gibson Security Security, personnel accountability Security Personnel (See Security Plan)

Notes:

(a) May be provided by Shift Personnel assigned other duties.

(b) Must be trained for the Emergency Task being performed.

(c) STA staffing in accordance with GGNS Technical Specification.

(d) Core/Thermal Hydraulics is part of normal STA duties as listed in the Updated Final Safety Analysis Report and Technical Specifications.

(e) These ERO positions may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absences, provided action is taken to fill the required position. This allowance is not applicable during declared emergencies.

(f) Overall direction of facility response is assumed from the Shift Manager (SRO) by the Emergency Director. Upon relief, the Shift Manager (SRO) resumes plant operational duties.

(g) These personnel will report and augment shift personnel as soon as possible without delay but no later than 75 minutes.

(h) If personnel are onsite they will report and augment the onshift personnel as soon as possible without delay, but no later than 45 minutes. Offsite personnel will report to their assigned facility as soon as possible without delay, but no later than 90 minutes.

(i) The role of the third RO may be fulfilled using an AO as allowed by TRM based upon GGNS on-shift staffing analysis.

5-23

GG Revision 80 FSAR 02 / 2020 Figure 5-1: Figure Deleted 5-24

GG Revision 80 FSAR 02 / 2020 Figure 5-2: Normal Station Organization SITE VICC PRESIDENT OIRt:CTOR CXCClITIIIC REGULATORY & ASSISTN-ICf SITE \IP PCRfORMN<CE IMPROVEMENT MANAGCR.

PEHFORMANCE IMPROVEMENT MANAGER SITE II MAN"GER OPERATIONS

~W<,.GCR CHEMISTRY MAN,>,GER RAOIAllON MAAAGER.

PROOUCTION PROJECTS& PROTECTION MANAGER. WJNT REGULATORY SERVICCS MANAGER COORDINATOR/

ASSURANCE SUPERVISOR.

OUTAGE OPIC.

~

MAJNTI,NANCE TECH SUPPORT MMIAGER.

EMERGCNCY SUPERVISOR.

ASSl!if ANf MANAGER SUPERINTENDENT Pl.MINING SUPERINlENDENT PL>NNING OPERATIONS SHIFT RP OPS l&C SUPT ONUNE MANAGER SUPERVISOR MAINT SUPERINTENDENT SECURITY RP SUPPORT SCHEDULING MCCHANICAL OPERATORS WORK CONIROl IAAHAGER SUP~RINTENOENT TFWHll,Ki ELECTRICAi.

SUPCRVISOR RCACIOR SUl'ERIN IENO~ M SUP! OPS £NGINEERINCl FIN TE.AM TRAINING M"""'GER, SUf>T . MATERl AL~

MAINTENANCE PURCHASING

& TECHNIC,V. & CONTRAC1S IAAINING SUPERVISOR, SUPT PROCUREMENT SIMUL>TOR&

TRAINING SUPERVISOR SUPPORT MATEHIALS MATERIAL.

PROJECI S COOAtllNA 1 OR SUPERVISOR _ Hnu ol communlcallon STORES - - - - - fine o f responslbillly 5-25

GG Revision 80 FSAR 02 / 2020 Figure 5-3: Emergency Organization GG FSAR EMERGENCY ORGANIZATION EMERGEtCY PLAtlT MAU-,CER RESIDES TSC TSC CO WUtlCATOR RESIDES TSC SECURITY SHIFT SECURITY CC>ai[l:UATOR Sl.PER"1SOR TSC IAAUAGER OSC MAUAGER RESIOES sf"flfJ~L ALARM RESIDES TSC RESIDES IIODEtlT COMMAtlD POST RE SIDES OSC RAO Ja. OGK:lril. COOADUATOR SHFT TEO-U.ICAL HlVISOA COHTROL ROOM S UPfRVISOR LOG KEE FER

  • OSC RESIDES TSC RES OES TSC RfSIOES COtlTROL ROOM RESIDES COHTROL ROOM RESIDES OSC OPE.RATI OlS COOROIUATOR COUTROL ROOM OPERATOR TSC CO lrM,IUr,CATOR RESIDES CR WORK COUTROLCOORDf'-'TOR RESIDES COUTROLROOM RESIDES TSC RE SIDES OSC PLAHT OPERA TORS EUS C CMMUII C ATOR EUGltE.ERlt.C COOROlr6'TOR RESIDES IU PLAUT RESIDES TSC RESIDES TSC RADOIEM CO~DIUATOR RESIDES asc FIRE BRIGADE RESIDES !UPLAUT RE.,C TOR EW:ltlEER MEC>I £1<<.IIEER ELECT l &CEUG RESIDES TSC RESIDES TSC RESIDES TSC 5-26

GG Revision 80 FSAR 02 / 2020 Figure 5-4: Emergency Organization EMERGENCY DIRECTOR GG RESIDES EOf TS:HNICAL ADVISOR FSAR RESIDES EOF

=RGENCY ORGANIZATION I

\

I I I EOF MAt~AGER RADIOLOGICAL ASSESSMENT OFF SITE COMMUNICATOR COORDINATOR COMPANY SPOKESPERSON RESIDES EOF RESIDES EOF

- RESIDES EOF RESIDES .JC EOFCOM M UNICATOR DOSE ASSESSOR

...... I RESIDES EOF RESIDES EOF

.._ I TECHNICAL ADVISOR JICMANAGER RESIDES J C AOMI NISlRATlON & RESIDES .IC IT SPECIALIST LOGISTICS COORDINATOR

- RESIDES EDF - RESIDES EOF OFFSITE TEAM COORO RESIOES EOF

- I I

INUIRY RESPONSE I LOG KEEPER* JIC I

PRESS RB.EASE PUBLIC IUfORMAHON LIAISON I COORDINATOR WRIIEA RESIDES .JC

- RESIDES EOF OFF SITE M0t,1TORING TEAMS RESIDES .JC RESIDES .IC RESIDES EOF I

INUIRY RESPONSE IfAM LEAD OFFSITE LIAISON RESIDES .JC

- RESIDES ECF I

OFF SITE UN SOU t-1 RESIDES EOCa 5-27

GG Revision 80 FSAR 02 / 2020 Figure 5-5: Interrelationships of Emergency Response Organ ization Interrelationships of Emergency Response Organization Control Room (NR CI

  • Te chnica l Support Center
I I

Operations Supp ort Center I Onsite 1 Entergy I I

1 Ope,::r ns CEC I I

Offs ite I Federal Support

-NRC I (NRCI

- Emergency

-FEMA I Operations Facility Field Monitoring Teams i

  • Joint Information Center

' j~

. State/Local EOCs (FEMA J
- M1ss1sslpp1 State EOC Loutstana State DEQ  ::::

Suppor t I da1borne County EOC Tensas Parish EOC GGNS I I

,- - - - - - - I Entergy Operations I ___ ____ !

GGNS / Agency Agency Support 5-28

GG Revision 80 FSAR 02 / 2020 Figure 5-6: Federal Response Management Diagram Federal Response Management Diagram Governor or Designated Rep_resentative NRC/FEMA Joint Coordination Federal Technical Support Federal Non -Technical Support NRC FEMA Coordinates Technical Coordinates Non-Aspects of Federal Technical Aspects of Response Federal Response DOE I I NCS I I DOD I I DOC I I USDA I I DHHS I I FEMA I I EPA I ~T Coordinates Federal Offsite Radiological Monitoring U ti Iit.'t'______j Source: Federal Register 45FR84911 NRc;l Utility

~ ~ ~ r3/4-i ~ I uJoA I 5-29

GG Revision 80 FSAR 02 / 2020 6 EMERGENCY MEASURES 6.1 Initiating Emergency Measures Emergency measures must be taken in response to an emergency condition. Upon recognizing and officially declaring that one of the four classes of emergencies exists, the emergency organization is activated. Once activation has taken place, assessments of the condition are made. corrective and protective actions are taken and aid to affected persons is administered as required.

6.1.1 Emergency Suspension of Normal Quality Assurance Procedures and Administrative Controls.

License Conditions. and Technical Specifications Should emergency circumstances require, reasonable actions that depart from normal Quality Assurance Procedures, Administrative Controls, License Conditions or Technical Specifications may be taken when this action is immediately needed to protect the public health and safety. These actions may only be taken if no action consistent with normal Quality Assurance Procedures. Administrative Controls, License Conditions and Technical Specifications that can provide adequate or equivalent protection is immediately apparent. At a minimum, approval by a licensed senior reactor operator is required before any such action may be taken.

6.1.2 Suspension of Normal Emergency Actions for Security Emergencies The Emergency Director and Emergency Plant Manager, upon the Emergency Director's evaluating and classifying a security emergency into any of the four emergency classifications discussed in Section 4.0. should only activate those personnel and facilities necessary to mitigate the emergency situation. This is the only exception to the personnel and facility activations described in the Plan and related implementing procedures: it is permitted because of the potential risk to personnel which a security emergency may present.

6-1

GG Revision 80 FSAR 02 / 2020 6.2 Activation of Emergency Organization The initial step in declaring an emergency is to recognize that an unusual condition exists or has the potential for existing. The Emergency Action Levels, as specified in Section 4.0, provide the criteria for determining when an abnormal situation exists that requires the declaration of an emergency and the subsequent activation of the applicable portions of the Emergency Organization.

6.2.1 Control Room Operators Normally, initial recognition of conditions requiring emergency actions occurs in the Control Room. Sometimes these conditions are signaled by alarms or instrument readings. If control room operators, or any other shift personnel, recognize an unusual condition or occurrence, it is their responsibility to immediately notify the Shift Manager.

6.2.2 Shift Manager Upon notification of a real or potential emergency condition, the Shift Manager is responsible (or determining whether or not the declaration of an emergency is required. If it is, he is then responsible for the activation of the Plan and assuming the role of Emergency Director. If a specific action level has been reached or exceeded, he declares the appropriate emergency classification.

The Shift Manager takes the following actions to ensure the safety of plant personnel and the general public and the safe operation of the plant.

1. Classify the emergency and make the required notifications
2. Perform assessment actions
3. Perform any other emergency actions as appropriate.

6.2.3 Shift Technical Advisor The Shift Technical Advisor advises and assists the Shift Manager on matters pertaining to the safe operation of the plant.

6-2

GG Revision 80 FSAR 02 / 2020 6.2.4 Emergency Director The Plan is activated with the declaration of an emergency. The Shift Manager continues as the Emergency Director until properly relieved by the EOF Emergency Director. The Emergency Director shall ensure that notification is initiated within 15 minutes of an emergency declaration.

Primary Secondary

1. (a) Mississippi Emergency Management (b) Mississippi Hwy Agency Patrol
2. (a) Governor's Office of Homeland (b) Louisiana Dept. of Security and Emergency Preparedness Envir. Quality
3. (a) Claiborne County Sheriffs Dept (b) Claiborne County Civil Defense
4. (a) Tensas Parish Sheriffs Dept An example of the form that is used for Emergency Notification is shown in Figure 6-2 and included as part of the Emergency Preparedness Forms Control Process.

Copies of this notification form are available in the appropriate emergency centers. The phone number is included on the form, so states may call back to verify the authenticity of the accident.

In accordance with 10CFRS0.72 the NRC Operations Center shall be notified by telephone immediately after notification of the appropriate state and local agencies and not later than one hour after the declaration of one of the Emergency Classes.

Upon arrival in the EOF, the EOF Emergency Director assumes the position of emergency Director in accordance with Emergency Plan Procedures.

The Emergency Director evaluates the accident conditions and verifies that the correct emergency classification has been declared. He then activates the appropriate portions of the Emergency Organizations if that has not already been done by the Shift Manager. In any case, the Emergency Plant Manager is notified.

6-3

GG Revision 80 FSAR 02 / 2020 If an Unusual Event has been declared, those members of the operating shift needed to handle the emergency are activated. If the Emergency Director feels there is a reasonable possibility of escalation of the emergency to a higher classification, applicable portions of the Emergency Organization are activated.

If an Alert. Site Area Emergency or General Emergency has been declared, the entire Emergency Organization is activated.

6.3 Assessment Actions Continuous assessment throughout the course of an emergency is necessary to effectively coordinate and direct the elements of the Emergency Organization. The initial assessment actions are dictated, in part. by the Emergency Action Level that has been reached or exceeded.

6.3.1 Assessment Actions During Unusual Events An Unusual Event condition requires basic emergency assessments. Attention must be paid to parameters that may indicate a possible worsening of conditions, (i.e. radioactive releases).

6.3.2 Assessment Actions During Alerts The existence of an Alert condition requires the following assessment actions as applicable.

a. Increased surveillance of applicable in-plant instrumentation.
b. Visual observation of the affected plant area.
c. Onsite and offsite radiological monitoring if a radioactive release has taken place or is suspected.
d. Determination of offsite doses if applicable.

6-4

GG Revision 80 FSAR 02 I 2020 6.3.3 Assessment Actions During Site Area Emergencies In the event of a Site Area Emergency, assessment activities arc more extensive than for an Alert. In addition to the activities that would be carried out during an Alert, the following activities would be performed as appropriate:

a. Monitor Meteorological data.
b. Dispatch radiological monitoring teams to offsite locations downwind of a release in conjunction with state radiological monitoring efforts.
c. Assess Offsite radioiodine thyroid doses.
d. Assess Offsite whole body dose.

6.3.4 Assessment Actions During General Emergencies In the event of a General Emergency, all assessment activities described for a Site Area Emergency will be conducted. Assessment of onsite and offsite exposures are performed regularly to determine if and when site or public sheltering and evacuations may be required; and the results, including methods and assumptions, are communicated to offsite officials.

6.4 Corrective Actions Corrective Actions are performed by plant personnel who are technically trained and capable of implementing the station's Plan and procedures.

6.5 Protective Actions The protective actions to be implemented onsite are the responsibility of GGNS, while the States of Mississippi and Louisiana and the counties within the 10-mile EPZ are responsible for providing offsite protective actions. The states are specifically responsible for protective actions for the SO-mile ingestion pathway EPZ. A range of protective actions to protect onsite personnel during hostile action is provided to ensure the continued ability to safely shut down the reactor and perform the functions of the emergency plan 6-5

GG Revision 80 FSAR 02 / 2020 6.5.1 Protective Cover, Evacuation, Personnel Accountability

a. Grand Gulf Nuclear Station
1. When an Alert, Site Area Emergency or General Emergency is declared, all personnel in the protected area are advised of the emergency classification by use of the public address system. If a site evacuation is ordered, the evacuation siren is sounded over the public address system in the protected area followed by an evacuation announcement and any special instructions. Non-essential personnel will evacuate immediately upon being notified.
2. Emergency personnel not assigned to the Control Room, Technical Support Center, Central Alarm Station, and Secondary Alarm Station, report to the Operations Support Center for accountability.

Non-emergency personnel are accounted for as they exit the protected area through Security Island. GGNS Security is responsible for performing an accountability survey of personnel in the protected area. It is anticipated that accountability and identification of missing persons can be accomplished in approximately: 30 minutes. This information is reported to the Emergency Plant Manager.

3. GGNS employees. contract personnel and visitors outside of the Protected Area but within the Emergency Preparedness Owner Controlled Area are notified promptly of a site evacuation and given instructions by public address systems, telephone or security personnel equipped with portable PA systems. Non-essential personnel will evacuate immediately upon being notified. GGNS Security checks to ensure that all persons located in the Emergency Preparedness Owner Controlled Area were notified and evacuated as directed and report the results to the Emergency Plant Manager.

Security will complete the checks as soon as possible but not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> under most conditions.

4. Persons outside the Emergency Preparedness Owner Controlled Area but in public access areas or passing through the site are notified of an emergency classification by the Alert Notification System activated by local authorities.

6-6

GG Revision 80 FSAR 02 / 2020

5. All site personnel are trained on site evacuation routes, escorted someone who has been trained or receive a map which gives instructions and routes off of the site. Site evacuation instructions and routes are specified in the evacuation announcement Non-essential personnel are expected to evacuate GGNS property in the same vehicles which were used for initial access.
6. Emergency situations. as discussed in this section include natural events as well as radiological incidents. The procedures to be followed in these evacuations are included in the Emergency Plan Procedures. Provisions are made for consideration of weather conditions. traffic or radiological impediments to evacuation.
b. Offsite Areas The administration of protective actions for persons residing offsite is the responsibility of the States of Mississippi and Louisiana. Mississippi's responsibility is outlined in the "Mississippi Emergency Operations Plan" and Louisiana's responsibility is outlined in the "Louisiana Peacetime Radiological Response Plan." These plans are implemented in addition to the county or parish emergency plans. The county and parish within the 10-mile EPZ surrounding the Station are responsible for developing and submitting emergency plans which are coordinated with those of the States and Station. GGNS provides protective action recommendations to the state/local civil defense agencies. The minimum standard PAR for a General Emergency is to evacuate the 2 mile radius and 5 miles downwind, monitor and prepare the remainder of the 10 mile EPZ, and consideration of the use of potassium iodide in accordance with State Plans. (Source : NU REG 0654 FEMA Rep 1, Rev 1, Supplement 3 "Guidance for Protective Action Strategies".) Evacuation will be recommended for 5 -10 miles in the downwind sectors, if dose projections or actual field measurements correspond to radiation levels to the public that exceed the EPA Protective Action Guides (PAG's). Sheltering may be recommended instead of evacuation when appropriate. Recommendations are based upon emergency classification and projected dose to the public and are consistent with EPA PAGs and FDA guidance. The Protective Actions Guides are summarized in Table 6-1. The methodology normally used for determining appropriate protective action recommendations is described in the Emergency Plan Procedures. Warning and/or advising the population-at-risk of an impending emergency is the responsibility of the counties or parishes affected. These counties or parishes are also 6-7

GG Revision 80 FSAR 02 / 2020 responsible for the preparation and dissemination of informational material concerning protective actions for the general public. Written messages for emergency dissemination to the public have been prepared by the State of Mississippi with supporting information provided by GGNS.

These prepared messages are documented in the Mississippi Emergency Operations Plan. Volume II. Part 3, Radiological Emergency Response Plan.

Appendix 1 to Annex G - Public Information. Figure 2-5 shows the evacuation centers within the SO-mile EPZ.

6.6 Contamination Control Measures A monitoring and decontamination station is established at the Emergency Operations facility (EOF) when directed by the Emergency Director. Emergency Organization personnel perform monitoring and decontamination in accordance with plant procedures.

When a site evacuation is ordered, non-essential personnel will be routed. as necessary to evacuation/decontamination centers established by the state/local governments.

Onsite contamination control measures are implemented in Plant Administrative Procedures and other lower level procedures. Plant procedures are designed to meet the requirements of 10CFR20. Appendix B.

Contamination control for offsite areas is provided for by the States of Mississippi and Louisiana Guidelines are provided through the emergency response plans of those two states.

6. 7 Aid to Affected Personnel This section of the plan describes measures which are used to provide necessary assistance if individuals are injured and/or radiologically exposed or contaminated.

6-8

GG Revision 80 FSAR 02 / 2020 6.7.1 Emergency Personnel Exposure Although an emergency situation transcends the normal requirements for limiting exposure, there are suggested levels of exposure acceptable in emergencies.

Three categories of risk versus benefit must be considered:

a. Saving of human life and reduction of injury
b. Protection of health and safety of the public and
c. Protection of property In certain emergency situations, the acceptance of above normal radiation exposure may be warranted.

The following are exposure guidelines for individuals inclusive of support personnel and Entergy employees:

a. Support personnel are restricted to GGNS administrative limits and are equipped with appropriate dosimetry. In situations where it appears that the administrative limits may be exceeded, the individuals are relieved of duties involving additional radiation exposure .
b. Guidance for Emergency worker exposure is given in the following table, which represents t hose extensions of GGNS administrative exposure limits for which authorization . by the Emergency Director or Emergency Plant Manager is required prior to the exposure being received:

Guidance on Dose Limits for Workers Performing Emergency Services DOSE LIMITS ACTIVITY CONDITIONS (TEDE)

> 5 up to 10 Rem Protecting Valuable Property Lower dose not practicable Lifesaving or Protection of large

> 10 up to 25 Rem Lower dose not practicable populations Lifesaving or Protection of large Only on a voluntary basis to persons

> 25 Rem populations fully aware of the risks involved Source: EPA 400-R-92-001 "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents" Table 2-2 Provisions have been made for 24-hour-per-day capability to determine the doses received by emergency personnel. Specific emergency procedures have been written for the issuance of permanent record dosimetry devices (or systems) and 6-9

GG Revision 80 FSAR 02 / 2020 self-reading dosimeters to emergency personnel. These procedures also provide instructions on how often to read dosimeters and keeping appropriate dose records.

The Emergency Director or Emergency Plant Manager may also authorize the use of radioprotective drugs for thyroid protection. Emergency personnel would take a pre-measured dose of the drug (such as Kl tablets). These drugs are made available in the Control Room, Operations Support Center, Technical Support Center, Emergency Operations Facility, and the RCA entrance.

6.7.2 Decontamination and First Aid Onsite personnel decontamination stations for emergency conditions are fully equipped with decontamination material and portable first aid kits. The primary decontamination center is located on the 133 foot level of the Unit II Turbine Building in the Radiation Protection Access Control Area. Alternate facilities are the showers in the Maintenance Shop {adjacent to the Administration Building) or EOF. The decontamination centers have provisions for disrobing, collecting contaminated clothing, showering of contaminated personnel, and clean clothing.

All personnel exiting from the controlled access area at Grand Gulf are monitored for contamination. The instruments used for this monitoring procedure are portal monitors and portable contamination survey instruments.

In situations when the portal monitors and/or the portable contamination survey instruments detect contamination, preventive measures must be initiated to mitigate the possibility of the spread of contamination.

The most effective measure for the decontamination of the hands and other parts of the body is thorough washing of the affected areas. A member of the Health Physics Section is to supervise any decontamination effort.

First Aid Courses are conducted for selected members of the Emergency Organization. Personnel trained in first aid/CPR are available on each shift to administer first aid as required.

6.7.3 Medical Transportation Transportation of injured persons from GGNS to the medical facility is normally provided by regional ambulance service in accordance with Letter(s) of Agreement (See Appendix D). In the event that these services are unavailable, provisions are 6-10

GG Revision 80 FSAR 02 / 2020 in place to transport injured persons in company owned or private vehicles.

Ambulance service can be requested by the local hospitals or GGNS. The ambulance maintains radio communications with the hospital while in transit GGNS uses telephone communication to contact the hospital, thereby maintaining indirect communications with the ambulance.

6.7.4 Medical Treatment In the event of a serious accident at Grand Gulf requiring medical treatment, Claiborne County Medical Center has agreed to provide the required assistance.

The hospital is equipped to handle contaminated injuries as well as injuries not related to contamination or over exposure. The River Region Medical Center and the Claiborne County Medical Center have emergency plans for the decontamination and treatment of the radioactively contaminated patient.

Appendix B includes a list of typical equipment located at the hospitals.

River Region Medical Center and The Ochsner Clinic provide backup medical services if the Claiborne County Medical Center is unable to provide the required services. Letters of Agreement (Appendix D) have been obtained to document these arrangements.

6-11

GG Revision 80 FSAR 02 / 2020 Table 6-1: Protective Actions Guides for the Early Phase of a Nuclear Incident 1

Projected Dose Protective Action Recommendation Or Classification

  • TEDE 1,000 to 5,000 mRem
  • Evacuation
  • CDE (Thyroid) 5,000 to 25,000 mRem
  • Sheltering may be considered if benefit
  • SDE (Skin Dose) 50,000 to 250,000 outweighs 'cost' of evacuation mRem
  • Sheltering up to 10,000 mRem may be justified for special populations
  • General Emergency Classification
  • Consider prophylactic use of potassium iodide in accordance with State Plan Note I - Dose that can be avoided if the protective action is implemented.

Source:

1) EPA 400-R-92-001 "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents" Table 2-1
2) Food and Drug Administration Guidance, December 2001, "Potassium Iodide as a Thyroid Blocking Agent in Radiation Emergencies" 6-12

GG Revision 80 FSAR 02 / 2020 Figure 6-1: Figure Deleted 6-13

GG Revision 80 FSAR 02 / 2020 Figure 6-2: Example of the GGNS Emergency Notification Form EMERGENCY NOTIACA TION FORM I 7i!S IS GP.AND C-ULF NUCLEA.'t STATION 'rlffii MESSAGE l'.'1.JME:F.

- A TME CATE I 6 CCMMUNICATQR C TEL MO eo1-437.

! EMERGENCY CLASSIFICATION:

A :::J 1,IOTIFIU..TION OF L,'JUSlJi".L E'IENT C. :::J SIT: i',.P.:A EME.=tG:r,c*, E. :::J TERMI 'Ji',.T:D s :::I.ALERT D GENE.",;>!. EMERGENCY 4 CURRENT EMERGENCY CLASSIFICATION  :::J DECLJ..PATiCI', TIME. DATE-_ _ _

J TEFJ,Ul*lATrON ilVE 5 RECOI.VdENDED PROTECTIVE ACTIONS:

DATE A :::J No Protecl!V: A..--tior.s Reccrr,r,:11~ /.i Tni= Time ({;j to it;;ni 31 s  :::J Consid:f Ur- of i'otassium lodi:ie in accoolance ,~th ~1=..e Plans

/.ND EVACUATE ALL sector.; to 2 mles. EV;..CL1ATE :se:tcr. _ _ _ to 5 mil:s

~

MONITOR /.ND PREP/1.P.E ti:e rerrairr.ier cf the 10 rri le EPZ l\ltr the exception of are:a. ;:revio,.:s.'f recorrrr.e,,..,..ed fc< :Yacuticn C.  :::J Cons1tl:f use of r'olassium lodx!e in ao::oo:Jance 1,itn ~1=.:e Plans

/.J.'D EVACUATE ALL s:-::tor. :o 2 rriles. EVACUATE S£C:or.

/.ND --- to 10 mies MC.\TTOR /IND PREPARE the remar.der of the I rril!!! EPZ l\ith :I"-= ,;xceptio,, of ar->..n pl":lli:<isly ~:ommerded fer evac-Jabon D Cons1CE:r L!9- of ?otass'\lm loifue *n ao~an::e '"tn S~:e Plans ;,,4td She:t~r

~ a EAL#:

e b INCIDENT DESCRIPTION,'UPOATEICOMMENTS 7 REACTOR SHUTDOWN?  :::J 'IC  :::J \'E3 TIIVE. DATE.

g METEROLOGICAL DATA. :::J NOT AVAJL.A:LE AT THIS T1ME !Go to :em 9i

~,'OTE* JI not ;v;da/JI.! is mall<ed Met D.ita sh~ he IJf':!*~ as soon i!5 =sibie on a rc,*,~~i-'J:; N!Xiifcaflcn Fenn A ',\IND DIREC7CN FROM ~re=,_; at MPH 3 SECTORS AFFECTED (A-RI C STAEILITY Cl.ASS (A-G)

D PRECIFITATION None CP.u OS~ D!:nmv Hail D Ctrer ii RELEASE INFORMATION:

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GG Revision 80 FSAR 02 / 2020 7 EMERGENCY RESPONSE FACILITIES AND EQUIPMENT 7.1 Facilities and Equipment Emergency planning requires the preinstallation of both facilities and equipment that allows the emergency organization to perform the following actions:

a. Assess the extent of the emergency
b. Perform the proper corrective actions to mitigate the effects of the emergency
c. Perform actions to protect onsite and offsite personnel
d. Provide information to offsite support agencies
e. Perform the proper recovery actions Emergency facilities have been established by GGNS and offsite support agencies. Figure 7-1 identifies these facilities and their locations.
7. 2 Control Room The Control Room contains those controls, instruments and communications equipment necessary for operation of the, plant under both normal and emergency conditions. The ventilation system, shielding, and structural integrity are designed and built to permit continuous occupancy during postulated accidents. During emergencies, the Control Room will provide for the classification, accident assessment, notification, and dose assessment function if these functions are unavailable at the EOF or when being relocated to the Backup EOF.

7.3 Emergency Response Facilities 7.3.1 Technical Support Center (TSC)

The Technical Support Center (Figure 7-2) provides an area outside the Control Room that can accommodate management, engineering personnel and the NRC acting in support of the command and control function during emergency conditions and the emergency recovery operations. The TSC personnel primarily assist in accident assessment, provide advice to the control room and communicate with Emergency Operations Facility (EOF) personnel regarding plant conditions and actions Communications are also provided with the Control Room and OSC.

The TSC area contains approximately 2,250 square feet The TSC area is large enough to accommodate 25 people, including five NRC personnel, as well as furnishings, data 7-1

GG Revision 80 FSAR 02 / 2020 displays, plant reference material, and communications equipment. The TSC is located directly above and overlooking the Control Room on the mezzanine level (EL 177') of the control building. The control building which houses the TSC is designed Safety Class 3.

The control building structure is seismic Category 1 and is designed to withstand tornadoes and extreme wind phenomena. The TSC is habitable to the same degree as the Control Room for all postulated accident conditions and is served by the Control Room ventilation system. The Backup TSC is located in the Maintenance & Engineering Building.

Emergency lighting is powered by the ESF AC buses, with backup emergency lighting provided by battery pack lighting units.

The TSC may be activated ac any time and shall be activated at an Alert Sire Area Emergency, or General Emergency. Once activated the TSC shall become operational as soon as possible (without delay) after declaration of any of these emergency classifications. When facility staffing can be accomplished with onsite personnel, it is the goal to become operational within 45 minutes. Otherwise offsite personnel shall provide shift augmentation in 75 minutes and be fully operational in 90 minutes.

A set of drawings and other records are accessible to the TSC personnel under emergency conditions. The documents include but are not limited to: Plant Technical Specifications, Plant Operating Procedures. Emergency Operating Procedures, and hard copies (stick file) of P&ID's, architectural, electrical one lines, electrical schematics, logic diagrams, and loop diagrams. Radiation Control and Chemistry procedures to be used during an emergency situation are also available.

A Plant Display System (PDS) and a Safety Parameter Display System (SPDS) are provided to supply data which enable TSC personnel to evaluate the status of the plant and radiological and meteorological conditions. Status boards are used to display data needed in the TSC to analyze plant conditions.

A computer based system designed to provide atmospheric dispersion and radiological dose assessments of radioactive materials released from GGNS during emergency conditions is available 7-2

GG Revision 80 FSAR 02 / 2020 7.3.2 Operations Support Center (OSC)

The OSC {Figure 7-3 ) provides an area for operations, maintenance, health physics, and chemistry personnel to assemble and be assigned to duties in support of emergency operations.

The location of the OSC is the Maintenance Shop of the GGNS Administration Building.

In addition, an in-plant staging area is located at the Radiation Protection Access Control Area of the Unit II Turbine Building to which certain individuals are assigned in the event of an emergency. Other shift personnel and additional support personnel assemble at the OSC to provide assistance as necessary. A radio control console located in the maintenance area provides communications with the Control Room, TSC and EOF.

The OSC is required to be activated at the declaration of an Alert, Site Area Emergency, and General Emergency. Once activated, the OSC shall become operational as soon as possible (without delay) after declaration of any of these emergency classifications.

When facility staffing can be accomplished with onsite personnel, it is the goal to become operational within 45 minutes. The backup OSC is located in the Control Building (Elevation 148').

7.3 .3 Emergency Operations Facility {EOF)

The EOF {Figures, 7-4 and 7-5) provides a location from which evaluation and coordination of all licensee activities related to an emergency is carried out. The EOF has the capability to obtain and display plant data and radiological information. The facility provides classification, accident assessment, notification, dose assessment, information to offsite groups, assesses the impact of the emergency offsite and provides the necessary support to assist the Emergency Organization.

The location for the EOF is in the Energy Services Center approximately 0.6 miles from the GGNS site. Figure 7-6 indicates the location of the EOF in relation to the plant. The EOF has a protection factor of 50 and its own ventilation system. The EOF contains the key technical personnel of the Emergency Organization. Space and communications are provided for federal, State, and local representatives at the EOF. The EOF provides a base of operation for Offsite' Monitoring Teams and is the central point for the receipt of field monitoring data.

The EOF may be activated at any time, and shall be activated at an Alert, Site Area Emergency, and General Emergency declaration. Once activated, the EOF shall become operational as soon as possible (without delay) after declaration of any of these 7-3

GG Revision 80 FSAR 02 / 2020 emergency classifications. When facility staffing can be accomplished with onsite personnel, it is the goal to become operational within 45 minutes. Otherwise offsite personnel shall provide shift augmentation in 75 minutes and be fully operational in 90 minutes.

7.3.4 Backup Emergency Operations Facility (BEOF)

The BEOF (Figure 7-7) is located at the Entergy Mississippi Baxter Wilson Steam Electric Station in Vicksburg, MS. In the unlikely event that the EOF had to be evacuated, the key EOF personnel evacuate the area arid relocate to the BEOF in accordance with Emergency Plan Procedure EN-EP-609. The BEOF is seventeen miles from the reactor. It is outside the ten mile EPZ but close enough to that responders can travel quickly to the site when it is deemed accessible by appropriate authorities.

The Control Room is notified of the situation and certain emergency response functions are transferred to the Control Room upon deactivation of the EOF. Once activated, the BEOF establishes communications with the Control Room.

The BEOF contains the following:

  • Communications equipment that allows contacting the other Emergency Response Facilities, Federal, State and local officials as well as the capability of making Emergency Notifications.
  • Equipment necessary to perform radiological assessment and communicate with field monitoring teams.
  • Capability to access plant drawings and procedures and computer links to the site.
  • Capability to access plant data systems and perform event classification.

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GG Revision 80 FSAR 02 / 2020 7.3.5 Media Centers GGNS utilizes the Joint Information Center (JIC) in Pearl Mississippi as an information center during an emergency. The Joint Information Center (Figure 7-9) is the principle location for disseminating intonation about the emergency, arranges for timely exchange of information among designated GGNS, state, local, and federal spokespersons, media monitoring activities, responding to public and media inquiries during emergencies and performing rumor control function. Press conferences are held periodically, and equipment and facilities are available to support timely communication and information dissemination concerning plant conditions.

The Joint Information Center is activated at an Alert, Site Area Emergency and General Emergency.

7.3.6 Alternate Facilities In the event that primary and back-up facilities are unavailable at GGNS there is an alternate facility available for the ERO

a. The Muster/Staging area is located at the Baxter Wilson Steam Electric Station (BWSES) in Vicksburg, Mississippi approximately 17 miles from Grand Gulf. This facility, which is co-located with the BEOF, is intended to host GGNS personnel, ERO, Security, RP etc., while preparing for reentry to the plant.
b. The Alternate TSC is located next to the Staging/Muster area at BWSES in the Vicksburg Area Engineering Office. This office building has phones, a copier, a FAX and various computers, plotters and printers available.

7.4 County and State Emergency Centers 7.4.1 Claiborne County Emergency Operations Center The Claiborne County Emergency Operations Center is located in the Port Gibson/Claiborne County Civil Defense Office in Port Gibson. The center is equipped with communications to the Control Room, TSC, EOF, the State Emergency Operations Center in Jackson and State supporting agencies. Functionally, the center coordinates all local emergency operations.

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GG Revision 80 FSAR 02 / 2020 7.4.2 Mississippi State Emergency Operations Center The State Emergency Operations Center (EOC) is located in Pearl Mississippi, approximately 60 miles from the site. The center has supplies and equipment to support state emergency operations activities, including communication links with other emergency operations centers. During an emergency, representatives from appropriate state agencies and GGNS assemble in the State EOC to coordinate response efforts.

7.4.3 Tensas Parish Emergency Operations Center The Tensas Parish Emergency Operations Center is located adjacent to the Tensas Parish Sheriff's Office.

The center is equipped with communications to the Technical Support Center, Control Room, Emergency Operations facility, Mississippi State Emergency Operations Center, the Louisiana State Emergency Operations Center (in Baton Rouge) and with Louisiana state supporting agencies. Functionally, the Tensas Parish EOC acts in parallel to the Claiborne County, Mississippi EOC and coordinate local emergency operations.

7.4.4 Louisiana State Emergency Operations Center The LDEQ and GOHSEP representatives report to the Louisiana Emergency Operations Center in Baton Rouge, approximately 125 miles from the site.

In the event of a nuclear emergency which requires activation of State resources. The center has equipment and supplies to support state emergency operations activities including communications links with other emergency centers.

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GG Revision 80 FSAR 02 / 2020 7.5 Communications Systems The communications systems are designed to ensure the reliable, timely flow of information and action directives between oil parties having jurisdiction and a role to play in the mitigation of emergencies at GGNS. Reliability is provided via (I) extensive redundancy, (2) dedicated communication equipment to preclude delays due to system overload, and (3) routine use and testing of many of the systems, which lowers the probability of undetected system failures.

Timeliness of information flow is achieved by (I) prompt notification, (2) redefined lines of communications, (3) predefined emergency action levels and (4) predefined levels of authority and responsibility. The GGNS communications network is formulated around this basic concept and is designed to channel information directly to the key parties having closely related functions, thus elim inating errors often associated with second hand information. By providing well defined and dedicated communications links, better accident management from physically separate control and support centers can be achieved. Provisions are made for State representatives to call and verify the authenticity of the accident and obtain additional information. The essential communications links are manned continuously and are periodically tested to assure availabil ity. Figure 7-12 shows the communications interfaces between the onsite and offsite emergency facilities.

7.5.1 Telephone System GGNS maintains telephone communication with the entire Entergy Corporation system via a Company-owned fiber-optic transmission system. Access to this mode of transmission is made via the plant telephone system. The GGNS plant telephone system also provides communications among the CR, TSC, OSC. EOF, JIC and public.

7.5.2 Plant Paging System & Sound Powered Phones The plant paging system links together permanent plant structures, including the TSC and OSC, through a network of phone stations and speakers. Sound powered phones are provided in the TSC and OSC to enable direct communication with the Control Room and all areas of the plant containing sound powered outlet boxes. Amplified headsets are provided in high noise areas to ensure adequate communications capability with the Control Room.

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GG Revision 80 FSAR 02 / 2020 7.5.3 Emergency Communications Equipment

a. Dedicated Communication Links The following dedicated telephone and/or system links are established to provide a continuous (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) means of communication during an emergency situation.
1. GGNS ORO Notification System: An internet based notification system to connect the facilities listed in Table 7-1. The GGNS ORO Notification System is used for initial notification and ongoing communications to the locations listed in Table 7-1 for the duration of the emergency. Utilization of this system by GGNS activates the emergency response network by notifying each location simultaneously. The GGNS Operational Hotline (OHL) is used as a back-up to the ORO Notification System.
2. NRC Emergency Telecommunication System: Consists of the following dedicated Federal Telephone System circuits to provide direct communication with the NRC Operations Center, Bethesda, MD:
a. Emergency Notification System (ENS): Is used to provide initial notification to, and ongoing communication with, NRC personnel in an emergency. The ENS is available in the Control Room. TSC, and EOF.
b. Health Physics Network (HPN): Is used to provide requested radiological data to the NRC in an emergency. The HPN is available in the TSC and EOF.
c. Reactor Safety Counterpart Link (RSCL): Is used by the NRC Site team and NRC Base Team to conduct internal NRC discussions on plant parameters without interfering with exchange of information between GGNS and NRC. This link may be used for discussions with the NRC Reactor Safety personnel and GGNS plant Management. The RSCL is available in the TSC and EOF.

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GG Revision 80 FSAR 02 / 2020

d. Protective Measures Counterpart Link (PMCL): Is used by the NRC Site team and NRC Base Team to conduct internal NRC discussions on radiological releases and meteorological conditions, and the need for protective actions without interfering with the exchange of information between GGNS and NRC. This link may also be used for discussions with NRC Protective Measures personnel and GGNS plant management. The PMCL is available in the TSC and EOF.
e. Emergency Response Data System (ERDS): Is used to transmit raw reactor parametric data from GGNS balance of plant computer to the NRC Operations Center. The ERDS is activated by GGNS at an Alert or higher declaration. The ERDS is available in the GGNS Control Room.
f. Management Counterpart Link (MCL): Is used for any internal discussion between NRC Executive Team Director and NRC Director of Site Operations or GGNS site management. The MCL is available in the TSC and EOF.
g. Operational Counterpart Link (OCL) or Local Area Network (LAN)

Access: Is used by the NRC Base Team and NRC Site Team to access products and services provided on the NRC Operations Center's local area network. The OCL is available in the TSC and EOF.

3. The GGNS Computerized Emergency Notification System is used to notify GGNS emergency response personnel upon declaration of an emergency.
a. The GGNS Computer Notification System is a hosted system that is a robust notification system that allows the ERO to be notified via a number of modalities (i.e. telephone, pager, SMS text, email, etc.) This system utilizes two data centers for all its productions systems in an Active-Active configuration. Data is continuously replicated between the two separate sites, and each site is capable of providing a full range of services. If service is disrupted at either site, all traffic is dynamically rerouted to the other site so that systems remain constantly available.
b. The GGNS Computer Notification System is activated 7-9

GG Revision 80 FSAR 02 I 2020 using any internet connected computer or touch tone telephone.

Use of a password guards against unintended activation. The password is readily available to the control room operating staff.

c. The GGNS Computer Notification System can be activated for any emergency classification. On call or alternate emergency response personnel will be notified to fill required response positions.
b. UHF Radios
1. Radios to connect the following facilities:
a. Control Room/TSC/EOF/CAS/SAS
b. Tensas Parish Sheriff Department
c. Claiborne County Sheriff Department The above mentioned UHF radio system serves as an alternate means of communications to notify local authorities of an emergency at GGNS.
2. UHF radios connect the Onsite and Offsite Monitoring Teams with the OSC and EOF respectively.
3. UFH radios are issued to OSC Emergency Response Team to connect them to the OSC.
c. Alarms A number of warning devices are used onsite to indicate unsafe or emergency conditions.
1. Local lnplant Radiation Alarms.
2. Fire Alarm.
3. Site Evacuation Alarm.

7.5.4 Alert Notification System An Alert Notification System has been provided that meets the design objectives of NU REG 0654, Appendix 3. The basic system consists of 43 sirens located in Claiborne County and Tensas Parish. Institutions located in the 10-mile EPZ are supplied with tone activated receivers which supplement the siren system. Port Gibson/Claiborne County 7-10

GG Revision 80 FSAR 02 I 2020 Civil Defense and Tensas Parish Office of Homeland Security and Emergency Preparedness are responsible for activating the portion of the system within their respective jurisdictions. In the event of a failure of the Alert Notification System the EPZ population will be notified by route alerting in accordance with state emergency plans.

Additional alert notification details are addressed in local and state emergency plans, the GGNS Emergency Preparedness Public Information website and mobile application and the Alert Notification System Final Report Figure 7-13 indicates the siren locations for the 10-mile EPZ.

As discussed in Section 8.7, an effort is made to provide information to the transient population concerning protective measures. The means of notifying the transient population is the Alert Notification System.

7.6 Assessment Facilities 7.6.1 Onsite Systems and Equipment

a. Control Room Parameters Appropriate parameters indicative of the status of the reactor and various plant systems are displayed in the control room. The safety related control room display instrumentation that can be used to assess the condition of the plant is discussed in GGNS FSAR Section 7.5.

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GG Revision 80 FSAR 02 / 2020

b. Area Radiation Monitoring System The area radiation monitoring system detects and measures gamma radiation levels at various locations. It also provides audible and visual alarms in areas monitored and in the control room, if gamma radiation exceeds a specified limit It provides visual indication in the area monitored and at a control room annunciator if there is a malfunction in any area monitor.

The containment area radiation monitors also provide information that can be used to determine the source term of a fission product release in the containment. An Emergency Plan Procedure contains guidance for the conversion of containment area radiation monitor readings in mR/hr or R/hr to offsite exposure.

Each area radiation monitoring channel consists of a detector and a local alarm unit at a remote location and an indicator and trip unit in the control room. A control room channel is provided with a detector in the control room. The area radiation monitor provided in the control room has no local alarm unit since the control room annunciator system provides alarms to the operators.

The following general areas are monitored by the Area Radiation Monitoring System:

1. Control Room
2. Radwaste building
3. Auxiliary building
4. Fuel storage and handling area
5. Various valve operating stations
6. Containment
7. Drywell
8. Various Sampling rooms
9. Turbine building
10. Radwaste Solidification Areas 7-12

GG Revision 80 FSAR 02 I 2020 C. Process and Effluent Radiation Monitoring Systems.

The main objective of required radiation monitoring systems is to initiate appropriate protective action to limit the potential release of radioactive materials from the primary and secondary containment if predetermined radiation levels are exceeded in major process/effluent streams. An additional objective is to have radiation monitoring systems available during all operating and emergency conditions to provide control room personnel with an indication of the radiation levels in the major process/effluent streams and alarm annunciators if high radiation levels are detected.

Certain effluent radiation monitoring systems also provide information that can be used to determine the source term of an unplanned radioactive release. They are used to correlate the activity levels in an effluent stream along with system flow rates to determine release rates in Ci/sec. Using the determined release rates and the appropriate meteorological stability class., radiation dose projections can be estimated for various distances from the site.

Emergency Plan Procedures include guidance for the determination of release rates and dose projections when the effluent monitors are off scale or inoperable.

The radiation monitoring systems (RMS) provided to meet these objectives are:

1. Main Steam Line RMS
2. Containment and Drywell Ventilation Exhaust RMS
3. Auxiliary Building Fuel Handling Area Ventilation Exhaust RMS
4. Auxiliary Building Fuel Handling Area Pool Sweep Exhaust RMS
5. Turbine Building Ventilation Exhaust RMS
6. Radwaste Building Ventilation Exhaust RMS
7. Standby Gas Treatment System RMS 7-13

GG Revision 80 FSAR 02 / 2020

d. Fire Protection The fire protection system consists of an outside yard loop with three fire pumps and one jockey fire pump, hydrants, sprinkler systems, deluge CO2 systems, Halon systems, standpipe hose stations, portable fire extinguishers, ionization smoke detectors, heat sensors, alarm systems, fire barriers, two fire water storage tanks and associated piping, valves and instrumentation.

Three redundant 50 percent capacity pumps (1 electric and 2 diesel driven) and closed-loop piping ensure delivery of extinguishing water with one pump and one leg of the piping loop out of service.

Fire and smoke detection systems are provided for the switchgear areas, battery rooms, control room, cable penetration areas, and other areas, based on the results of the fire hazards analysis included in the FSAR. In addition, a GGNS-owned fire truck is maintained onsite. The fire truck may be taken offsite for various reasons (i.e. training, vehicle maintenance, etc.).

e. Geophysical Monitoring
1. Seismic Monitoring Activation of any accelerometer causes an audible and visual annunciation in the control room to alert the plant operator that an earthquake has occurred. This annunciation is set to occur at 0.01 g vertical acceleration in the Horizontal or Vertical directions as detected at the Containment Base mat or Drywell and may include other areas as determined by system requirements. The accelerometers trigger the initiation of the strong-motion accelerometers recording system at horizontal or vertical acceleration levels slightly higher than the expected background level, including induced vibrations from sources such as traffic, elevators, people, and machinery.

System equipment includes:

a. Six triaxial time/history strong-motion accelerometers (SMA)
b. Seven triaxial peak-recording accelerographs
c. Recording and playback equipment 7-14

GG Revision 80 FSAR 02 / 2020 A cabinet located in the Control Room houses the recording, and calibration unit that is used in conjunction with the SMA sensors to produce a playback record of the earthquake. It also contains the audible and visual annunciators wired to display initiation of the time/history recorder, and the power supply components for all equipment contained within the cabinet and in the field. Equipment is installed in the cabinet for data analysis.

Should the GGNS seismic monitoring system fail, backup seismic information would be obtained through a coordinated effort with the Mississippi Bureau of Geology. That agency receives seismic information from Memphis. Tennessee, Panola County, Mississippi, and Mobile, Alabama. The Mississippi Bureau of Geology would be requested lo obtain real-time seismic information und to relay this information by telephone to GGNS. Although these seismic monitoring stations are located some distance from GGNS, because of the sophistication of the detection equipment, they should be able to keep the GGNS site informed of any seismic activity within the state of Mississippi.

2. Meteorological Monitors The onsite meteorological tower, located approximately 5,300 feet northwest of the control building, is 162 feet high and has the following instruments installed:

Surface Tipping bucket rain gauge Delta Temperature translator (utilizes 33 and 162 foot tempera t ure sensors) 33 feet Wind speed sensor Wind direction sensor Temperature sensor Relative Humidity 162 feet Wind speed sensor Wind direction sensor Temperature sensor The meteorological system utilizes local digital storage modules and Plant Data System digital storage.

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GG Revision 80 FSAR 02 / 2020 GGNS also utilizes a back-up meteorological system which provides meteorological information to the control room, if the primary meteorological system fails. The instrumentation on the backup system is listed below:

33 feet Wind speed sensor Wind direction sensor Temperature sensor In the unlikely event that both the primary and backup meteorological systems were inoperable, the tertiary means of obtaining wind speed and direction data would be through the National Weather Service or the U.S.

Corps of Engineers, Waterways Experiment Station.

An Uninterruptible Power Supply {UPS) is utilized to power the meteorological system instrumentation and components to ensure that a 90% data recovery is achieved. All components of the UPS/Back- up Power Supply are located at the Meteorological Station.

f. Hydrological Monitors A groundwater level monitoring program is established to provide data on the seasonal fluctuations of the regional groundwater operations to define the zone of depression caused by plant pumping operations and to monitor the level of the perched groundwater table at the plant site. In the event that GGNS personnel were unable to conduct the hydrological sampling program, this information could be supplied by the U.S.

Geological Survey, which monitors groundwater levels in the town of Port Gibson.

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GG Revision 80 FSAR 02 / 2020

g. In-Plant Airborne Iodine Monitoring In reference to Section 7.6.3.1 of GGNS Technical Requirements Manual, a program is established which ensures the capability to accurately determine, the airborne iodine concentration in vital areas under accident conditions. This program includes the following:
1. Training of personnel
2. Procedures for Monitoring, and
3. Provisions for maintenance of sampling and analysis equipment.

7.6.2 Offsite Monitoring Equipment and Facilities GGNS has been conducting and continues to conduct an environmental radiological monitoring program for the Station.

The ongoing objectives of the program are:

a. To determine whether any statistically significant increase occurs in the concentration of radionuclides in critical pathways.
b. To detect any buildup of long-lived radionuclides in the environment.
c. To detect any change in ambient gamma radiation levels.
d. To verify that radioactive releases are within allowable limits and that plant operations have no detrimental effect on the health and safety of the public or on the environment.
e. To fulfill the radiological environmental surveillance requirements of the GGNS Technical Specifications.

The monitoring program provides the following: (1) the gathering of data on environmental radiation levels and the Station's degree of influence on these levels; (2) checks for specific radioisotopes to detect their introduction into the surroundings; (3) a background for a continually developing program of radiological assessment.

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GG Revision 80 FSAR 02 I 2020 Ambient radiation is measured by dosimeters of legal record (DLR). These DLRs are installed at various onsite and offsite locations. The locations have been selected based on available meteorological data, prevailing wind direction and population concentration. During normal operating conditions, quarterly measurements of the environmental dose rates are made. During an emergency, incremental and time integrated dose measurements can be made by selective and periodic changing of DLRs.

The locations of existing environmental monitoring stations are given in the GGNS Technical Requirements Manual. Environmental monitoring stations have been located to ensure compliance with the NRC Radiological Assessment Branch Technical Positions for the Environmental Radiological Surveillance Program.

7.6.3 Radiological Assessment Laboratories The GGNS Chemistry Department has isotopic analysis capability available for onsite radiological analysis.

The Mississippi State Department of Health Laboratory, located in Jackson, MS, would be setup to receive samples in the event of a Site Area Emergency or General Emergency. They could be expected to be ready within 1 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of notification. This laboratory has the capability to measure beta-gamma emitters, including radioiodine in environmental samples (soil, vegetation, water, and air). Data from this laboratory may be provided to each agency's representative in the Emergency Operations Facility by radio communications established by each agency or by normal phone communications with the Mississippi State Department of Health or Louisiana Department of Environmental Quality. Additional mobile laboratories with similar capabilities are available from DOE, Region 111, Oak Ridge, TN (estimated response time 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) and EPA, Region IV, Montgomery, AL (estimated response time 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />).

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GG Revision 80 FSAR 02 I 2020 7.6.4 Post-Accident Sampling Capability Through the use of installed emergency sampling equipment. measurements and analysis can be performed onsite to assess the magnitude of the radiological hazards associated with an emergency condition. Specifically, a system is installed to obtain samples from the following locations:

a. RHR A and B
b. Containment Atmosphere
c. Suppression Pool The offsite radiation monitoring teams have the capability to determine the extent of the radiological hazard in the environment. Environmental air samplers and portable equipment are available for the following assessment in the field within the 10-mile EPZ:
a. Beta-gamma radiation from the plume and/or ground contamination.
b. Iodine concentration and assessment of inhalation and thyroid dose by using air samplers with iodine specific cartridges and portable and fixed analyzers. The technique to be used to determine radioiodine concentrations in a radioactive plume is described in Emergency Plan Procedures. This technique allows the determination of radioiodine concentrations in the field with a minimum detectable activity of 1 x 10-7 uCi/cc in the presence of interfering noble gases and background radiation.
c. Water sampling for later analysis to assess contamination due to liquid release pathways can also be done by offsite monitoring teams.

The offsite monitoring teams dispatched from GGNS consist of 2 members.

Transportation is available using designated GGNS vehicles. with normal deployment expected to be within approximately 90 minutes following notification.

Emergency Plan Procedures have been established that relate the various measured parameters to integrated doses. Provisions have been made for estimating integrated dose from the projected and actual dose rates and for comparing these estimates with the protective action guides.

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GG Revision 80 FSAR 02 / 2020 7.7 Protective Facilities Emergency situations may arise, whether it be man-made or natural causes, which require that protective action be initiated to assure the safety of personnel. Predetermined procedures to be initiated in the event of a fire, tornado. or earthquake are contained within the plant operating procedures. An important consideration in the protection of the Grand Gulf personnel is for the immediate removal of those personnel not essential for the control of the plant. Security Personnel would be examples of those required to remain onsite. In the event of an emergency situation, the appropriate notification is made. Upon notification, all personnel onsite should either assume their prearranged emergency responsibilities or should follow instructions given over the PA system. This permits accountability of personnel before leaving the site or being assigned to an emergency team.

7.8 First Aid and Medical Facilities First aid equipment and facilities at Grand Gulf are available to handle a wide range of emergency situations from minor first aid to transporting a seriously injured individual to an offsite medical facility. Readily available first aid is provided by Plant Staff personnel that are first aid trained. First aid kits containing items typically needed to care for minor injuries are located in the following areas:

a. Control Room
b. Maintenance Shop
c. EOF A first aid treatment room is located in the Health Physics Access Control Area on the 93 foot level of the Control Building and is equipped with normal industrial first aid supplies.

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GG Revision 80 FSAR 02 / 2020 7.9 Rescue and Damage Control Equipment Rescue and damage control equipment consists of normal and special purpose tools and devices used in the course of maintenance and operational functions throughout GGNS.

Personnel who are assigned to use rescue and damage control equipment in an emergency are familiar with the locations and use of specific equipment. To ensure that adequate supplies are available for usage during plant emergency conditions, rescue and damage control equipment is located in the Maintenance Shop. Typical supplies contained in these cabinets are listed in Appendix B. Bulky items, such as hydraulic jacks, cutting and burning rigs, and portable generators, are not stored in emergency facilities and may be obtained from maintenance control areas, the Warehouse, or Maintenance Shop.

The GGNS Maintenance and Operations Sections are responsible for inventories of tools, equipment, and vehicles assigned to the ir respective section. As such, during work days, Supervisors in each section may authorize the use of tools, equipment, and vehicles as the situation demands. Furthermore, the Shift Manager has immediate access to shops, tool cribs, lockers, vehicles, rescue and damage control equipment, and other material during backshifts and weekends .

7.10 Personal Protective Equipment To protect personnel remaining onsite and/or arriving onsite during the emergency, quantities of personal protective equipment, including anti-contamination clothing and individual respiratory equipment are maintained on site . Protective clothing and individual respirators/

masks are stored in the emergency cabinets located in the Control Room . the TSC, the OSC, and the EOF. This equipment is inspected, inventoried, and operationally checked on at least a quarterly basis in accordance with Section 8.6.

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GG Revision 80 FSAR 02 / 2020 Table 7-1: GGNS ORO Notification System LOCATION {USUAL) CONTACT ALTERNATE Control Room Control Room Communicato r Control Room Operator Emergency Operations Facility EOF Offsite Communicato r Alt. EOF Offsite Communicato r Entergy Operations Corporate Emergency Center Information Coordinator Logistics Coordinator Mississippi Emergency Management Agency Director, MEMA Comm. Officer, MEMA Mississippi Highway Safety Patrol Comm. Officer, MHP Dispatcher, MHP Claiborne County Civil Defense Director, CCCD Asst. Director, CCCD Claiborne County Sheriffs Department Sheriff, CCSD Dispatcher, CCSD Louisiana Department of Environmental Quality Secretary of LDEQ Radiological Emergency Planning &

Response Staff Tensas Parish Sheriff's Office Sheriff, TPSO Dispatcher, TPSO Governor's Office of Homeland Security and Emergency Assistant Secretary, GOHSEP Comm. Officer, GOHSEP Preparedness 7-22

GG Revision 80 FSAR 02 / 2020 Figure 7-1: EMERGENCY FACILITIES GRAND GULF NUCLEAR STATION OFFSITE SUPPORT AGENCIES AND EMERGENCY FACILITIES CONTRACTORS EMERGENCY FACILITIES (ON OR NEAR SITE) {OFF SITE)

CONTROL ROOM JOINT MISSISSIPPI NRC INFORMATION STATE EOC HEADQUARTERS Location : El. 166' CENTER Control Bldg. Location: Location Location : Pearl, MS. Rockville, MD Pearl, MS.

TECHNICAL ENTERGY CLAIBORNE NRC SUPPORT CENTER OPERATIONS COUNTY REGION IV CORPORATE EOC Location : EMERGENCY Location Adjacent CENTER Location : Arlington, TX To Control Port Gibson, Room . Location : MS Jackson, MS.

OPERATIONS LOUISIANA GENERAL SUPPORT CENTER STATE ELECTRIC EOC Location : Location Maintenance Location : San Jose, CA Shop Baton Rouge, LA EMERGENCY TENSAS PARISH OPERATIONS EOC FACILITY Location :

Location : Energy St. Joseph, LA Services Center 7-23

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7-28

GG Revision 80 FSAR 02 / 2020 Figure 7-7: BACKUP EMERGENCY OPERATIONS FACILITY Exit Entrance Telecom Copier/FAX Office Equipment I

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GG Revision 80 FSAR 02 / 2020 Figure 7-8: ALTERNATE FACILITIES Alternate Facilities Two Story Building (Staging/Muster Area)

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GG Revision 80 FSAR 02 I 2020 8 MAINTAINING EMERGENCY PREPAREDNESS 8.1 Organizational Preparedness GGNS recognizes its responsibilities to take measures necessary to maintain emergency preparedness for all personnel who may be involved in a station emergency. The Site Vice President, through the Director, Regulatory and Performance Improvement has authority and responsibility for establishing management direction and control to assure that preparedness is maintained and that any required corrective actions are implemented. The Manager, Emergency Planning is delegated the overall responsibility for implementation of the emergency preparedness program, including training, drills and exercises involving GGNS Emergency Organization Personnel. The Manager, Emergency Planning has access to and reporting relationships with Corporate Emergency Preparedness senior management and GGNS site senior management with oversight responsibility for Emergency Preparedness. These relationships assure site emergency preparedness and fleet emergency preparedness resources, priorities and performance standards are balanced for best performance.

The Manager, Training & Development is responsible for providing required Emergency Preparedness Training for personnel who are part of the GGNS Emergency Response Organization, commensurate with their positions in the emergency organization.

8.2 Training All Entergy Operations personnel who are part of the GGNS Emergency Response Organization are required to participate in a formal Emergency Preparedness Training Program. The overall program consists of the following:

a. Plant Access Training for all unescorted personnel in the protected area.
b. Emergency Preparedness Training Specialized (EPTS) and Emergency Plan Procedure training for all emergency response personnel as required.
c. Fitness For Duty (FFD) training for all emergency response personnel in the protected area and the EOF.

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GG Revision 80 FSAR 02 / 2020 An orientation and training program is offered for all outside support agencies such as the local fire department, law enforcement, ambulance, hospital services, and civil defense/emergency preparedness.

8.2.1 General Emergency Plan Training A program is developed to provide information on the Emergency Plan to all personnel (excluding visitors) coming on site for the first time and to all personnel participating in tile annual retraining program. The following objectives are met:

a. To train personnel with respect to their responsibilities during an emergency situation
b. To keep personnel informed of any applicable changes to the Emergency Plan.

In order to meet these objectives, instructions concerning the following are given to all personnel:

a. Signals and Alarms
b. Evacuation routes and procedures
c. Response during an emergency 8.2.2 Emergency Preparedness Training Specialized and Emergency Plan Procedure Training Emergency Organization Personnel receive on, an annual basis, training in emergency response. This training program ensures continued emergency preparedness of all persons who may participate in a station emergency. Emergency Preparedness Training Specialized (including the scope, nature and frequency) is provided and includes, but is not limited to, the following categories:
a. Directors or coordinators of the response organizations;
b. Personnel responsible for accident assessment;
c. Radiological monitoring teams and radiological analysis personnel;
d. Security;
e. Repair and damage control/ correctional action teams;
f. First aid and rescue personnel;
g. Corporate support personnel filling GGNS Emergency Response Organization Positions;
h. Personnel responsible for transmission of emergency information and instructions.
i. Fire fighting Specific emergency training courses and frequency are referenced in the Emergency Preparedness Training Program.

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GG Revision 80 FSAR 02 / 2020 8.2.3 Orientation and Training Program for Offsite Support Agencies The Manager, Emergency Planning ensures training is provided for appropriate offsite support agencies. These agencies include local fire, law enforcement, ambulance, and hospital services. Assistance may be provided as needed by personnel from Training, Health Physics, Operations, Security, or Corporate Communications. This emergency plan training includes the following topics as a minimum:

a. Grand Gulf Nuclear Station site layout
b. Communications interfaces and procedures between the onsite organizations and the offsite support agencies
c. Expected responses to emergencies
d. Anticipated protective actions
e. Basic health physics and radiation protection
f. Primary and alternate plant access routes and access procedures.

Local civil defense/emergency preparedness personnel are provided training through participation in joint utility/ state/local status meetings, through invitations to attend the training offered to the agencies listed above, and through their respective state emergency preparedness organization(s). Grand Gulf Nuclear Station may also provide assistance in the training of other county/parish emergency organization personnel, if requested to do so. Emphasis is placed on the interfaces between the station and the state and local emergency organizations, communications procedures, basic radiation protection, and the expected roles of the offsite response agencies.

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GG Revision 80 FSAR 02 / 2020 8.3 Drills and Exercises Periodic exercises are conducted to evaluate major portions of emergency response capabilities; periodic drills are conducted to develop and maintain skills; and deficiencies identified as a result of exercises and drills are utilized to update the Plan and procedures.

The general purposes of drills and exercises are as follows:

a. To test the effectiveness, timing and content of the Emergency Plan and Emergency Plan Procedures
b. To test the emergency facilities and equipment
c. To ensure that emergency organization personnel are familiar with their duties and responsibilities.

An exercise is an event that tests the integrated capability and a major portion of the basic elements existing within emergency preparedness plans and organizations. An exercise simulates an emergency resulting in potential or actual offsite radiological releases that would require response by offsite authorities. A limited exercise is an event that has limited objectives and tests one or more specific portions of the basic elements existing within emergency preparedness plans and organizations.

A drill is a supervised instruction period designed to test, develop and maintain skills. A drill may be a component of an exercise or limited exercise. Drills are supervised by qualified personnel and on-the-spot correction of erroneous performance is permitted.

8.3.1 Drill and Exercise Scenarios Exercises and limited exercises are based upon preplanned scenarios with observers assigned to various locations to monitor the actions of the emergency Organization personnel. The sequence of events normally followed for exercises is:

a. Prepare the scenarios and review them with key officials of participating organizations (the actual details of exercise scenarios are kept confidential)
b. Submit exercise scenarios to the NRC as required by 10CFRS0 Appendix E.
c. Assign and brief observers - qualified observers from the utility, state/local government as well as observers from the NRC, FEMA, and the Regional Assistance Committee
c. Conduct the drill/exercise
d. Critique the drill/exercise as soon as practicable after it is conducted
e. Make necessary changes as a result of the critique review, and; 8-4

GG Revision 80 FSAR 02 / 2020

f. Provide documentation to the Manager, Emergency Planning, Director, Regulatory and Performance Improvement and Site Vice President.

Drill scenarios are prepared by the individual responsible for conducting the drill and are approved by the appropriate level of management. Drills may involve a single individual, section or department, or they may involve parts of the emergency organization .

State and local support agency participation during exercises are conducted under the biennial exercise requirements of 44CFR350. Scenarios, as appropriate, must emphasize coordination among onsite and offsite response organizations. The scenarios to be used for exercises are varied from year to year; operations in various weather conditions; during each eight-year cycle one drill or exercise is held between 6:00 p.m. and 4:00 a.m.; some of the drills or exercises are unannounced. Offsite participation is not required for off-hours or unannounced drills and exercises. Scenarios include the following:

a. Basic objectives and appropriate evaluation criteria
b. Dates, locations, and organ izations expected to participate
c. Listing of simulated events
d. Time schedule (real and simulated)
e. Narrative summary including information such as simulated casualties, offsite fire department assistance, rescue of personnel, use of protective clothing, deployment of radiological monitoring teams, public information activities, etc.
f. Observer assignments and advance materials consisting of the scenario, evaluation criteria, performance objectives, and observer check sheets.
g. The opportunity for the ERO to demonstrate key skills specific to emergency response duties in their facilities.

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GG Revision 80 FSAR 02 / 2020 8.3.2 Drill and Exercise Schedule The following drills and exercises are conducted to ensure that the Emergency Organization maintains a high degree of readiness.

a. Communications Drills Communications are tested on a monthly basis with the State and local governments within the plume exposure pathway of the Emergency Planning Zones (10 mile EPZ), and with the NRC.

Communications are tested on a quarterly basis with those State Emergency Response Organizations within the ingestion pathway (SO mile EPZ).

Communications drills include the aspect of understanding of the contents of messages. In addition, the communications drills may be utilized to review and update emergency telephone numbers.

Communications are tested annually with Federal emergency response organizations.

Communications are tested annually between the Control Room, TSC and the EOF, and between the site, state/local EOCs and field assessment teams.

b. Emergency Repair Team A drill is conducted on an annual basis to determine the effectiveness of the Emergency Repair Team members and their equipment
c. Fire Brigade Each fire brigade is drilled as required by UFSAR Section 9B.9.2. A drill is conducted on an annual basis to determine the effectiveness of the local fire department working in conjunction with the Fire Brigade. This annual drill shall involve the participation of at least one of the local fire departments.

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d. Medical Emergency Drill A medical emergency drill, involving a simulated contaminated individual, which contains provisions for participation by local support service agencies (i.e.,

ambulance and offsite medical treatment facility). shall be conducted annually.

The offsite portion of the medical drill may be performed separately, or as part of an exercise or other scheduled drill.

e. Radiological Monitoring Drill Plant environs and radiological monitoring drills, both onsite and offsite, are conducted on an annual basis to determine the effectiveness of the collection and analysis of sample media. The drills include the utilization of communication equipment and demonstrate proper record keeping procedures.
f. Health Physics Drill A Health Physics Drill is conducted on a semiannual basis and involves response to, and analysis of simulated elevated airborne and liquid samples and direct radiation measurements in the environment.
g. Text Deleted
h. Radiation Emergency Exercise An exercise is conducted on a biennial basis. The exercise involves participation of offsite emergency support personnel within the local and State Emergency Organizations. This exercise simulates emergency conditions requiring the declaration of a Site Area Emergency or General Emergency.

At least every eight years, a joint exercise appropriate to a Site Area Emergency or General Emergency that involves Federal, State, and local emergency response personnel, organizations, and agencies is conducted. The scope of the exercise tests as much of the emergency plan (i.e., GGNS, State, and local) including the alert and notification system, as is reasonably achievable. The degree of public participation in this exercise is determined by the appropriate State agencies.

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GG Revision 80 FSAR 02 / 2020 In each exercise cycle the scenarios are varied to provide the opportunity for the ERO to demonstrate proficiency in the key skills necessary to respond to the following:

1. Hostile action directed at the plant site .
2. No or minimal radiological release.
3. An initial classification of, or rapid escalation to, a Site Area or General Emergency.
4. Implementation of strategies, procedures and guidance developed under 10CFRS0.54(hh)(2).
i. Radiation Emergency Drill Drill(s) are conducted periodically between exercises to ensure emergency response capabilities are maintained. At least one of the drill(s) include management and coordination of the emergency response, accident assessment, protective action decision making, and plant system repair and corrective actions. State and local agencies shall be allowed to participate in the drill(s) when requested.

J. Hostile Action Based Exercise.

Hostile action based (HAB) exercises are performed in conjunction with a full scale exercise once every six years or once per eight year cycle. Full state participation is required every cycle, but states with more than one plume exposure pathway may alternate this participation between reactor sites.

k. Remedial Exercises.

Remedial exercises will be required if the emergency plan is not satisfactorily tested during the biennial exercise. State and local participation should be to an extent necessary to show that appropriate corrective measures have been taken regarding the elements of the plan not properly tested .

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GG Revision 80 FSAR 02 I 2020 8.3.3 Scenario Variety Documentation.

A record of scenarios shall be maintained documenting the content of scenarios used to meet the requirements of this Emergency Plan section.

8.4 Responsibilities The Manager, Emergency Planning is responsible for coordinating the implementation of the overall radiological emergency response planning and preparedness effort to include, but not be limited to:

a. Ensuring that the Emergency Plan complies with all Federal regulations, and that it is coordinated with the Grand Gulf Nuclear Station Physical Security Plan and the emergency response plans of Claiborne County, Tensas Parish, and the States of Mississippi and Louisiana.
b. Ensuring that Emergency Plan Procedures are consistent with Administrative, Security, Radiation Control, and Training Procedures, the Emergency Plan, and with each other.
c. Ensuring that training is offered annually for the emergency response personnel and local offsite support agencies and that training commitments for on-call emergency response personnel are met.
d. Ensuring that drills and exercises are conducted in accordance with Section 8.3, and that necessary corrective actions are implemented.
e. Ensuring that the Plan and procedures are reviewed and updated on an annual basis.
f. Ensuring that the commitments of the Public Information Program are met on an annual basis. This includes ensuring the accuracy of the information contained in the Grand Gulf Emergency Preparedness Public Information website and mobile application.
g. Ensuring that maintenance and inventory of emergency equipment and supplies is performed on a quarterly basis.

The Manager, Emergency Planning interfaces with several organizations who have specific responsibilities for some of the above areas.

The Manager, Emergency Planning is responsible for ensuring that the commitments of the News Media Emergency Information Program and the Public Information Program are met. He is also responsible for conducting specialized training and drills for personnel directly involved with these programs.

The Security Manager is responsible for revisions to the GGNS Physical Security Plan.

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GG Revision 80 FSAR 02 I 2020 The Manager, Emergency Planning works with the above individuals, as well as with federal, state and local personnel having responsibilities to the GGNS emergency preparedness program, to ensure that the commitments of the Plan are fully implemented.

Training opportunities are afforded to the Emergency Planning Staff to ensure that they are able to effectively carry out their assigned responsibilities.

8.5 Review and Updating of the Emergency Plan and Emergency Plan Procedures The Plan shall be reviewed and updated as necessary' on at least an annual basis. Letters of Agreement with offsite organizations and agencies are reviewed during the annual Plan review and updated as necessary. A change in original signatory(ies) to a given Letter of Agreement does not in itself require revision of that Letter. A change in applicability of content of a Letter of Agreement, however, does require a revision to that Letter.

Emergency Plans of offsite organizations and agencies are reviewed as requested.

The Manager responsible for the Quality Assurance programs is responsible for conducting an independent review of the Emergency Preparedness Program, to verify compliance with the Quality Assurance Program Manual, the Fire Protection Plan, federal regulations, and operating license provisions. The review shall be conducted at intervals not to exceed 12 months or, as necessary, based on an assessment of performance indicators, and as soon as reasonably practicable after a change occurs in personnel, procedures, equipment, or facilities that potentially could adversely affect emergency preparedness, but no longer than 12 months after the change. In any case, all elements of the emergency preparedness program must be reviewed at least once every 24 months. The review must include an evaluation for adequacy of interfaces with State and local governments and drills, exercises, capabilities, and procedures.

The results of the review, along with recommendations for improvements, must be documented, maintained for a period of five years and reported to the Manager; Emergency Planning, Director, Regulatory* and Performance Improvement, Site Vice President, and affected groups. The part of the review involving the evaluation for adequacy of interface with State and local governments must be available to the appropriate State and local governments.

In addition, the Manager, Emergency Planning, by virtue of his involvement with the Emergency Preparedness Program, provides an ongoing review. Personnel performing reviews or audits of the Emergency Plan and/or Emergency Plan Procedures take into account and review corporate policy, state policy and plans, local plans, and the various agreements and understandings with federal, state, and local support agencies and organizations.

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GG Revision 80 FSAR 02 / 2020 The Plan is a part of the GGNS FSAR but is maintained as a separate document. Document holders receive revisions to the Plan in a controlled manner as they are issued. Revised pages are dated and marked to show where revisions have been made.

The Manager, Emergency Planning is responsible for coordinating reviews and audits of the Emergency Plan and implementing procedures. In addition, the Manager, Emergency Preparedness, through letters, meetings, seminars, or other means available, ensures that all elements of the total emergency organizations are informed of revisions to the Plan.

Results of all exercises and each annual revision and change to the plan are reported to reviewed by the Site Vice President, and Director, Nuclear Safety Assurance, who provides management direction and control to ensure that all corrective actions are implemented.

8.6 Maintenance and Inventory of Emergency Equipment and Supplies The Manager, Emergency Preparedness, or his designee, is responsible for planning and scheduling the quarterly inventory and inspection of designated emergency equipment and supplies at GGNS. He, or his designee, ensures that identified deficiencies are corrected in a reasonable period of time.

All emergency equipment/instruments are inspected, inventoried and operationally tested on a quarterly basis and after each use. Lists of telephone numbers used in emergency response are reviewed and updated quarterly.

Designated emergency equipment and supplies and their storage locations are listed in Appendix B. Supplies having shelf-lives are checked and replaced as necessary.

Any deficiencies found during the inventory and inspection are either cleared immediately or documented for corrective action. There are sufficient reserves of emergency equipment/instruments available to replace any equipment which is removed from the emergency kits for calibration or repair. All emergency instruments are calibrated at the intervals specified by procedures. A summary report of each inventory and inspection is prepared and submitted to file.

8.7 Educational Information to the Public Grand Gulf Nuclear Station, in conjunction with State and local agencies, provides the following information to those members of the general public that reside within the 10 mile Emergency Planning Zone:

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GG Revision 80 FSAR 02 / 2020

a. Educational information on radiation
b. Personnel to contact for further information
c. Protective measures, e.g. evacuation routes and relocation renters, sheltering, respiratory protection, radioprotective drugs
d. Special needs of the handicapped.

This information is disseminated via a Grand Gulf Emergency Preparedness Public Information website and mobile application, and postcard mailed annually to residents of the 10-mile EPZ, in accordance with the Public Education and Information Program included in Appendix. H. This program addresses providing information to the transient population. The Public Education and Information Program annually ensures the permanent and transient adult population within the plume exposure EPZ are provided an adequate opportunity to become aware of the above information.

8.8 News Media Information A News Media Emergency Information Program was developed that includes details on arrangements for timely exchange of information among the designated spokespersons and news media representatives. This program is included in Appendix H. The details for dealing with rumors are included in Emergency Plan Procedure 10-S-01-34. GGNS provides supporting information to state and local authorities to develop messages intended for the public.

Messages to state and local authorities include information concerning recommended protective actions. This program also provides for an annual training session to acquaint the news media with the methodology to obtain information during an emergency, as well as information about overall emergency preparedness for GGNS.

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GG Revision 80 FSAR 02 / 2020 9 RECOVERY In any declared Emergency, immediate actions are intended to limit consequence and provide maximum protection to plant personnel, the general public, and plant equipment. For a Site Area or General Emergency, once emergency phase corrective and protective actions have been implemented and effective controls established, emergency actions shift to the Recovery phase which includes reentry and recovery operations.

It is the responsibility of the Emergency Director to determine when the Recovery Phase can be initiated. The following criteria must be met before recovery operations can begin :

a. The plant must be in a controlled and stable condition
b. Release of radioactive material to the environment must be controlled and must be below any of the Emergency Action Level threshold values
c. Radiation levels must be stable or decreasing in all plant areas The Emergency Director discusses existing offsite cond itions with appropriate State officials prior to terminating a Site Area Emergency or General Emergency classification.

Recovery may be completed by the Emergency Organization before emergency termination. If recovery has not been accomplished by the termination of the emergency, a recovery organization is activated as described in Section S.S. Its objective is to safely and effectively place the plant back in a safe operating condition or an acceptable long term condition.

Appropriate GGNS and outside assistance is mobilized to accomplish this objective. The Emergency Director is responsible for transmitting a notification to agencies connected to the GGNS Operational Hot Line (see Section 7.S.3 .a.l) that the incident is terminated, and the plant is transitioning to the Recovery phase .

Recovery is conducted in compliance with normal occupational dose limits specified in 10CFR20.

Significant release of radioactive materials during recovery is planned, controlled, and evaluated in advance for radiological impact, and appropriate offsite organizations and agencies informed of the scheduled release and estimated impact. Emergency Plan Procedures provide methods of periodically estimating total population exposure.

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GG Revision 80 FSAR 02 / 2020 9.1 Recovery Operations The nature and extent of an emergency determine the required recovery operations and the size of the recovery organization that must be formed. A recovery plan must be flexible enough to adapt to existing conditions. It is not possible to anticipate in advance all emergency conditions that may be encountered. General principles are addressed in this section that serve as a guide for developing a flexible plan of action. More detailed information is provided in Emergency Plan procedures.

The initial objectives of recovery operations are to determine damage to equipment, the installation of shielding, rope barriers and signs, the application of clearance tags, decontamination, and cleanup to place the plant in an acceptable long term condition. Other recovery operations are not initiated until the area affected by the emergency has been defined. Particular attention is directed toward isolating and tagging out components and systems to control or minimize hazards. A systematic assessment is conducted to determine the extent of damage to plant equipment.

Once the initial objectives are completed, a detailed investigation of the accident causes and consequences, both to the plant and to the environment, is conducted. Repair work and modifications to plant equipment and/or changes to operating procedures are determined, approved, and performed. Test programs to confirm fitness for return to services are developed and implemented.

9.2 Reentry Operations Reentry operations are part of the Recovery phase and includes returning to areas that were precluded from entry due to radiation levels or other hazards. For radiation hazards, an initial radiation assessment is performed to allow reentry and recovery operations. The following is a list of actions that should be performed prior to authorizing reentry operations into the affected areas:

a. Review available radiation survey data. Determine plant areas potentially affected by radiation and/or contamination.
b. Review radiation exposure margins of personnel who will participate in recovery operations. Determine the need for, and source of additional personnel.
c. Review adequacy of radiation survey instrumentation and equipment (type, ranges, number, calibration, etc.).
d. Preplan survey team activities to include:

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GG Revision 80 FSAR 02 / 2020

l. Areas to be surveyed
2. Anticipated radiation and contamination levels
3. Radiation survey equipment required
4. Shielding requirements and availability
5. Protective clothing and equipment required
6. Access control procedures
7. Exposure control limits and personnel dosimetry required
8. Decontamination requirements
9. Communications Initial reentry operations into plant areas include the following goals (in order of priority):
a. Determine recovery operation tasks (application of clearance tags, etc.)
b. Observe hazards or potential hazards limiting recovery operations
c. Conduct comprehensive radiation surveys of plant facilities and define radiological problem areas which could impede recovery operations
d. Post areas in the plant with radiological warning signs, and rope barriers.

Recovery operations are conducted in compliance with normal operational radiation exposure levels specified in 10CFR20. When possible, significant releases of radiation during recovery is planned, controlled, evaluated in advance for radiological impact, and appropriate offsite organizations and agencies informed of the scheduled release and estimated impact. Emergency Plan Procedures provide methods of period ically estimating total population exposure .

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GG Revision 80 FSAR 02 / 2020 APPENDIX A Emergency Plan Cross Reference and List of Procedures that Implement the Emergency Plan A-1

GG Revision 80 FSAR 02 / 2020 EMERGENCY PLAN CROSS REFERENCE EMERGENCY PLAN ADMINISTRATIVE EMERGENCY PLAN 1 SECTION PROCEDURES PROCEDURES (EPP) COMMENTS SECTION 1.0 DEFINITIONS requires no procedures SECTION 2.0 SCOPE AND APPLICABILITY contains no explicit actions or responsibilities which should be implemented by procedures. There is an implicit requirement for a procedure to assure that changes to any procedure -- administrative, operational, security, radiation protection, or emergency --be reviewed with respect to all related procedures to assure a coordinated emergency response will be provided when required .

2.1 Criterion for GGNS Emergency Plan Development 2.2 Applicability of the Emergency Plan 2.2.1 General Information and Site Description 2.2.2 Population and Population Distribution 2.2.3 Emergency Planning Zones 2.3 Scope of the Emergency Plan 2.3.1 Regulatory Requirements 2.3.2 1 Objectives of the Emergency Plan 2.4 1 Emergency Plan Interrelationships 2.4.1 Emergency Plan Procedures 2.4.2 Related Plans, Programs and Procedures 2.4.3 Participating Governmental Agencies Table 2-1 Public Facilities and Institutions A- 2 1 All emergency plan procedures prefaced with 10-S GG Revision 80 FSAR 02 / 2020 EMERGENCY PLAN CROSS REFERENCE EMERGENCY PLAN ADMINISTRATIVE EMERGENCY PLAN 1 SECTION PROCEDURES PROCEDURES (EPP) COMMENTS Table 2-2 Resident Population Distribution in Evacuation Area by Sector Figure 2-1 General Area Surrounding GGNS Figure 2-2 Site Layout Figure 2-3 Permanent Resident Population Distribution Figure 2-4 Ten-Mile Emergency Planning Zone Figure 2-5 Fifty-Mile Emergency Planning Zone 3.1 1 Emergency Planning 3.2 Emergency Plan Steps 3.3 1,6 Emergency Direction and Assignments 4.1 1 Emergency Classification System 4.1.1 1,6 Unusual Event 1,6,34, EN-EP-609, 610 & Alert 4.1.2 611 1,6,34, EN-EP-609, 610 & Site Area Emergency 4.1.3 611 1,6,34, EN-EP-609, 610 & General Emergency 4.1.4 611 4.2 Classification of postulated accidents.

Table 4-1 1,38 Emergency Action Levels Initiating Conditions 5.1 Statement of GGNS organization 5.2 Statement of normal station organization .

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All emergency plan procedures prefaced with 10-5 GG Revision 80 FSAR 02 / 2020 EMERGENCY PLAN CROSS REFERENCE EMERGENCY PLAN ADMINISTRATIVE EMERGENCY PLAN 1 SECTION PROCEDURES PROCEDURES (EPP) COMMENTS 5.2.1 General Manager, Plant Operations 5.2.2 Senior Manager, Operations 5.2.3 Senior Manager, Maintenance 5.2.4 Manager, Radiation Protection 5.2.5 Senior Manager, Production 5.2.6 Manager, Training & Development 5.2.7 Shift Technical Advisor 5.2.8 Manager, Supply Chain 5.2.9 Director, Reg & Performance Improvement 5.3 Statement of normal station shift staffing.

5.4 Emergency Organization 5.4.1 Normal Station Shift 5.4.2 EN-EP-801 EN-EP-609, EN-EP-613 Emergency Director 5.4.3 EN-EP-801 EN-EP-609 EOF Manager 5.4.4 EN- EP-801 EN-EP-609 Radiological Assessment Coordinator 5.4.5 EN-EP-801 EN-EP-609 Technical Advisor 5.4.6 EN-EP-801 EN-EP-609 Admin. & Logistics Coordinator 5.4.7 EN-EP-801 EN-EP-609,34 Public Information Liaison 5.4.8 EN-EP-801 6, EN -EP-609 Offsite Communicator A- 4 1

All emergency plan procedures prefaced w ith 10-S GG Revision 80 FSAR 02 / 2020 EMERGENCY PLAN CROSS REFERENCE EMERGENCY PLAN ADMINISTRATIVE EMERGENCY PLAN 1 SECTION PROCEDURES PROCEDURES (EPP) COMMENTS 5.4.9 EN-EP-801 EN-EP-609 EOF Communicator 5.4.10 EN-EP-801 EN-EP-609 Lead Offsite Liaison 5.4.11 EN-EP-801 EN-EP-609 Offsite Liaison EN-EP-801 12, EN-EP-609 Dose Assessor 5.4.12 EN-EP-313 5.4.13 EN-EP-801 EN-EP-609 Offsite Team Coordinator 5.4.14 EN-EP-801 EN-EP-609 Offsite Monitoring Team 5.4.15 EN-EP-801 EN-EP-609 Information Technology (IT) Specialist 5.4.16 EN-EP-801 EN-EP-610 EOF Log Keeper 5.4.17 EN-EP-801 EN-EP-610 Emergency Plant Manager (EPM) 5.4.18 EN-EP-801 EN-EP-610 TSC Manager 5.4.19 EN-EP-801 EN-EP-610 TSC Communicator 5.4.20 EN-EP-801 1, EN-EP-610 Security Coordinator 5.4.21 EN-EP-801 EN-EP-610 ENS Communicator 5.4.22 EN-EP-801 EN-EP-610 Maintenance Coordinator 5.4.23 EN-EP-801 EN-EP-610 Engineering Coordinator 5.4.24 EN-EP-801 EN-EP-610 Radiological Coordinator A- 5 1

All emergency plan procedures prefaced with 10-S GG Revision 80 FSAR 02 / 2020 EMERGENCY PLAN CROSS REFERENCE EMERGENCY PLAN ADMINISTRATIVE EMERGENCY PLAN 1 SECTION PROCEDURES PROCEDURES (EPP) COMMENTS 5.4.25 EN-EP-801 EN- EP-610 Operations Coordinator 5.4.26 EN- EP-801 EN-EP-610 Engineers (Mech./l&C/Elect.)

5.4.27 EN -EP-801 EN-EP-610,35 Reactor Engineer 5.4.28 EN-EP-801 EN-EP-611 OSC Manager 5.4.29 EN -EP-801 EN-EP-611 Log Keeper - OSC 5.4.30 EN-EP-801 EN-EP-611 Operations Support 5.4.31 EN -EP-801 EN-EP-611 Work Control Coordinator 5.4.32 EN-EP-801 EN-EP-611 Mechanical/l&C/Electrical Coordinator 5.4.33 EN-EP-801 EN -EP-611 Rad Chem Coordinator 5.4.34 EN- EP-801 34 Company Spokesperson 5.4.35 EN -EP-801 34 Technical Advisor-JIC 5.4.36 EN -EP-801 34 JIC Manager 5.4.37 EN-EP-801 34 Log Keeper - JIC 5.4.38 EN-EP-801 34 Inquiry Response Coordinator 5.4.39 EN-EP-801 34 Press Release Writer A- 6 1

All emergency plan procedures prefaced with 10-S GG Revision 80 FSAR 02 / 2020 EMERGENCY PLAN CROSS REFERENCE EMERGENCY PLAN ADMINISTRATIVE EMERGENCY PLAN 1 SECTION PROCEDURES PROCEDURES (EPP) COMMENTS 5.5 EN-EP-613 Recovery Organization Local services support (normal 10CFR20 limits on 5.6 exposure or contamination) 5.6.1 Description of medical support 5.6.2 Fire Support 5.6.3 Law Enforcement Agencies 5.7 Coordination with Governmental Agencies.

5.7.1 MEMA and Miss. Div. of Radiological Health 5.7.2 LDEQAND GOHSEP 5.7.3 Port Gibson/Claiborne Co. Civil Defense Tensas Parish Office of Homeland Security and 5.7.4 Emergency 5.7.S 6 NRC A- 7 1

All emergency plan procedures prefaced with 10-S GG Revision 80 FSAR 02 I 2020 EMERGENCY PLAN CROSS REFERENCE EMERGENCY PLAN ADMINISTRATIVE EMERGENCY PLAN 1 SECTION PROCEDURES PROCEDURES (EPP) COMMENTS 5.7.6 DOE 5.7.7 INPO 5.7.8 U.S.C.G.

5.8 EN-EP-609 Contractor Assistance 5.9 Support for Federal Response Table 5-1 6 Minimum shift staffing Figure 5-1 Deleted Figure 5-2 Normal Station Organization Figure 5-3 Emergency Organization Figure 5-4 Emergency Organization Interrelationships of Emergency Response Figure 5-5 Organizations Figure 5-6 Federal Response Management Diagram 6.1 Initiating emergency measures 6.1.1 EN-EP-801 Emergency Guidance Suspension (50.54x) 6.1.2 EN-EP-610 Security Plan 6.2 Activation of emergency organization 6.2.1 Control room operators A- 8 1

All emergency plan procedures prefaced with 10-S GG Revision 80 FSAR 02 / 2020 EMERGENCY PLAN CROSS REFERENCE EMERGENCY PLAN ADMINISTRATIVE EMERGENCY PLAN 1 SECTION PROCEDURES PROCEDURES (EPP) COMMENTS 6.2.2 1 Shift Manager 6.2.3 STA 6.2.4 1,6,34 Emergency Director 6.3 Assessment Actions 6.3.1 1 Assessment actions during Unusual Events 6.3.2 1 Assessment actions during Alerts 6.3.3 1 Assessment actions during Site Area Emergencies 6.3.4 1 Assessment actions during General Emergencies 6.4 Corrective Actions 6.5 Protective actions Protective cover, evacuation, personnel 6.5.1 accountability 6.5.1.a 11, EN-EP-609 GGNS 6.5.1.b 11 Offsite areas 6.6 11 Contamination Control Measures 6.7 Aid to affected personnel 6.7.1 17,20 Emergency Personnel Exposure 6.7.2 11 Decontaminat ion and First Aid 6.7.3 19 Medical Transportation 6.7.4 19 Medical Treatment A-9 1 All emergency plan procedures prefaced with 10-S GG Revision 80 FSAR 02 / 2020 EMERGENCY PLAN CROSS REFERENCE EMERGENCY PLAN ADMINISTRATIVE EMERGENCY PLAN 1 SECTION PROCEDURES PROCEDURES (EPP) COMMENTS Table 6-1 12 Recommended Protective Actions Figure 6- 1 Deleted Figure 6-2 6, EN -EP-609 Emergency Notification Form 7.1 Facilities and Equipment 7.2 Control Room 7.3 39 Emergency Response Facilities 7.3.1 EN -EP-610 TSC 7.3.2 EN -EP-611 osc 7.3.3 EN-EP-609 EOF 7.3.4 EN -EP-609, 41 BEOF 7.3.5 34 Media Centers 7.4 County and State Emergency Centers 7.4.1 Claiborne County EOC 7.4.2 Mississippi State EOC 7.4.3 Tensas Parish EOC A-10 1 All emergency plan procedures prefaced with 10-5 GG Revision 80 FSAR 02 / 2020 EMERGENCY PLAN CROSS REFERENCE EMERGENCY PLAN ADMINISTRATIVE EMERGENCY PLAN 1 SECTION PROCEDURES PROCEDURES (EPP) COMMENTS 7.4.4 Louisiana State EOC 7.5 01-S-10-5 Communications Systems 7.5.1 Telephone System 7.5.2 Plant Paging System & Sound Powered Phones 01-S-10-5 1,6, EN-EP-611 Emergency Communications Equipment 7.5.3 10-S-01-6 7.5.4 Alert Notification System 7.6 Assessment Facilities 7.6.1 EN-EP-313 12 Onsite Systems and Equipment 7.6.2 Offsite Monitoring Equipment and Facilities 7.6.3 14 Radiological Assessment Laboratories 7.6.4 Post-Accident Sampling Capability 7.6.4 01-S-10-5 28 Designated Emergency Vehicles 7.7 11 Protective Facilities 7.8 01-S-10-5 First Aid and Medical Facilities 7.9 01-S-10-5 Rescue and Damage Control Equipment 7.10 01-S-10-5 Personal Protective Equipment Table 7-1 EN-EP-609 GGNS Operational Hot Line Figure 7-1 Emergency Facilities A-11 1

All emergency plan procedures prefaced with 10-S GG Revision 80 FSAR 02 / 2020 EMERGENCY PLAN CROSS REFERENCE EMERGENCY PLAN ADMINISTRATIVE EMERGENCY PLAN 1 SECTION PROCEDURES PROCEDURES (EPP) COMMENTS Figure 7-2 Technical Support Center Figure 7-3 Operations Support Center Figure 7-4 Emergency Operations Facility Level I Figure 7-5 Emergency Operations Facility Level II Figure 7-6 Emergency Operations Facility Location Figure 7-7 Backup Emergency Operations Facility Figure 7-8 Deleted Figure 7-9 Joint Information Center Layout Figure 7-10 Deleted Figure 7-11 Deleted Figure 7-12 Communications Interfaces Figure 7-13 Siren Locations 8.1 Organizational Preparedness 8.2 EN-TQ-110 Training 8.2.1 EN-TQ-110 General Emergency Plan Training Emergency Preparedness Training Specialized and 8.2.2 EN-TQ-110 Emergency Plan Procedure Training A- 12 1

All emergency plan procedures prefaced w ith 10-S GG Revision 80 FSAR 02 / 2020 EMERGENCY PLAN CROSS REFERENCE EMERGENCY PLAN ADMINISTRATIVE EMERGENCY PLAN 1 SECTION PROCEDURES PROCEDURES (EPP) COMMENTS Orientation and Training Program for Offsite 8.2.3 0l-S-10-3 Support Agencies 8.3 37 Drills and Exercise 8.3.1 Drill and Exercise Scenarios 8.3.2 Drill and Exercise Schedule 8.4 01-S-10-3 Responsibilities Review of Emergency Plan and Emergency Plan 8.5 01-S-10-3 Procedure Ol-S-10-3, 5 39 Maintenance and Inventory of Emergency 8.6 EN-RP-301 Equipment and Supplies 8.7 01-S-10-3 Educational Information to the Public 8.8 34 News Media Information 8.11 EN-RP-301 RP Instrument Calibration 9.1 22,23, EN-EP-609 Reentry/Recovery 9.2 23, EN-EP-609 Reentry 9.3 1,22, EN-EP-609 Recovery Appendix A Reserved Appendix B List of supplies Appendix C Reserved AP.Qendix D Letters of Agreement from offsite organizations A-13 1

All emergency plan procedures prefaced with 10-S GG Revision 80 FSAR 02 / 2020 EMERGENCY PLAN CROSS REFERENCE EMERGENCY PLAN ADMINISTRATIVE EMERGENCY PLAN 1 SECTION PROCEDURES PROCEDURES (EPP) COMMENTS Appendix E Evacuation Time Estimates Appendix F Index of Supporting Plans AQ_Qendix G Reserved 34 News Media Emergency Information Program and AQ.Qendix H Public Education and Information Program Appendix I Reserved A- 14 1

All emergency plan procedures prefaced w ith 10-S GG Revision 80 FSAR 02 I 2020 LIST OF PROCEDURES THAT IMPLEMENT THE EMERGENCY PLAN 10-S-01-1 Activation of Emergency Plan (EPP-1)

(EPP-1) Upon recognition that abnormal plant or site conditions exist, this procedure will be used by the operator to determine the appropriate EAL(s), properly classify the emergency condition and action to be taken for the emergency classification.

10-S-01-2 Unusual Event (EPP-2)

DELETED- Superseded by 10-5-01-1 10-S-01-3 Alert (EPP-3)

DELETED-Superseded by 10-S-01-1.

10-S-01-4 Site Area Emergency (EPP-4)

DELETED-Superseded by 10-S-01-1.

10-S-01-5 General Emergency (EPP-5)

DELETED - Superseded by 10-S-01-1.

10-S-01-6 Notification of Offsite Agencies and Plant On-Call Emergency Personnel (EPP-6)

This procedure lists the methods of notifying Emergency Organization Personnel; for notifying Federal, State, and local authorities; for notifying outside service agencies; and for keeping the proper communication record.

10-S-01-7 Activation of Emergency Facilities (EPP-7)

DELETED-Superseded by EN-EP-609, EN-EP-610, EN-EP-611 and 10-S-01-41 10-S-01-8 Fire (EPP-8)

DELETED - Superseded by 10-S-03-2 10-S-01-9 Release ofToxic Material (EPP-9)

DELETED-Superseded by 10-S-01-1 (EPP-1) and 05-1-02-11-12 10-S-01-10 Natural Occurrences (EPP-10)

DELETED-Superseded by 05-1-02-Vl-l, 05-1-02-Vl-2, 05-S-02-Vl-3, and EN-FAP-EP-010 10-S-01-11 Evacuation of Onsite Personnel (EPP-11)

This procedure provides the guidelines for evacuation and accountability of personnel during an emergency.

10-S-01-12 Radiological Assessment and Protective Action Recommendations (EPP-12)

This procedure provides guidance for performing radiological assessment during emergencies.

10-S-01-13 Onsite Radiological Monitoring (EPP-13)

DELETED-Superseded by 10-S-01-14 (EPP-14) 10-S-01-14 Emergency Radiological Monitoring (EPP-14)

This procedure provides guidelines for performing radiological surveys outside of the restricted area during emergency conditions . Instructions for dose rate measurements and collection and analysis of radioiodines are included.

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GG Revision 80 FSAR 02 / 2020 LIST OF PROCEDURES THAT IMPLEMENT THE EMERGENCY PLAN 10-S-01-15 Site Access Point Operations (EPP-15): DELETED 10-S-01-16 Personnel Accountability (EPP-16)

DELETED- Superseded by 10-5-01-11 (EPP-11) 10-S-01-17 Emergency Personnel Exposure Control (EPP-17)

This procedure provides guidelines for the issuing dosimetry and RWP access during emergencies.

10-S-01 -18 Personnel Search and Rescue (EPP-18)

This procedure provides guidelines for perform ing search and rescue operations in order to locate and/

or rescue individuals that have not been accounted for.

10-S-01-19 Personnel Injury (EPP-19)

This procedure provides for handling those individuals who have been injured and must be transported off site.

10-S-01-20 Administration of Thyroid Blocking Agents (EPP-20)

This procedure provides guidance on the use of potassium iodide as a thyroid blocking agent to prevent thyroid uptake of rad ioactive iodine and the subsequent dose.

10-S-01-21 Evacuating Personnel and Vehicle Contam ination Control (EPP-21): DELETED-Superseded by 10-S-01-11 (EPP-11)

EN-EP-613 Recovery This procedure provides guidance for the Recovery phase of on emergency and the formation of a Recovery organization .

10-S-01-23 Reentry (EPP-23)

This procedure provides general guidance for the Reentry Operations.

10-S-01-24 Maintenance of Emergency Preparedness (EPP-24)

DELETED -Superseded by 01-S-10-5.

10-S-01-25 Onsite Personnel Response (EPP-25)

DELETED-Superseded by 10-S-01-11 (EPP-11) 10-S-01-26 Offsite Emergency Response (EPP-26)

This procedure provides instructions for offsite emergency personnel that are ordered to report to the site during an emergency.

10-S-01-27 Public Information (EPP-27): DELETED- Superseded by 10-S-01-34 10-S-01-28 Control of Designated Emergency Vehicles (EPP-28)

This procedure provides a description of the administrative controls over company-owned veh icles designated for use during an emergency A-16

GG Revision 80 FSAR 02 I 2020 LIST OF PROCEDURES THAT IMPLEMENT THE EMERGENCY PLAN EN-EP-611 Operations Support Center (OSC) Operations This procedure provides general instructions for the Operations Support Center (OSC) including: facility activation, personnel responsibilities, staffing and coordination of Emergency Response Teams.

EN-EP-610 Technical Support Center (TSC) Operations This procedure provides general instructions for the TSC including: facility activation, personnel responsibilities, staffing and coordination between the Control Room, and the Operations Support Center.

EN-EP-609 Emergency Operations Facility (EOF) Operation This procedure provides instructions for the activation operation of the EOF.

10-S-01-34 Joint Information Center (JIC) Operations (EPP-34)

This procedure provides instructions for dissemination of public information and the activation and operation of the NMC and EiC.

10-S-01-35 Core Damage Assessment (EPP-35)

This procedure provides guidance for determining if core damage may or has occurred and estimating amount of reactor core damage under accident conditions.

10-S-01-36 Incident Command Post (ICP) Operation This procedure provides general instructions for the activation and operation of the Incident Command Post 10-S-01-37 Communication Drill This procedure provides guidance for performing communication drills.

10-S-01-38 EAL Contingency Planning This document identifies the plant instruments that are the designated indicators of Emergency Action Level (EAL) entry criteria. It then analyzes each primary instrument for backup/alternative indications allowed by the EAL, Instrument redundancy and Correlation between EAL requirements by Operating Mode versus related Tech Spec/TRM/ODCM. This procedure is entered when any of the equipment listed in the attachments is identified to be out of service 10-S-01-39 Grand Gulf Equipment Important to Emergency Response This procedure ensures that when equipment important to emergency response (emergency preparedness [EP] equipment) is removed from service for maintenance or is in a degraded condition, the correct restoration priority is assigned, compensatory measures are implemented, and the equipment is restored to a functional condition promptly EN-TQ-110 Emergency Response Organization Training Program This procedure describes and implements training for GGNS ERO to ensure a constant state of preparedness for and during emergencies.

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GG Revision 80 FSAR 02 I 2020 LIST OF PROCEDURES THAT IMPLEMENT THE EMERGENCY PLAN 01-S-10-3 Emergency Planning Department Responsibilities This procedure describes the responsibilities and organizational structure of the Emergency Planning staff, provides guidance for the overall maintenance of the Emergency Planning program and defines the responsibilities for ma intenance and control of the GGNS Emergency Plan.

EN-EP-306 Drills and Exercises This procedure describes the type and frequency of drills and exercise, procedure for conducting a drill or exercise, and method for management review and approval of drills and exercises.

01-S-10-5 Control of Emergency Response Equipment and Facilities This procedure prescribes the requirements for the inventory, inspection, maintenance and operability checks of Emergency Facilities and Equipment.

01 -S-10-8 Emergency Preparedness Action Tracking System DELETED - Superseded by 01-8-10-3 .

EN-EP-801 Emergency Response Organization The procedure outlines responsibilities for personnel assigned to an ERO position and for other company personnel who may be called upon to support an emergency response effort but are not directly assigned to an ERO position.

EN-EP-313 Offsite Dose Assessment Using the Unified Rascal Interface This procedure provides the methods and instructions for performing offsite dose assessment using the Unified RASCAL Interface (URI) by the On-Shift and ERO Dose Assessors and may also be u sed by Offsite Response Organizations (OROs) who use URI for Dose Assessment EN-RP-301 Radiation Protection Instrument Control This procedure describes the Entergy Nuclear program to ensure that radiation and radioactivity measurement instruments are properly maintained and calibrated, and response checked at the appropriate frequencies.

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GG Revision 80 FSAR 02 I 2020 APPENDIX B List of Emergency Equipment and Supplies for Emergency Facilities and Hospitals B-1

GG Revision 80 FSAR 02 / 2020 This appendix contains a list of supplies by general category maintained in the emergency kits and lockers located in the various emergency facilities. Detailed lists of the inventory are maintained in accordance with 01-5-10-5, Control of Emergency Response Equipment and Facilities.

EMERGENCY EQUIPMENT MAINTAINED IN THE CONTROL ROOM/TSC/OSC/EOF A. Protective Equipment B. Radiological Monitoring Equipment C. Communications Equipment D. Emergency Supplies EMERGENCY EQUIPMENT MAINTAINED IN THE BEOF A. Communications Equipment EMERGENCY EQUIPMENT MAINTAINED AT RIVER REGION MEDICAL CENTER AND CLAIBORNE COUNTY MEDICAL CENTER A. Protective Equipment B. Radiological Monitoring Equipment C. Emergency Supplies EMERGENCY FOOD AND WATER SUPPLIES A. Emergency food and water supplies are maintained in the Control Room envelope in sufficient quantity to maintain five people for five days.

B. Emergency food and water supplies are maintained in the EOF in sufficient quantity to maintain seven people for five days.

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GG Revision 80 FSAR 02 I 2020 APPENDIX C Reserved C- 1

GG Revision 80 FSAR 02 / 2020 APPENDIX D Letters of Agreement D- 1

GG Revision 80 FSAR 02 / 2020 Letters of agreement detail arrangements for the request and utilization of resources of federal, state local and private organizations in response to emergency conditions at the Grand Gulf Nuclear Station. The documents located in previous revisions of this Appendix have been removed. These documents and their annual confirmations are maintained by the Emergency Planning Department and are available for review. A summary of letters and contracts used to implement the Grand Gulf Emergency Plan are contained in the following list.

1. U.S. Department of Energy - The U.S. Department of Energy provides support through the Radiation Emergency Assistance Center/Training Site (REAC/TS) to Entergy Nuclear facilities in the event of a radiological emergency.
2. State of Mississippi - The State or Mississippi commits response as delineated in the Mississippi Radiological Emergency Preparedness Plan and the Mississippi Emergency Management Plan.
3. State of Mississippi/Mississippi Emergency Management Agency -The Mississippi Emergency Management Agency (MEMA) provides for the coordination of Mississippi state agency and local government response in support of the Grand Gulf Emergency Plan. This assistance includes maintaining the offsite emergency plan, training in support of this plan, maintaining a communications system to implement elements of the plan and assisting with evacuation arrangements in support of the plan.
4. Governor's Office of Homeland Security & Emergency Preparedness - The Governor's Office of Homeland Security & Emergency Preparedness (GOHSEP) provides assistance with the implementation of the Louisiana Peacetime Radiological Response Plan. GOHSEP provides a 24/7 communications point; conducts radiological training for Louisiana based local and state responders; participates in Grand Gulf drills and exercises; coordinates and maintains state level emergency response procedures; and calibrates and maintains offsite radiation detection equipment.
5. Port Gibson/Claiborne County Civil Defense Council *The Port Gibson/Claiborne County Civil Defense Council commits to the implementation of its Radiological Emergency Plan, the activation of the Port Gibson/Claiborne County EOC, and the initiation of protective actions for Claiborne County in the event of a nuclear Incident at Grand Gulf.
6. Tensas Parish Office of Homeland Security and Emergency Preparedness - Tensas Parish Office of Homeland Security and Emergency Preparedness commits to the implementation of its Radiological Emergency Plan, the activation of the Tensas Parish EOC, and the initiation of protective actions for Tensas Parish in the event of a nuclear incident at Grand Gulf.

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GG Revision 80 FSAR 02 / 2020

7. Port Gibson Police Department-The Port Gibson Police Department commits to assistance with traffic control, backup communications, initiation of protective actions and coordination of evacuations within Port Gibson city limits in the event of a nuclear incident at Grand Gulf.
8. Claiborne County Sheriff's Department -The Claiborne County Sheriff's Department letter of agreement detailing emergency related support for Grand Gulf is on file in accordance with Federal regulations dealing with the protection of information concerning physical security of the plant.
9. Claiborne County fire Department - Claiborne County Fire Department commits to assistance with fighting fires to the site, assisting law enforcement with evacuations, maintaining fire protection surveillance and assisting with decontamination in the event of a nuclear incident at Grand Gulf.
10. Claiborne County Hospital -The Claiborne County Hospital commits to accept and treat injured or ill personnel from Grand Gulf Nuclear Station who are radioactively contaminated or overexposed, develop and maintain procedures for dealing with radioactively contaminated/exposed personnel, and participate in emergency related drills.
11. River Region Health System - The River Region Health System commits to accept and treat injured or ill personnel from Grand Gu lf Nuclear Station who are radioactively contaminated or overexposed, develop and maintain procedures for dealing with radioactively contaminated/exposed personnel, and participate in emergency related drills.
12. Institute of Nuclear Power Operations - The Institute of Nuclear Power Operations coordinates emergency related assistance between electric utilities responsible for the operation of commercial nuclear power facilities.
13. Ochsner Clinic Foundation - The Ochsner Clinic Foundation through letter of agreement agrees to accept and treat injured or ill personnel from Grand Gulf Nuclear Station whether or not they are radioactively contaminated or overexposed. Ochsner also agrees to accept injured or ill GGNS personnel from Claiborne County Medical Center or River Region Medical Center.
14. ASAP EMS. Corp. -ASAP EMS provides ambulance service to treat and transport injured or ill Grand Gulf personnel to local hospitals. ASAP EMSD will also develop and maintain procedures for transportation of radioactively contaminated GGNS personnel and will participate in drills related to the medical transportation of GGNS personnel. This service was previously provided by Metro Ambulance Service.

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GG Revision 80 FSAR 02 / 2020 APPENDIX E Executive Summary of the Evacuation Time Estimates For Grand Gulf Nuclear Station November 2012 The entire Evacuation Time Estimates Study can be found in GIN 2013/00190.

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GG Revision 80 FSAR 02 / 2020 EXECUTM

SUMMARY

This report describes the analyses. undertaken and the re.suits obtained by a study to develop Evacuation Time Estimates (ETEJ for the Grand Gulf Nuclear Station {GGNS) located in Claiborne County, MS. ETE are part of the req uired planning basis and provide Entersv and State and local governments with site-specific information needed for Protective Action decision-making.

In the performance of this effort. guidance is provided by documents published by Federal Governmental agencies. Most important of these are:

  • Criteria for Development of Evacuation Time Estimate Studies, NUREG/CR-7002, November 2011.
  • Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, NUREG-0654/FEMA-REP-1, Rev. 1, November 1980.
  • Development of Evacuation Time Estimates fo r Nuclear Power Plants, NUREG/ CR-6863, January 2005 .
  • 10CFR50, Appendix E - " Emergency Planning and Preparedness for Production and Utilization Facilities" Overview of Project Activities.

This project began in April, 2012 and extended over a period of six months. The major activities performed are briefly described in chronological sequence:

  • Attended Nkick-off" meetings with Entersv personnel and emergency management personnel representing state and county governments.
  • Accessed U.S. Census Bureau data files for the year 2010. Studied Geosraphical Information Systems (615) maps of the area in the vicinity of the GGNS, then conducted a detaifed field survey of the highway network.
  • Svnthesized this infonnation to create an analysis network representing the highway system topology and capacities within the Emergency Plannins Zone (EPZ), plus a Shadow Region covering the region between the EPZ boundary and approximately 15 miles radially from the plant.
  • Designed and sponsored a telephone survey of residents within the E.PZ to gather focused data needed for this ETE study that were not contained w ithin the census database. The survey instrument was reviewed and modified by the licensee and offstte response orsanizatlon (ORO} personnel prior to the survey.
  • Data collection farms (provided to the OROs at the kickoff meeting) were returned with data pertaining to employment. transients, and special facilities in each countv and parish.

Grand Gulf Nuclear Station ES-1 KLD Engmeering. P.C.

Evacuation Tane Estimate Rev. 1 E-2

GG Revision 80 FSAR 02 I 2020

  • The traffic demand and trip-generation rates of evacuating vehicles were estimated from the gathered data. The trip generation rates reflected the estimated mobilization time (i.e., the time required by evacuees to prepare for the evacuation trip) computed using the results of the telephone survey of EPZ residents.
  • Following federal guidelines, the EPZ is subdivided into 16 PAS / PAA. These PAS/ PAA are then grouped within circular areas or "keyhole" configurations (circles plus radial sectors) that define a total of 41 Evacuation Regions.
  • The time-varying external circumstances are represented as Evacuation Scenarios, each described in terms of the following factors : (1) Season (Summer, Winter); (2) Day of Week (Midweek, Weekend); (3) Time of Day (Midday, Evening); and (4) Weather (Good, Rain). One special event scenario involving a football game at Alcorn State University was considered. One roadway impact scenario was considered wherein a single lane was closed on US 61 northbound for the duration of the evacuation.
  • Staged evacuation was considered for those regions wherein the 2-mile radius and sectors downwind to 5 miles were evacuated.
  • A rapidly escalating accident at the GGNS that quickly assumes the status of General Emergency such that the Advisory to Evacuate is announced in a timely manner following the siren notification, and no early protective actions have been implemented.
  • While an unlikely accident scenario, this planning basis will yield ETE, measured as the elapsed time from the Advisory to Evacuate until the stated percentage of the population exits the impacted Region, that represent "upper boundu estimates. This conservative Planning Basis is applic.able for all initiating events.
  • If the emergency occurs while schools are in session, the ETE study assumes that the children will be evacuated by bus directly to reception centers located outside the EPZ.

Parents, relatives, and neighbors are advised to not pick up their children at school prior to the arrival of the buses dispatched for that purpose. The ETE for schoolchildren are calculated separately.

  • Evacuees who do not have access to a private vehicle will either ride-share with relatives, friends or neighbors, or be evacuated by buses provided as specified in the county evacuation plans. Those in special facilities will likewise be evacuated with public transit, as needed: bus, van, or ambulance, as required. Separate ETE are calculated for the transit-dependent evacuees, for homebound special needs population, and for those evacuated from special facilities.

Computation of ETE A total of 492 ETE were computed for the evacuation of the general public. Each ETE quantifies the aggregate evacuation time estimated for the population within one of the 41 Evacuation Regions to evacuate from that Region, under the circumstances defined for one of the 12 Grand Gulf Nuclear Station ES-2 KlD Engineering, P.C.

EvaC1r.1tion Trme Estimate Rev_ 1 E-3

GG Revision 80 FSAR 02 / 2020 Evacuation Scenarios (41 x 12 = 492). Separate ETE are calculated for transit-dependent evacuees, induding schoolchildren for applicable scenarios.

Except for Region R03, which is the evacuation of the entire EPZ. only a portion of the people within the EPZ would be advised to evacuate. That is, the Advisory to Evacuate applies only to those people occupying the specified impacted region. It is assumed that 100 percent of the people within the impacted region will evacuate in response to this Advisory. The people occupying the remainder of the EPZ outside the impacted region may be advised to take shelter.

The computation of ETE assumes that 20% of the population within the EPZ but outside the Impacted region, will elect to "voluntarily* evacuate. In addition, 20% of the population In the Shadow Region will also elect to evacuate. These voluntary evacuees could impede those who are evacuating from within the impacted region. The impedance that could be caused by voluntary evacuees is considered in the computation of ETE for the impacted region.

Staged evacuation is considered wherein those people within the 2-mile region evacuate immediately, while those beyond 2 miles, but within the EPZ, shelter-in-place. Once 90% of the 2-mlle region Is evacuated, those people beyond 2 miles begin to evacuate. As per federal guidance, 20% of people beyond 2 miles will evacuate (non-compliance) even though they are advised to shelter-in-place.

The computational procedure ls outlined as follows:

  • A link-node representation of the highway network is coded. Each link represents a unidirectional length of highway; each node usually represents an intersection or merge point. The capacity of each link is estimated based on the field survey observations and on established traffic engineering procedures.
  • The evacuation trips are generated at locations called Hzonal centroids* located within the EPZ and Shadow Region. The trip generation rates vary over time reflecting the mobilization process, and from one location (centroid) to another depending on population density and on whether a centroid ls within, or outside, the impacted area.
  • The evacuation model computes the routing patterns for evacuating vehicles that are compliant with federal guidelines (outbound relative to the location of the plant), then simulate the traffic flow movements over space and time. This simulation process estimates the rate that traffic flow exits the impacted region.

The ETE statistics provide the elapsed times for 90 percent and 100 percent, respectively, of the population within the impacted region, to evacuate from within the impacted region. These statistics are presented in tabular and graphica l formats. The 90th percentile ETE have been identified as the values that should be considered when making protective action decisions because the 100th percentile ETE are prolonged by those relatively few people who take longer to mobilize. This is referred to as the *evacuation tair in Section 4.0 of NUREG/CR-7002.

The use of a public outreach (infonnatlon) program to emphasize the need for evacuees to minimize the time needed to prepare to evacuate (secure the home, assemble needed clothes, Grand Gulf Nuclear Station ES-3 KlO Engineering. P,C.

Evacuation Time Estimate Rev. 1 E-4

GG Revision 80 FSAR 02 / 2020 medicines, etc.) should also be considered.

Traffic Manasement This study references the comprehensive traffic management plans provided by Claiborne County, MS and Tensas Parish, LA. Due to the limited traffic congestion within the EPZ, no additional traffic or access control measures have been identified as a result of this study.

Selected Results A compilation of selected information is presented on the following pages in the form of Figures and Tables extracted from the body of the report; these are described below.

  • Figure 6-1 displays a map of the GGNS EPZ showing the layout of the 16 PAS/ PAA that comprise, in awegate, the EPZ.
  • Table 3-1 presents the estimates of permanent resident population in each PAS/ PAA based on the 2010 Census data.
  • Table 6-1 defines each of the 41 Evacuation Regions in terms of their respective groups of PAS/PAA.
  • Table 6-2 lists the Evacuation Scenarios.
  • Tables 7-1 and 7-2 are compilations of ETE. These data are the times needed to clear the indicated regions of 90 and 100 percent of the population occupying these regions, respectively. These computed ETE include consideration of mobilization time and of estimated voluntary evacuations from other regions within the EPZ and from the Shadow Region.
  • Tables 7-3 and 7-4 presents ETE for the 2-mile region for un-staged and staged evacuations for the 90 th and 100th percentiles, respectively.
  • Table 8-7 presents ETE for the schoolchildren in good weather.
  • Table 8-10 presents ETE for the transit-dependent population in good weather.
  • Figure H-8 presents an example of an Evacuation Region (Region R08) to be evacuated under the circumstances defined in Table 6-1. Maps of all regions are provided in Appendix H.

Conclusions

  • General population ETE were computed for 492 unique cases - a combination of 41 unique Evacuation Regions and 12 unique Evacuation Scenarios. Table 7-1 and Table 7-2 document these ETE for the 90th and 100th percentiles. These ETE range from 1:25 (hr.min) to 2:30 at the 90th percentile.
  • Inspection of Table 7-1 and Table 7-2 indicates that the ETE for the 100th percentile are significantly longer than those for the 90th percentile (see Figures 7-8 through 7-19). This is due to the fact that the resident mobilization curve has a long "tair; relatively few evacuees take a Ions time to mobilize.
  • Inspection of Table 7-3 and Table 7-4 indicates that a staged evacuation provides no benefits to evacuees from within the 2 mile region and unnecessarily delays the evacuation of those beyond 2 miles (compare Regions R02, R04 through R09 with Grand Gulf Nuclear Station ES-4 KlD Engineering. P.C.

Evacuation T11ne Estimate Rev. 1 E-5

GG Revision 80 FSAR 02 / 2020 Regions R35 through R41, respectively, ln Tables 7-1 and 7-2) . See Section 7.6 fo r additional discussion.

  • Comparison of Scenarios 10 (winter, midweek/weekend, evening) and 11 (winter, weekend, evening) in Table 7-2 indicates that the special event does not materially affect the ETE at the 100th percentile, but increases the ETE at the 90th percentile for regions including PAS / PM 6 by up to 35 minutes . See Section 7.5 for additional discussion.
  • Comparison of Scenarios 1 and 12 in Table 7-1 indicates that the roadway clos ure - the closure of o ne lane on US 61 northbound from the boundary of Port Gibson to the EPZ th boundary (by the Claiborne County line) - does not have an impact o n the 90 percentile ETE. See Section 7 .5 for additional discussion.
  • Throughout the evacuation the EPZ is free from congestion, with the exception of the exit roadways from the Alcorn State University. The most congested area in t he network is SR 522 fro m the University to US 61 SB. By 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 20 minutes afte r the Advisory to Evacuate, traffic is moving at free-flow speed (LOS A) on all roadways within the EPZ (Scenario 6, R03 ). See Section 7.3 and Figures 7-3 through 7-7.
  • Se parate ETE were computed for schools, medical facilities, transit-depe ndent pe rsons, ho mebound special needs persons and correctional facilities . The average single-wave ETE fo r schools and medical facilities are within a similar range as the general population ETE at the 90 th percentile; the ETE for transit-dependents, homebound special need s persons and the correctional facil ity are slightly longer on average. See Section 8 .
  • Table 8-5 indicates t hat there a re sufficient trans portatio n resources available to evacuate the public schools in bo th the county and parish, but not all the transit-dependent population within the EPZ in a single wave. There are also not enough ambulances to evac uate the bedridde n po pulation in a single wave . The second-wave ETE for ambulances and special needs population does exceed the general po pulation ETE at the 9dh perce ntile. See Sections 8.4 and S.S.

th

  • The general po pulation ETE at the 100 pe rcentile closely fo llows the trip ge ne ration time due to a lack of congestion withi n the EPZ. The 90 th percentile ETE are less sensitive to truncating t he tail of the mobilization time distribution, since the mobilization time of the bulk of evacuees is unchanged. See Table M-1.
  • The general population ETE is insensitive to the voluntary evacuation of ve hicles in the Shadow Regio n (tripling the shadow evacuation percentage does not increase 90th or 100th percentile ETE). See Table M-2.
  • Population changes of SO and 75% do not result in ETE changes wh ich meet the criteria for updating ETE between decennial Censuses. A popu lation increase of 160% is needed to increase the 90th percentile ETE by 30 minutes . See Section M.3.

Grand Gulf Nuclear Station ES-S KW Engineering, P.C Evacuation nme Estimate Rev. I E-6

GG Revision 80 FSAR 02 / 2020

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~~ ~

GI GGNS

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MS / PAA C.n.:l l/li il/.-01

\,,-:.. 2, 5~ 10 Mlle IUng~ ~ t s . 1 1 . . . . . . 0.. 10

.. o ~... ( 1- . v Figure 6-1. GGNS EPZ PAS/ PAA Grand Gulf Nuclear Station ES-6 KLD Engineering, P.C.

Evacuation Time Estimate Rev.1 E- 7

GG Revision 80 FSAR 02 / 2020 Table 3-1. EPZ PenMnent Resident Population PAS/ PAA 2000 Population 2007 Population 2010 Population 1 104 100 43 2A 356 342 305 28 150 144 151 3A 983 946 961 38 506 487 388 4A 2,892 2,778 2,407 48 564 541 453 SA 163 156 138 58 396 381 356 6 2,057 2,258 2,629 7 3 3 28 8 163 148 126 9 1,892 1,708 1,185 10 4 31 388 394 11 1,530 1, 381 1,403 12 - - -

TOTAL 12.190 11,761 10,967 EPZ Population Growth (2000 to 2010): -10.03%

Grand Gulf Nudear Station ES-7 KlD Engineering. P.C.

Evacuation Time Estimate Rev. 1 E-8

GG Revision 80 FSAR 02 / 2020 Table 6-1. Description of Evacuation Regions Region Description 6 7 s I 9 I 10 RDl 2-Mile Rin RD2 5-Mile Rin RD3 Full EPZ Wind Direction Evacuate 2-Mile Radius and Downwind to S Miles PAS/PAA Region Toward 3A I 3B I 4A I 4B I SA I SB I 6 7 s I 9 I 10 RD4 WSW, W,WNW, N/A NNE RDS NE, ENE RD6 E RD7 ESE, SE, SSE ROB s RD9 SSW N/A SW Evacuate 2-Mlle Radius and Downwind to EPZ Bounda Wind Direction PAS/PAA Region Toward 2A I 2B I 3A I 3B I 4A I 4B I SA I SB I 6 7 s I 9 I 10 I 11 I 12 N/A N RlD NNE Rll NE.ENE R12 E R13 ESE R14 SE R15 SSE R16 s R17 SSW R18 SW R19 WSW R20 w Grand Gulf Nuclear Station ES-8 KLD Engineering, P.C.

Evacuation Time Estimate Rev.1 E-9

GG Revision 80 FSAR 02 / 2020 PAS/ PAA Region Description I 1 I 2A I 2B I 3A I 3B I 4A I 4B ! SA I SB I 6 I 7 R21 WNW R22 NW,NNW Region Wind Direction Toward I 1 I Evacuate 5-Mile Radius and Downwind to EPZ Bounda 2A I 2B I 3A I 3B I I 4A 4B PAS/ PAA I SA I SB I 6 I 7 I 8 I 9 I 10 N/A N R23 NNE R24 NE, ENE R25 E R26 ESE R27 SE R28 SSE R29 s R30 SSW R31 SW R32 wsw,w R33 WNW R34 NW,NNW Region Wind Direction Toward I 1 I Evacuate 2-Mlle Radius and Sta;ed Downwind to S Miles 2A I 2B I 3A I 3B I 4A I 4B I PAS / PAA SA I SB I 6 I 7 I 8 I 9 I 10 R35 5-Mile Rini R36 WSW, W,WNW, N/A NNE R37 NE, ENE R38 E R39 ESE, SE, SSE R40 s R41 SSW N/A SW Grand Gulf Nuclear Station ES-9 KLD Englneertng, P.C.

Evacuation Time Estimate Rev.1 1: - lU

GG Revision 80 FSAR 02 / 2020 Table 6-2. Evacuation Scenario Definitions Day of Time of l

Scenario Season Week Day Vlleather Special 1 Summer Midweek Midday Good None 2 Summer Midweek Midday Rain None 3 Summer Weekend Midday Good None 4 Summer Weekend Midday Rain None Midweek, 5 Summer Evening Good None Weekend 6 Winter Midweek Midday Good None 7 Winter Midweek Midday Rain None 8 Winter Weekend Midday Good None 9 Winter Weekend Midday Rain None Midweek, 10 Winter Evening Good None Weekend Alcorn State University 11 Wlnter Weekend Evening Good football game Roadway Impact- Lane 12 Summer Midweek Midday Good Closure on US 61 1

Winter assumes that school is in sess.ion (also applies to spring and autumn) . Summer assumes that school is not in session.

Grand Gulf Nuclear Station ES..10 KLD Engineering. P.C.

Evacuation Time Estimate Rev.I E-11

GG Revision 80 FSAR 02 / 2020 Table 7-L Time to dear the Indicated Area of 90 Percent of the Affected Population Summer Summer summer Winter Winter Winter Winter Summer Midweek Midweek Midweek Weekend Midweek Weekend Weekend Midweek Weekend Weekend (5) (6) (7) (8) {9) {10) (11) (12) Scenari Evening I

Midday Midday Evening Midday Midday Evening Midday Region I Good Weather I Rain Good Weather I Rain Good Weather Good Weather Rain Good Weather I Rain Good Weather Special Event Roadway Impact I Region Entire 2-Mile Region, 5-Mile Region, and EPZ ROl 1:30 1:30 1 :25 1:25 1:30 1:30 1:30 1:30 1:30 1:25 1:25 1:30 ROI R02 2:10 2:15 2:05 2:05 2:00 2:10 2:10 2:05 2:05 2:00 2:00 2:10 R02 R03 2:20 2:20 2:05 2:05 .2:00 2:15 2:15 2:00 2:05 2:00 2:30 2:20 R03 2-Mile Region and Keyhole to 5 Miles R04 1:30 1:30 1:25 1:25 1:30 1:30 1:30 1:30 1:30 1:25 1:25 1:30 R04 ROS 2:05 2:05 2:05 2:05 2:00 2:05 2:05 2:05 2:05 2:00 2:00 2:05 ROS R06 2:05 2:10 2:05 2:05 2:00 2:05 2:10 2:05 2:05 2:00 2:00 2:05 R06 R07 2:10 2:10 2:05 2:05 2:00 2:05 2:10 2:00 2:05 2:00 2:00 2:10 R07 R08 2:05 2:10 2:00 2:05 2:00 2:05 2:10 2:00 2:05 2:00 2:00 2:05 ROS R09 2 :00 2:05 2:00 2:05 2 :00 2:00 2:05 2:00 2:05 2:00 2:00 2:00 R09 2-Mile Region and Keyhole to 10 Miles RlO 2:05 2:05 2:05 2:05 2:05 2:05 2:05 2:05 2:05 2:00 2:00 2:05 RIO Rll 2:05 2:05 2:05 2:05 2:00 2:05 2:05 2:05 2:05 2:00 2:00 2:05 Rll R12 2:05 2:10 2:05 2:05 2:00 2:05 2:10 2:05 2:05 2:00 2:00 2:10 R12 R13 2:15 2:15 2:05 2:05 2:00 2:10 2:15 2:05 2:05 2:00 2:00 2:15 R13 R14 2:15 2:15 2:05 2:10 2:05 2:15 2:15 2:05 2:05 2:05 1:55 2:15 R14 R1S 2:10 2:15 2:05 2:05 2:00 2:10 2:10 2:05 2:05 2:00 1:55 2:10 R1S RI& 2:10 2:15 2:00 2:05 2:00 2:10 2:10 2:00 2:05 1:55 2:30 2:10 R16 R17 2:10 2:10 2:00 2:00 1:55 2:00 2:05 2:00 2:00 1:55 2:30 2:10 R17 R18 2:10 2:10 2:00 2:00 1:55 2:05 2:05 2:00 2:00 1:55 2:30 2:10 R18 R19 2:10 2:10 2:00 2:00 1:55 2:05 2:05 2:00 2:00 1:55 2:30 2:10 R19 R20 2:15 2:20 2:00 2:00 2:00 2:15 2:15 2:00 2:00 1:55 1:55 2:15 R20 R21 2:10 2:10 2:00 2:00 1:55 2:10 2:10 1:55 2:00 1:55 1:55 2:10 R21 R22 2:05 2:05 2:00 2:00 1:55 2:05 2:05 1:55 2:00 1:55 1:55 2:05 R22 Grand Gulf Nuclear Station ES-11 KLD Engineering, P.C.

Evacuation Time Estimate Rev. 1 E -12

GG Revision 80 FSAR 02 / 2020 Summer Summer Summer Winter Winter Winter Midweek Midweek Midweek Weekend Mid week Weekend Weekend Weekend Evening Region Good Good Good Good Good Good Rain Rain Rain Rain Weather weat her Weather Weather Weather Weather Event 5-Mlle Region and Keyhole to EPZ Boundary R23 2:10 2:15 2:05 2:10 2:00 2:10 2:15 2:05 2:05 2:00 2:00 2:10 R23 R24 2:10 2 :15 2 :05 2:10 2:00 2:10 2 :15 2 :05 2:05 2:00 2:00 2:10 R24 R25 2:10 2:15 2:05 2:05 2:00 2:10 2:15 2:05 2:05 2:00 2:00 2:10 R25 R26 2:15 2:15 2:05 2:10 2:00 2:10 2 :15 2:05 2:05 2:00 2:00 2:15 R26 R27 2:15 2:15 2:05 2:10 2:00 2:15 2 :15 2:05 2:05 2:00 1:55 2:15 R27 R28 2:15 2 :15 2:05 2:10 2:00 2:10 2 :15 2:05 2 :05 2:00 1:55 2 :15 R28 R29 .2:15 2:15 2:05 2:05 2:00 2:10 2:10 2:05 2:05 2:00 2:30 2:15 "R29 R30 2 :15 2:15 2:05 2:05 2:00 2:10 2:10 2:00 2:05 2:00 2:30 2:15 R30 R31 2:15 2:15 2:00 2:05 2:00 2:10 2:10 2:00 2:05 2 :00 2:30 2:15 R31 R32 2:15 2:15 2 :05 2:05 2:00 2:15 2:15 2:05 2 :05 2 :00 2:00 2:15 R32 R33 2:15 2:15 2:05 2:05 2:00 2:15 2:15 2:05 2:05 2:00 2:00 2:15 R33 R34 2 :10 2:15 2:05 2:05 2:00 2:10 2:15 2:05 2:05 2 :00 2:00 2:10 R34 Staged Evacuation Mile Region, 2-Mile Region and Keyhole to 5 Miles R3S 2 :10 2:15 2:05 2:05 2:00 2:10 2 :10 2:05 2:05 2:00 2:00 2:10 R3S R36 1:35 1 :35 1:45 1 :45 1:45 1:35 1:35 1:40 1:40 1 :45 1 :45 1:35 R36 R37 2:05 2:05 2:05 2:05 2:00 2:05 2:05 2:05 2:05 2:00 2:00 2:05 R37 R38 2 :05 2 :10 2 :05 2:05 2:00 2:05 2:10 2:05 2:05 2 :00 2:00 2:05 R38

-R39 2:10 2:10 2:05 2:05 2:00 2:05 2:10 2:00 2:05 2:00 2:00 2:10 R39 R40 2:05 2 :10 2:00 2 :05 2:00 2:05 2:10 2 :00 2:00 1:55 1:55 2 :05 R40 R41 2:00 2:05 2:00 2 :00 1:55 2:00 2:05 2:00 2:00 1:55 1:55 2:00 R41 Grand Gulf Nuclear Station ES-12 KLD Engineering. P.C.

Evacuation Time Estimate Rev. 1 E -13

GG Revision 80 FSAR 02 / 2020 Table 7-2. Time to Clear the Indicated Area of !QQ_Percent of the Affected Population Summer Summer Summer Winter Winter Winter I Winter I Summer Midweek Weekend Midweek Weekend Midweek Weekend Midweek I Weekend Weekend I.Midweek (2) (3) (4) (5) (6) (7) (8) (9) (10)

Midday Midday Evening Midday Midday Evening Evening Midday Region I Good Weather I Rain Good Weather I Rain Good Weather Good Weather I Rain Good Weather I Rain Good Weather Special Event Roadway Impact I Region Entire 2-Mile Region, 5-Mile Region, and EPZ R01 4 :45 4 :45 4:45 4 :45 4 :45 4:45 4:45 4 :45 4:45 4:45 4:45 4:45 R01 R02 4 :50 4 :50 4:50 4:50 4:50 4 :50 4:50 4:50 4:50 4 :50 4:50 4:50 ROZ R03 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 R03 2-Mile Region and Keyhole to 5 Miles R04 4:50 4 :50 4:50 4:50 4:50 4:50 4 :50 4:50 4 :50 4:50 4:50 4 :50 R04 ROS 4:50 4:50 4:50 4:50 4 :50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 ROS R06 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4 :50 R06 R07 4:50 4 :50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 R07 ROS 4:50 4 :50 4:50 4:50 4:50 4:50 4:50 4 :50 4:50 4 :50 4:50 4:50 ROS R09 4:50 4:50 4:50 4 :50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 R09 2-Mile Region and Keyhole to 10 Miles RlO 4 :55 4 :55 4:55 4 :55 4:55 4:55 4 :55 4 :55 4:55 4:55 4:55 4 :55 RlO R11 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 R11 R12 4:55 4:55 4:55 4 :55 4 :55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 R12 R13 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4 :55 4:55 4:55 R13 R14 4:55 4:55 4:55 4:55 4 :55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 R14 R1S 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 R15 R16 4:55 4:55 4:55 4 :55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 R16 R17 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 R17 RU 4:55 4 :55 4:55 4:55 4:55 4:55 4 :55 4:55 4:55 4:55 4:55 4:55 R18 R19 4:55 4:55 4:55 4 :55 4 :55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 R19 R20 4:55 4:55 4:55 4 :55 4:55 4:55 4 :55 4 :55 4:55 4 :55 4:55 4:55 R20 R21 4:55 4:55 4:55 4:SS 4:55 4:55 4:55 4 :55 4:55 4:55 4:55 4:55 R21 R22 4:55 4:55 4:55 4 :55 4:55 4:55 4 :55 4:55 4 :55 4:55 4 :55 4:55 R22 Grand Gulf Nuclear Station ES-13 KLD Engineering. P.C.

Evacuation Time Estimate Rev.1 E-14

GG Revision 80 FSAR 02 / 2020 Summer Summer Winter Winter Winter Winter Summer Midweek Weekend Midweek Weekend Midweek Midday Midday Evening Midday Midday Evening Evening Midday Region I Good Rain Good Rain Good Good Rain Good Rain Good special Roadway I Region Weather Weather Weather Weather Weather Weather Event Impact 5-Mile Region and Keyhole to EPZ Boundary R23 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 R23 R24 4:55 4:55 4:55 4:55 4:55 4:55 4 :55 4 :55 4 :55 4 :55 4 :55 4:55 R24 R25 4:55 4:SS 4:55 4:55 4:55 4 :55 4:55 4 :55 4:55 4:55 4:55 4:55 R25 R26 4:55 4:55 4:55 4 :55 4:55 4:55 4 :55 4:55 4:55 4 :55 4 :55 4:55 R26 R27 4:SS 4:55 4:55 4:55 4:55 4:55 4 :55 4:55 4:55 4:55 4:55 4:55 R27 R28 4:55 4 :55 4:55 4:55 4 :55 4:55 4 :55 4 :55 4:55 4 :55 4 :55 4:55 R28 R29 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 R29 R30 4:55 4 :55 4:55 4:55 4 :55 4:55 4:55 4:55 4:55 4:55 4 :55 4:55 R30 R31 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 R31 R32 4:55 4:55 4:55 4 :55 4 :55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 R32 R33 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 4:55 R33 R34 4:55 4:55 4:55 4 :55 4 :55 4:55 4 :55 4 :55 4:55 4 :55 4 :55 4:55 R34 Staged Evacuation

  • 5-Mile Region, 2-Mile Region and Keyhole to 5 Miles R35 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 R35 R36 4:50 4:50 4:50 4 :50 4:50 4 :50 4:50 4:50 4:50 4:50 4:50 4:50 R36 R37 4:50 4:50 4:50 4 :50 4:50 4 :50 4:50 4:50 4:50 4:50 4 :50 4:50 R37 R38 4 :50 4:50 4:50 4:50 4:50 4:50 4 :50 4 :50 4:50 4:50 4:50 4:50 R38 R39 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 R39 R40 4:50 4:50 4:50 4:50 4:50 4 :50 4 :50 4 :50 4:50 4 :50 4 :50 4:50 R40 R41 4:50 4 :50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4 :50 4 :50 4:50 R41 Grand Gulf Nuclear Station ES-14 KLD Engineering, P.C.

Evacuation Time Estimate Rev. 1 E -15

GG Revision 80 FSAR 02 / 2020 Table 7-3. Time to aear 90 Percent of the 2-Mile Area within the Indicated Region Summer summer summer Winter Winter Winter Winter Summer Midweek Midweek Midweek Weekend Midweek Weekend Weekend Midweek Weekend Weekend Midday Midday Midday Midday Region Good Good Good Good Rain ... .. Rain

      • eather Rain Weather Rain 2-Mile and 5-Mile Region ROl 1:30 1:30 1:25 1:25 1:30 1:30 1:30 1:30 1:30 1:25 1:25 1:30 ROl R02 1:30 1:30 1:25 1:25 1:30 1:30 1 :30 1:30 1:30 1:25 1:25 1:30 R02 2-Mile Region and Keyhole to S Miles R04 1:30 1:30 1:25 1:25 1:30 1:30 1:30 1:30 1:30 1:25 1:25 1:30 R04 ROS 1:30 1:30 1:25 1:25 .1:30 1:30 1:30 1:30 1:30 1:25 1:25 1:30 ROS R06 1:30 1:30 1:25 1:25 1:30 1:30 1:30 1:30 1:30 1:25 1:25 1:30 R06 R07 1:30 1:30 1:25 1:25 1:30 1:30 1:30 1:30 1:30 1:25 1:25 1:30 R07 ROS 1:30 1:30 1:25 1:25 1:30 1:30 1:30 1:30 1:30 1:25 1:25 1:30 ROS R09 1:30 1:30 1:25 1:25 1:30 1:30 1:30 1:30 1:30 1:25 1:25 1:30 R09 Staged Evacuation Mile Region, 2-Mile Region and Keyhole to 5 Miles R35 1:35 1:35 1:45 1:45 1:45 1:35 1:35 1:40 1:40 1:45 1:45 1:35 R35 R36 1:35 1:35 1:45 1:45 1:45 1:35 1:35 1:40 1:40 1:45 1:45 1:35 R36 R37 1:35 1:35 1:45 1:45 1:45 1:35 1:35 1:40 1:40 1:45 1:45 1:35 R37 R38 1:35 1:35 1:45 1:45 1:45 1:35 1:35 1:40 1:40 1:45 1:45 1:35 R38 R39 1:35 1:35 1:45 1:45 1:45 1:35 1:35 1:40 1:40 1:45 1:45 1:35 R39 R40 1:35 1:35 1:45 1:45 1:45 1:35 1:35 1:40 1:40 1:45 1:45 1:35 R40 R41 1:35 1:35 1:45 1:45 1:45 1:35 1:35 1:40 1:40 1:45 1:45 1:35 R41 Grand Gulf Nuclear Station ES-15 KLD Engineering, P.C.

Evacuation Time Estimate Rev.I E - 16

GG Revision 80 FSAR 02 / 2020 Table 7-4. Time to Clear 100 Percent of the 2-Mile Area within the Indicated Region summer I Summer Winter Winter Winter Winter Summer Weekend Midweek Midday Midday Evening Midday Midday Evening Evening Midday Region Good Good Rain Rain Good Good Rain Good Rain Good Special Roadway I Region Weather Weather Weather Weather Weather Weather Event Impact 2-Mile and 5-Mile Region ROl 4:45 4:45 4:45 4:45 4:45 4:45 4:45 4:45 4:45 4:45 4:45 4:45 R01 R02 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 R02 2-Mile Region and Keyhole to 5 Miles R04 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 R04 ROS 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 ROS R06 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 RO&

R07 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 R07 ROS 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 ROS R09 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 R09 Staged Evacuation Mile Region, 2-Mile Region and Keyhole to 5 Miles R35 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 R35 R36 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 R36 R37 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 R37 R38 4:50 4:50 4:50 4:50 4:50 4 :50 4:50 4 :50 4:50 4:50 4:50 4:50 R38 R39 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 R39 R40 4:50 4:50 4:50 4 :50 4:50 4:50 4:50 4 :50 4:50 4:50 4:50 4:50 R40 R41 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 4:50 R41 Grand Gulf Nuclear Station ES-16 KLD Engineering. P.C.

Evacuation Tlme Estimate Rev.1 E -17

GG Revision 80 FSAR 02 I 2020 Table 8-7. School Evacuation Time Estimates -Good Weather Travel Dist. Time Driver Dist . Travel EPZ from Mobili- To Time to Bdry EPZ Second Second zation Loading EPZ Average EPZ to Bdry to ETE to Bus Ready Wave Wave Tinle Time Bdry Speed Bdry ETE R.C. R.C. R.C. For Second ETE ETE to Schoo l (min) {min) (mi) (mph) (min) (hr:min) (mi.) (min) {hr:min) Wave (min) (hr:min) R.C.

.* CLAIBORNE SCHOOLS A.W . Watson Elementary School 90 15 6 .1 42.8 9 1:55 39.1 52 2:50 240 4:25 5:15 Richardson Headstart 90 15 5.9 43.8 8 1:55 39.1 52 2:45 240 4:25 5:15 Chlld Day Care Kindergarten 90 15 5.9 43.8 8 1:55 39.1 52 2:45 240 4~ 5:15 Heavenly Angels Daycare 90 15 4.2 51.3 5 1:50 39.1 52 2:45 238 4:20 5:10 Port Gibson High 90 15 5.6 47.0 7 1:55 39.1 52 2:45 239 4:25 5:15 Oalborne County Vo-Tech 90 15 5.7 45.0 8 1:55 39.1 52 2:45 240 4:25 5:15 Katherine's Daycare and Learning 90 15 6.1 42.9 9 1:55 39.1 52 2:50 240 4:25 5:15 Port Gibson M iddle School 90 15 4 .7 48.0 6 1:55 39.1 52 2:45 238 4:20 5:15 Concerned atlzens Daycare 90 15 4 .7 48.0 6 1:55 39.1 52 2:45 238 4:20 5:15 Chamberlain-Hunt Academy 90 15 4.7 48.0 6 1:55 39.1 52 2:45 238 4:20 5:15 Little Kids University 90 15 4.7 48.0 6 1:55 39.1 52 2:45 238 4:20 5:15 Oalborne Educational Foundation 90 15 4.2 51.3 5 1:50 39.1 52 2:45 238 4:20 5:10 God's Uttle Bee's Child Care 90 15 6.2 46.9 8 1:55 39.1 52 2:45 240 4:25 5:15 2:25 230 4:10 Little Green Nursery 90 15 3.7 33.7 7 1:55 25.9 35 2:30 180 3:25 4:00 Tensas Academy 90 15 3.7 33.7 7 1:55 35.4 47 2:40 180 3:25 4:10 Tensas High School 90 15 2.5 37.7 4 .1:50 35.4 47 2:40 180 3:20 4:10 Tensas Elementarv 90 15 2.5 37.7 4 1:50 35.4 47 2:40 180 3:20 4 :10

- - Maximum for £PZ: 1:55 Maximum: 2:50 Maximum: ~ 5:15 Average for EPZ: . 1:50 _ Average: '2:45 Average: 4:10 - S:OD Grand Gulf Nuclear Station ES-17 KLD Engineering, P.C.

Evaruatlon Time Estimate Rev.1 E -18

GG Revision 80 FSAR 02 / 2020 Table 8-10. Transit-Dependent Evacuation Tlrne Estimates - Good Weather One-Wave Two-Wave Route Travel Route Route Travel Pickup Oistance Time to Driver Travel Pickup Route 8LJ5 Mobilization Length Speed Time Time ETE to R. C. R. C. Unload Rest Time Time ETE Nu,nb e r Nun,ber (min) (miles) (mph) (min) (min) (hr:min) (miles) (min) (min) (min) (min) (min) (hr .m in) 1 I 1 105 12.4 55.0 14 30 2:30 22.0 29 5 10 59 30 4:45 3 105 6.0 52.4 7 30 2;25 39.1 52 5 10 67 2 30 5:10 2 120 6 .0 51.7 7 30 2:40 39.1 52 5 10 67 30 5:25 3 I 1 105 7 .5 55.0 8 30 2:25 25.9 35 5 10 53 30 4:40 2 105 5 .6 39.8 8 30 2:25 35.4 47 5 10 63 4 30 5:00 2 120 5 .6 42.6 8 30 2:40 35.4 47 5 10 64 30 5:15 1 105 1.2 41.4 2 30 2:20 33.4 45 5 10 48 30 5 4:40 I

1 120 1.2 41.3 2 30 2:35 33.4 45 5 10 48 30 4:55 4 105 3 .1 39.3 5 30 2:20 38.1 51 5 10 60 30 6 5:00 2 120 3 .1 39.3 5 30 2:35 38.1 51 5 10 60 30 5:15 2 105 5.5 55.0 6 30 2:25 18.1 24 5 10 37 30 4:15 7

1 120 5.5 55.0 6 30 2::40 18.1 24 5 10 37 30 4:30 Maximum ETE:

~

Average ETE: _ 2:30 Maximum ETE:

Average ETE:

Grand Gulf Nuclear Station ES-18 KLD Engineering, P.C.

Evacuation Time Estimate Rev. 1 E-19

GG Revision 80 FSAR 02 / 2020 APPENDIX F List of Supporting Plans F-1

GG Revision 80 FSAR 02 / 2020 APPENDIX F - LIST OF SUPPORTING PLANS

1. Mississippi Radiological Emergency Preparedness Plan; Volume ill, to the Mississippi Comprehensive Emergency Management Plan
2. Port Gibson/Claiborne County - Radiological Emergency Preparedness Plan
3. Louisiana Peacetime Radiological Response Plan; Supplement 11, Fixed Nuclear Facilities to Louisiana Emergency Operations Plan. Attachment 2, Grand Gulf Nuclear Station
4. Louisiana Peacetime Radiological Response Plan; Supplement II, Fixed Nuclear Facilities to Louisiana Emergency Operations Plan Attachment 2, Grand Gulf Nuclear Station, Enclosure I, Tensas Parish Radiological Emergency Response Plan
5. Hospital Emergency Department Management of Radiation Accidents F-2

GG Revision 80 FSAR 02 / 2020 APPENDIX G NUREG 0654 Cross Reference G -1

GG Revision 80 FSAR 02 I 2020 Planning Standards and Evaluation Criteria A. Assignment of Responsibility Organization Control)

Planning Standard Primary responsibilities for emergency response by the nuclear facility licensee, and by state and local organizations within the Emergency Planning Zones have been assigned, the emergency responsibilities of the various supporting organizations have been specifically established, and each principal response organization has staff to respond and to augment its initial response on a continuous basis.

Evaluation Criteria Cross Reference to Plan

1. a. Each plan shall identify the state, local, federal and private sector Sections 2.4.3, 5.6, 5. 7, organizations (including utilities), that are intended to be part of the 5.8 overall response organization for Emergency Planning Zones. (See Appendix 5).
b. Each organization and suborganization having an operational role Sections 2.3.1, 2.3.2, shall specify its (All) concept of operations, and its relationship to 2.4.1, 2.4.2, 5.0 the total effort.

C. Each plan shall illustrate these interrelationships in a block diagram. Figure 5-5

d. Each organization shall identify a specific individual by title who Sections 5.4.1, 5.4.2 shall be in charge of the emergency response.
e. Each organization shall provide for 24-hour per day emergency Sections 5.4, 7.5, response, including 24-hour per day manning of communications Table 5-1 links.
2. a. Each organization shall specify the functions N/A and responsibilities for major elements and key individuals by title, of emergency response, including the following Command and Control, Alerting and Notification, Communications, Public information, Accident Assessment, Public Health and Sanitation, Social Services, fire and Rescue, Traffic Control, Emergency Medical Services, Law Enforcement, Transportation, Protective Response (including authority to request federal assistance and to initiate other protective actions), and Radiological Exposure Control. The description of these functions shall include a clear and concise summary such as a table of primary and support responsibilities using the agency as one axis, and the function as the other. (See Section B for licensee.)
b. Each plan shall contain (by reference to specific acts, codes or N/A statutes) the legal basis for such authorities.

3 Each plan shall include Written agreements referring to the concept of operations developed between federal, state, and and local agencies and other support organizations having G-2

GG Revision 80 FSAR 02 / 2020 Evaluation Criteria Cross Reference to Plan organ izations having an emergency response role within the Emergency Planning Zones. The agreements shall identify the emergency measures to be provided and the mutually acceptable criteria for their implementation and specify the arrangements for exchange of information. These agreements may be provided in an appendix to the plan or the plan itself may contain descriptions of these matters and a signature page in the plan may serve to verify the agreements. The signature page format is appropriate for organizations where response functions are covered by laws, regulations or executive orders where separate written agreements are not necessary.

4. Each principal organization shall be capable of continuous (24*hour) Section 5.7 operations for a protracted period. The individual in the principal organization who will be responsible for assuring continuity of resources (technical, administrative, and material) shall be specified by title.

B. ONSITE EMERGENCY ORGANIZATION

1. Each licensee shall specify the onsite emergency organization of Section 5.2, 5.4, Fig 5-2, plant staff personnel for all shifts and its relation to the 5-3 responsibilities and duties of the normal staff complement
2. Each licensee shall designate an individual as emergency Sections 5. 4.1 coordinator who shall be on shift at all times and who shall have the authority and responsibil ity to immediately and unilaterally initiate any emergency actions, including providing protective action recommendations to authorities responsible for implementing offsite emergency measures.
3. Each licensee shall identify a line of succession for the emergency Section 5.4.2 coordinator position and identify the specific conditions for higher level utility officials assuming this function
4. Each licensee shall establish the functional responsibilities assigned Sections 5.4.2 to the emergency coordinator and shall clearly specify which responsibilities may not be delegated to other elements of the emergency organization. Among the responsibilities which may not be delegated shall be the decision to notify and to recommend protective actions to authorities responsible for offsite emergency measures.
5. Each licensee shall specify the positions or title and major tasks Sections 5.4, Table 5-1 to be performed by the persons to be assigned to the functional areas of emergency activity. For emergency situations, specific assignments shall be made for all shifts and for plant staff members, both onsite and away from the site. These assignments shall cover the emergency functions in Table B* I entitled, "Minimum Staffing Requirements for Nuclear Power Plant Emergencies." The minimum on-shift staffing levels shall be as indicated in Table 8-1.

G-3

GG Revision 80 FSAR 02 / 2020 Evaluation Criteria Cross Reference to Plan The licensee must be able to augment on-shift capabilities within a short period after declaration of an emergency. This capability shall be as indicated in Table B* I. The implementation schedule for licensed operators, auxiliary operators and the shift technical advisor on shift shall be as specified in the July 31, 1980 letter to all power reactor licensees.

Any deficiencies in the other staffing requirements of Table 8-1 must be capable of augmentation within 30 minutes by September 1, 1981, and such deficiencies must be fully removed by July 1, 1982.

6. Each licensee shall specify the interfaces between and among the Figure S-5 onsite functional areas of emergency activity, licensee headquarters support, local services support, and state and local government response organization. This shall be illustrated in a block diagram and shall include the onsite technical support center and the operational support (assembly) center and the licensee's near-site Emergency Operations Facility (EDF).
7. Each licensee shall specify the corporate management, Sections 5.4 administrative Sections and technical support personnel who will augment the plant staff as specified in the table entitled "Minimum Staffing Requirements for Nuclear Power Plant Emergencies," (Table B* 1) and in the following areas:
a. logistics support for emergency personnel, e.g., transportation, Sections S.4.6 communications, temporary quarters, food and water, sanitary facilities in the field, and special equipment and supplies procurement;
b. technical support for planning and reentry/recovery operations; Sections 5.4.24, 5.4.27, 5.5
c. management level interface with governmental authorities; and Sections 5.4.2
d. release of information to news media during an emergency Sections 5.4.2 (coordinated with governmental authorities}.
8. Each licensee shall specify the contractor and private organizations Sections 5.8 who may be requested to provide technical assistance to and augmentation of the emergency organization.
9. Each licensee shall identify the services to be provided by local Sections 5.6, S.7.3, agencies for handling emergencies, e.g., police, ambulance, medical, 5.7.4 hospital, and fire-fighting organizations shall be specified. The Appendix D licensee shall provide for transportation and treatment of injured personnel who may also be contaminated. Copies of the arrangements and agreements reached with contractor, private, and local support agencies shall be appended to the plan. The agreements shall delineate the authorities, responsibilities, and limits on the actions of the contractor, private organization, and local services support groups.

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GG Revision 80 FSAR 02 / 2020 C. Emergency Response Support and Resources Planning Standard Arrangements for requesting and effectively using assistance resources have been made, arrangements to accommodate state and local staff at the licensee's near-site Emergency Operations facility have been made, and other organizations capable of augmenting the planned response have been identified.

Eva luation Criteria Cross Reference to Plan

1. The Federal government maintains in-depth capability to assist licensees, states and local governments through the Federal Radiological Monitoring and Assessment Plan (formerly Radiological Assistance Plan (RAP) and lnteragency Radiological Assistance Plan (RAP). Each state and "licensee shall make provisions for incorporating the federal response capability into its operation plan, including the following :
a. specific persons by t it le authorized to request federa l assistance; see Sections 5.4.2 A.1. d, A.2.a .
b. specific federal resources expected, including expected t imes of arrival Sections 5.7.5, 5.7.6 at specific nuclear faci lity sites; and
c. specific licensee, state and local resources available to support the Section 5.9 federal response, e.g., air fields, command posts, telephone lines, radio frequencies and telecommun ications centers.
2. a. Each principal offsite organization may dispatch representatives to the N/A licensee's near-site Emergency Operations Facility. (State technical analysis representatives at the nearsite EOF are preferred.)
b. The licensee sha ll prepare for the dispatch of a representative to Sections 5.4.11 principal offsite governmental agency operations centers.
3. Each organization shall identify radiological laboratories and their Section 7.6.3 general capabilities and expected availability to provide radiological monitoring and analyses services which can be used in an emergency.
4. Each organization shall identify nuclear and other facilities, Sections 5.6, 5.7, 5.8 organizations or individuals which can be relied upon in an emergency Appendix D to provide assistance. Such assistance shall be identified and supported by appropriate letters of agreement.

D. Emergency Classification System Planning Standard A standard emergency classification and action level scheme, the bases of which include facil ity system and effluent parameters, is in use by the nuclear faci lity licensee, and state and local response plans call for reliance on information provided by facility licensees for determ inations of minimum initial offsite response measures G-5

GG Revision 80 FSAR 02 / 2020 Evaluation Criteria Cross Reference to Plan

1. An emergency classification and emergency action level scheme as set Section 4-1 forth in Appendix I must be established by the licensee. The specific Table 4-1 instruments, parameters or equipment status shall be shown for establishing each emergency class, in the in-plant emergency procedures. The plan shall identify the parameter values and equipment status for each emergency class.
2. The initiating conditions shall include the example conditions found in Sections 4.1, 4.2 Appendix 1 and all postulated accidents in the Final Safety Analysis Table 4-2 Report (FSAR) for the nuclear facility.
3. Each state and local organization shall establish an emergency N/A classification and emergency action level scheme consistent with that established by the facility licensee.
4. Each state and local organization should have procedures in place that N/A provide for emergency actions to be taken which are consistent with the emergency actions recommended by the nuclear facility licensee, taking into account local offsite conditions that exist at the time of the emergency.

E. Notification Methods and Procedures Planning Standard Procedures have been established for notification, by the licensee of state and local response organizations and for notification of emergency personnel by all response organizations; the content of initial and follow up messages to response organizations and the public has been established; and means to provide early notification and clear instruction to the populace within the plume exposure pathway Emergency Planning Zone have been established.

Evaluation Criteria Cross Reference to Plan

1. Each organization shall establish procedures which describe mutually Sections 4.1, 6.2.2, agreeable bases for notification of response organizations consistent 6.2.4 with the emergency classification and action level scheme set forth in Figure 6-2 Appendix 1. These procedures shall include means for verification of messages. The specific details of verification need not be included in the plan.
2. Each organization shall establish procedures for alerting, notifying, and Sections 4.0, 6.2, mobilizing emergency response personnel. 7.5.3.a.3 G-6

GG Revision 80 FSAR 02 / 2020

3. The licensee in conjunction with state and local organizations shall Section 6.2.4 establish the contents of the initial emergency messages to be sent from Figure 6-2 the plant. These measures shall contain information about the class of emergency, whether a release is taking place, potentia lly affected population and areas, and whether protective measures may be necessary.
4. Each licensee shall make provisions for followup messages from the faci lity Section 6.2.4 to offsite authorities which shall contain the following information if it is Figu re 6-2 known and appropriate:
a. location of incident and name and telephone number (or commun ications channel identification) of caller;
b. date/time of incident;
c. class of emergency;
d. type of actual or projected release (airborne, waterborne, surface spil l), and estimated duration/impact times;
e. estimate of quantity of radioactive mate rial released or being released and the points and height of releases;
f. chemical and physical form of released material, includ ing estimates of the relative quantities and concentration of noble gases, iodines and particu lates;
g. meteorological conditions at appropriate levels (wind speed, direction (to and from}, indicator of stability, precipitation, if any);
h. actual or projected dose rates at site boundary; projected integrated dose at site boundary; projected dose rates and integrated dose at the projected peak and at 2, 5 and I 0 mi les,
i. including sector{s) affected;
j. estimate of any surface radioactive contam ination inplant onsite or offsite;
k. licensee emergency response actions underway; I. recommended emergency actions, including protective measures;
m. request for any needed onsite support by offsite organizations; and
n. prognosis for worsening or termination of event based on plant information.

S. State and local government organizations shall establish a system for N/A disseminating to the publi c appropriate information contained in initial and followup messages received from the licensee including the appropriate notification to appropriate broadcast media, e.g., the Emergency Broadcast System (EBS).

6, Each organization shall establish adm inistrative and physical means, and Section 7.5.4 the time required for notifying and providing prompt instructions to the public within the plume exposure pathway Emergency Planning Zone. (See Appendix 3.) It shall be the licensee's responsibility to demonstrate that such means exist, regardless of who implements this requirement. It shall be the responsibility of the state and local governments to activate such a system.

7. Each organization shall provide written messages intended for the public. Sections consistent with the licensee's classification scheme. In particular, draft 6.5.1,8.7 messages to the public giving instructions with regard to specific protective actions to be taken by occupants of affected areas shall be Appendix H prepared and included as part of the state and local plans. Such messages should include the appropriate aspects of sheltering, ad hoc respiratory protection, e.g., handkerchief G-7

GG Revision 80 FSAR 02 / 2020 over mouth, thyroid blocking or evacuation. The role of the licensee is to provide supporting information for the messages. For ad hoc respiratory protection see "Respiratory Protective Devices Manual" American Industrial Hygiene Association, 1963 pp. 123-126.

F. Notification Methods and Procedures Planning Standard Provisions exist for prompt communications among principal response organizations 10 emergency personnel and to the public.

Evaluation Criteria Cross Reference to Plan

1. The communications plans for emergencies shall include organizational titles and alternates for both ends of the communication links. Each organization shall establish reliable primary and backup means of communication for licensees, local, and stale response organizations. Such systems should be selected to be compatible with one another. Each plan shall include:
a. provision for 24-hour per day notification to and activation of the Sections 5.2, 5.4, state/local emergency response network; and at a minimum, a 7.5 telephone link and alternate, including 24-hour per day manning of communications links that initiate emergency response actions.
b. provision for communications with contiguous state/local governments Sections 6.2.4, 7.5 within the Emergency Planning Zones;
c. provision for communications as needed with federal emergency Sections 6.2.4, 7.5 response organizations;
d. provision for communications between the nuclear facility and the Sections 7.5 licensee's near-site Emergency Operations Facility, state and local emergency operations centers, and radiological monitoring teams;
e. provision for alerting or activating emergency personnel in each Sections 6.2 response organization; and
f. provision for communication by the licensee with NRC headquarters Sections 7.5 and NRC Regional Office Emergency Operations Centers and the licensee's near-site Emergency Operations Facility and radiological monitoring team assembly area.
2. Each organization shall ensure that a coordinated communication link Sections 6.7.3 for fixed and mobile medical support facilities exists.
3. Each organization shall conduct periodic testing of the entire Sections 7.5, 8.3.2 emergency communications system (see evaluation criteria H. 10, N.2.a and Appendix 3).

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GG Revision 80 FSAR 02 I 2020 G. Public Education and Information Planning Standard Information is made available to the public on a periodic basis on how they will be notified and what their initial actions should be in an emergency (e.g., listening to a local broadcast station and remaining indoors),

the principal points of contact with the news media for dissemination of information during an emergency (including the physical location or locations) are established in advance, and procedures for coordinated dissemination of information to the public are established.

Evaluation Criteria Cross Reference to Plan

1. Each organ ization shall provide a coordinated periodic (at least Section 8.7 annually) dissemination of information to the public regarding how Appendix H they will be notified and what their actions should be in an emergency.

This information shall include, but not necessarily be limited to:

a. educational information on radiation;
b. contact for additional information;
c. protective measures, e.g., evacuation routes and relocation centers, sheltering, respiratory protection, radioprotective drugs; and
d. special needs of the handicapped.

Means for accomplishing this dissemination may include, but are not necessarily limited to:

information in the telephone book; periodic information in utility bills; posting in public areas; nd publications distributed on an annual basis.

2. The public information program shall provide the permanent and Section 8.7 transient adult population within the plume exposure EPZ an adequate Appendix H opportun ity to become aware of the information annually. The programs should include provision for written material that is likely to be available in a residence during an emergency. Updated information shall be disseminated at least annually. Signs or other measures (e.g.,

decals, posted notices or other means, placed in hotels, motels, gasoline stations and phone booths} shall also be used to disseminate to any transient population within the plume exposure pathway EPZ appropriate information that would be helpful if an emergency or accident occurs. Such notices should refer the transient to the telephone directory or other source of local emergency information and guide the visitor to appropriate rad io and television frequencies.

3. a. Each principal organ ization shall designate the points of contact and Section 7.3.S physical locations for use by news media during an emergency. Appendix H
b. Each licensee shall provide space which may be used for a limited number of the news media at the nearsite Emergency Operations Facility.

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GG Revision 80 FSAR 02 / 2020 Evaluation Criteria Cross Reference to Plan

4. a. Each principal organization shall designate a spokesperson who should Sections S.4.34 have access to all necessary information. Appendix H
b. Each organization shall establish arrangements for timely exchange of Sections 7.3.5, 8.8 information among designated spokespersons. Appendix H
c. Each organization shall establish coordinated arrangements for dealing Sections 7.3.5 with rumors. Appendix H
5. Each organization shall conduct coordinated programs at least annually Sections 8.8 to acquaint news media with the emergency plans, information Appendix H concerning radiation, and points of contact for release of public information in an emergency.

H. Emergency Facilities and Equipment Planning Standard Adequate emergency facilities and equipment to support the emergency response are provided and maintained.

Evaluation Criteria Cross Reference to Plan

1. Each licensee shall establish a Technical Support Center and an onsite Sections 7.3.1, 7.3.2 operations support center (assembly area) in accordance with NUREG-0696, Revision 1.
2. Each licensee shall establish an Emergency Operations facility from Sections 7.3.3, 7.3.4 which evaluation and coordination of all licensee activities related to an emergency is to be carried out and from which the licensee shall provide information to federal, state and local authorities responding to radiological emergencies in accordance with NUREG-0696, Revision 1.
3. Each organization shall establish an emergency operations center for N/A use in directing and controlling response functions.
4. Each organization shall provide for timely activation and staffing of the Section 4.1, 5.4, 6.1, facilities and centers described in the plan. 6.24, 7.3 S. Each licensee shall identify and establish onsite monitoring systems that are to be used to initiate emergency measures in accordance with Appendix 1, as well as those to be used for conducting assessment.

The equipment shall include:

a. geophysical phenomena monitors, Sections 7.6 (e.g., meteorological, hydrologic, seismic);

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GG Revision 80 FSAR 02 / 2020 Evaluation Criteria Cross Reference to Plan

b. radiological monitors, (e.g., process, area, emergency, effluent, wound Sections 7.6 and portable monitors and sampling equipment);
c. process monitors, {e.g., reactor coolant system pressure and Sections 7.6 temperature, containment pressure and temperature, liquid levels, flow rates, status or lineup of equipment components); and
d. fire and combustion products detectors. Sections 7.6
6. Each licensee shall make provision to acquire data from or for emergency access to offsite monitoring and analysis equipment including:
a. geophysica l phenomena monitors, (e.g., meteorological, hydrologic, Sections 7.6 seismic);
b. radiological monitors including ratemeters and sampling devices. Sections 7.6 Dosimetry shall be provided and shalt meet, as a minimum, the NRC Radiological Assessment Branch Technical Position for the Environmental Radiological Monitoring Program; and
c. laboratory facilities fixed or mobi le. Sections 7.6
7. Each organization, where appropriate, shall provide for offsite Sections 7.6.2 radiological monitoring equipment in the vicinity of the nuclear facility.
8. Each licensee shall provide meteorological instrumentation and Sections 7.6.1.e.2 procedures which satisfy the criteria in Appendix 2, and provisions to obtain representative current meteorological information from other sources.
9. Each licensee shall provide for an onsite operations support center Sections 7.3.2 (assembly area) which shall have adequate capacity, and supplies, Appendix B including, for example, respiratory protection, protective clothing, portable lighting, portable radiation monitoring equipment, cameras and communications equipment for personnel present in the assembly area.
10. Each organ ization shall make provisions to inspect, inventory and Sections 8.6 operationally check emergency equipment/instruments at least once Appendix B each calendar quarter and after each use. There shall be sufficient reserves of instruments/equipment to replace those which are removed from emergency kits for calibration or repair. Calibration of equipment shall be at intervals recommended by the supplier of the equipment.
11. Each plan shall, in an appendix, include identification of emergency kits Appendix B by general category (protective equipment, communications equipment, radiological G -11

GG Revision 80 FSAR 02 I 2020 monitoring equipment and emergency supplies).

12. Each organization shall establish a central point (preferably associated Sections 7.3.3 with the licensee's near-site Emergency Operations facility}, for the receipt and analysis of all field monitoring data and coordination of sample media.

I. Accident Assessment Planning Standard Adequate methods. systems and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency condition are in use.

Evaluation Criteria Cross Reference to Plan

1. Each licensee shall identify plant system and effluent parameter values Section 7.6.1 characteristic of a spectrum of off-normal conditions and accidents, Table 4-1 and shall identify the plant parameter values or other information which correspond to the example initiating conditions of Appendix I. Such parameter values and the corresponding emergency class shall be included in the appropriate facility emergency procedures. Facility emergency procedures shall specify the kinds of instruments being used and their capabilities.
2. Onsite capability and resources lo provide initial values and continuing Section 7.6.1, 7.6.4 assessment throughout the course of an accident shall include post-accident sampling capability, radiation and effluent monitors, in-plant iodine instrumentation, and containment radiation monitoring in accordance with NUREG-0578, as elaborated in the NRC letter to all power reactor licensees dated October 30, 1979.
3. Each licensee shall establish methods and techniques to be used for determining:
a. the source term of releases of radioactive material within plant Section 7.6.1 systems. An example is the relationship between the containment radiation monitor(s) reading(s) and radioactive material available for release from containment.
b. the magnitude of the release of radioactive materials based on plant Section 7.6.1 system parameters and effluent monitors Table 4-1
4. Each licensee shall establish the relationship between effluent monitor Section 7.6.1, 7.6.2 readings and onsite and offsite exposures and contamination for various meteorological conditions.
5. Each licensee shall have the capability of acquiring and evaluating Section 7.6.1 meteorological information sufficient to meet the criteria of Appendix
2. There shall be provisions for access to meteorological information by at least the nearsite Emergency Operations facility, the Technical Support Center, the Control Room and an offsite NRC G -12

GG Revision 80 FSAR 02 / 2020 Evaluation Criteria Cross Reference to Plan center. The licensee shall make available to the state suitable meteorological data processing interconnections which will permit independent analysis by the state, of facil ity generated data in those states with the resources to effectively use this information.

6. Each licensee shall establish t he methodology for determining the Section 7.6 .1 release rate/projected doses if the instrumentation used for assessment are off scale or inoperable.
7. Each organization shall describe the capability and resources for field Section 7.3 .3, 7.6.2, monitoring within the plume exposure Emergency Planning Zone which 7.6.4 are an intrinsic part of the concept of operations for the facility.
8. Each organization, where appropriate, shall provide methods, Section 7.5.3, 7.6 equipment and expertise to make rapid assessments of the actual or potential magnitude and locations of any rad iological hazards through liquid or gaseous release pathways. This shall include activation, notification means, field team composition, transportation, communication, mon itoring equipment and estimated deployment times.
9. Each organization shall have a capability to detect and measure Section 7.6 radioiodine concentrations in air in the plume exposure EPZ as low as 10-7 uCi/cc (microcuries per cubic centimeter) under field conditions.

Interference from the presence of noble gas and background radiation shall not decrease the stated minimum detectable activity.

10. Each organization shall establish means for relating the various Section 7.6 measured parameters (e.g., contamination levels, water and air activity levels) to dose rates for key isotopes (i.e ., those given in Table 3, page
18) and gross radioactivity measurements. Provisions sha ll be made for estimating integrated dose from the projected and actual dose rates and for comparing these estimates with the protective action guides.

The detailed provisions shall be described in separate procedures.

11. Arrangements to locate and track the airborne radioactive plume shall N/A be made, using either or both federal and state resources.

J. Protective Response Planning Standard A range of protective actions have been developed for the plume exposure pathway EPZ for emergency workers and the public. Guidelines for the choice of protective actions during an emergency, consistent with federal guidance are developed and in place, and protective actions for the ingestion exposure pathway EPZ appropriate to the locale have been developed.

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1. Each licensee shall establish the means and time required to warn or advise onsite individuals and individuals who may be in areas controlled by the operator, including:
a. Employees not having emergency assignments; Section 6.5.1
b. Visitors; Section 6.5.1
c. Contractor and construction personnel; and Section 6.5.1
d. Other persons who may be in the public access areas on or passing Section 6.5.1 through the site or within the EP owner controlled area.
2. Each licensee shall make provisions for evacuation routes and Section 6.5 transportation for onsite individuals to some suitable offsite location, including alternatives of inclement weather, high traffic density and specific radiological conditions.
3. Each licensee shall provide for radiological monitoring of people Section 6.5.1, 6.6 evacuated from the site.
4. Each licensee shall provide for the evacuation of onsite non-essential Section 6.5.1, 6.6, personnel in the event of a Site or General Emergency and shall provide 6.7.2 a decontamination capability at or near the monitoring point specified in J.3.
s. Each licensee shall provide for a capability to account for all individuals Section 6.5.1 onsite at the time of the emergency and ascertain the names of missing individuals within 30 minutes of the start of an emergency and account for all onsite individuals continuously thereafter.
6. Each licensee shall, for individuals remaining or arriving onsite during the emergency, make provisions for:
a. Individual respiratory protection; Section 7.10
b. Use of protective clothing; and Section 7.10
c. Use of radioprotective drugs, (e.g., individual Section 6.7.1 thyroid protection).
7. Each licensee shall establish a mechanism for recommending protective Sections 4.1, 6.5.1 actions to the appropriate state and local authorities. These shall Table 6*1 include Emergency Action Levels corresponding to projected dose to the population-at-risk, in accordance with Appendix I and with the recommendations set forth in Tables 2.1 and 2.2 of the Manual or Protective Action Guides and Protective Actions for Nuclear Incidents (EPA-52011-7 5-001). As specified in Appendix I, prompt notification shall be made directly to the offsite authorities responsible for implementing protective measures within the plume exposure pathway Emergency Planning Zone.

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8. Each licensee's plan shall contain time estimates for evacuation within Appendix E the plume exposure EPZ. These shall be in accordance with Appendix 4.
9. Each state and local organization shall establish a capability for N/A implementing protective measures based upon protective action guides and other criteria . Th is shall be consistent with the recommendations of EPA regarding exposure resulting from passage of radioactive airborne plumes, (EPA-520/1-75-001) and with those of DHEW (DHHS)

FDA regarding radioactive contamination of human food and animal feeds as published in the Federal Register of December 1, 1978 (43 FR 58790) .

10. The organization's plans to implement protective measures for the plume exposure pathway shall include:
a. Maps showing evacuation routes, evacuation areas, preselected Appendix E radiological sampl ing and monitoring points, relocation centers in host Figure 2-4, 2*5 areas, and shelter areas; (identification of radiological sampling and monitoring points shall include the designators in Table J-1 or an equivalent uniform system described in the plan);
b. Maps showing population distribution around the nuclear facility. This Figure 2*3, 2-4 shall be by evacuation areas (licensees shall also present the Appendix E information in a sector format);
c. Means for notifying all segments of the transient and resident Sections 6.5.1, 7.S.4 population;
d. Means for protecting those persons whose mobility may be impaired N/A due to such factors as institutional or other confinement;
e. Provisions for the use of radioprotective drugs, particularly for N/A emergency workers and institutionalized persons within the plume exposure EPZ whose immed iate evacuation may be infeasible or very difficu lt, including quantities, storage, and means of distribution.
f. Stale and local organizations' plans should include the method by which N/A decisions by the State Health Department for administering radioprotective drugs to the general population are made during an emergency and the predeterm ined conditions under which such drugs may be used by offsite emergency workers;
g. Means of relocation; N/A Evaluation Criteria Cross Reference to Plan
h. Relocation centers in host areas which are at least 5 miles, and N/A preferably 10 miles, beyond the boundaries of the plume exposure emergency planning zone; (see J.12).

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i. Projected traffic capacities of evacuation routes under emergency N/A conditions
j. Control of access to evacuated areas and organization responsibilities N/A for such control
k. Identification of and means for dealing with potential impediments N/A (e.g., seasonal impassability of roads) m use of evacuation routes, and contingency measures; I. Time estimates for evacuation of various sectors and distances based N/A on a dynamic analysis (time-motion study under various conditions) for the plume exposure pathway emergency planning zone (see Appendix 4); and
m. The bases for the choice or recommended protective actions from the Section 6.S.1 plume exposure pathway during emergency conditions. This shall Appendix E include expected local protection afforded in residential units or other shelter for direct and inhalation exposure, as well as evacuation time estimates.

2/ The following reports may be considered in determining protection afforded.

(1) "Public Protection Strategies for Potential Nuclear Reactor Accidents Sheltering Concepts with Existing Public and Private Structures" (SAND 77* 17255). Sandia Laboratory.

(2) "Examination of Offsite Radiological Emergency Measures for Nuclear Reactor Accidents Involving Core Melt" (SAND 78-0454), Sandia Laboratory.

(3) "Protective Action Evaluation Part II, Evacuation and Sheltering as Protective Actions Against Nuclear Accidents Involving Gaseous Releases" (EPA 520/1-78-001B), U.S. Environmental Protection Agency.

11. Each state shall specify the protective measures to be used for the N/A ingestion pathway, including the methods for protecting the public form consumption of contaminated food-stuffs. This shall include criteria for deciding whether dairy animals should be put on stored feed. The plan shall identify procedures for detecting contamination, for estimating the dose commitment consequences of uncontrolled ingestion, and for imposing protection procedures such as impoundment, decontamination, processing, decay, product diversion, and preservation. Maps for recording survey and monitoring data, key land use data (e.g., farming), dairies, food processing plants, water sheds, water supply intake and treatment plants and reservoirs shall be maintained. Provisions for maps showing detailed crop information may be by including reference to their availability and location and a plan for their use. The maps shall start at the facility and include all of the SO-mile ingestion pathway EPZ. Up-to-date G -16

GG Revision 80 FSAR 02 / 2020 Evaluation Criteria Cross Reference to Plan lists of the name and location of all facilities which regularly process milk products and other large amounts of food or agricultural products originating in the ingestion pathway Emergency Planning Zone, but located elsewhere, shall be maintained .

12. Each organization shall describe the means for registering and N/A monitoring of evacuees at relocation centers in host areas. The personnel and equipment available should be capable of monitoring within about a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> period all residents and transients in the plume exposure EPZ arriving at relocation centers.

K. Radiological Exposure Control Planning Standard Means for controlling radiological exposures, in an emergency, are established for emergency workers. The means for controlling radiological exposures shall include exposure guidelines consistent with EPA Emergency Worker and Lifesaving Activity Protective Action Guides.

Evaluation Criteria Cross Reference to Plan

1. Each licensee shall establish onsite exposure guidelines consistent with EPA Emergency Worker and Lifesaving Activity Protective Actions Guides (EPA S20/1-7S/OO1) for:
a. removal of injured persons; Section 6.7
b. undertaking corrective actions; Section 6.7 C. performing assessment actions; Section 6.7
d. providing first aid; Section 6.7
e. performing personnel decontamination; Section 6.7
f. providing ambulance service; and Section 6.7
g. providing medical treatment services. Section 6.7
2. Each licensee shall provide an onsite radiation protection program to Section 6.7.1 be implemented during emergencies, including methods to implement exposure guidelines. The plan shall identify individual(s), by position or title, who can authorize emergency workers to receive doses in excess of 10 CFR Part 20 limits. Procedures shall be worked out in advance for permitting onsite volunteers to receive radiation exposures in the course of carrying out lifesaving and other emergency activities . These procedures shall include expeditious decision making and a reasonable consideration of relative risks.
3. a. Each organization shall make provision for 24-hour-per-day capability Section 6. 7 .1 to determine the doses received by emergency personnel involved in any nuclear accident, including volunteers. Each organization shall make provisions for distribution of dosimeters, both self-reading and permanent record devices.

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b. Each organization shall ensure that dosimeters are read at appropriate Section 6.7.1 frequencies and provide for maintaining dose records for emergency workers involved in any nuclear accident.
4. Each state and local organization shall establish the decision chain for N/A authorizing emergency workers to incur exposures in excess of the EPA General Public Protective Action Guides (i.e., EPA PAGs for emergency workers and lifesaving activities).
5. a. Each organization as appropriate, shall specify action levels for Sections 6.6, 6.7 determining the need for decontamination.
b. Each organization, as appropriate, shall establish the means for Sections 6.7.2, 6.7.3, radiological decontamination of emergency personnel wounds, 6.7.4 supplies, instruments and equipment, and for waste disposal.
6. Each licensee shall provide onsite contamination control measures including:
a. area access control; Section 6.6
b. drinking water and food supplies; Appendix B
c. criteria for permitting return of areas and items to normal use, see Section 9.0 Draft ANSI 13.12.
7. Each licensee shall provide the capability for decontaminating relocated Section 6.7.2 onsite personnel, including provisions for extra clothing and decontaminants suitable for the type of contamination expected, with particular attention given to radioiodine contamination of the skin.

L. Medical and Public Health Support Planning Standard Arrangements are made for medical services for contaminated injured individuals.

Evaluation Criteria Cross Reference to Plan

1. Each organization shall arrange for local and backup hospital and Section 5.6.1, 6. 7.4 medical services having the capability for evaluation of radiation exposure and uptake, including assurance that persons providing these services are adequately prepared to handle contaminated individuals.

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GG Revision 80 FSAR 02 / 2020 1/ The availabil ity of an integrated emergency medical services system and a public health emergency plan serving the area in which the facil ity is located and, as a minimum, equivalent to the Public Health Service Guide for Developing Health Disaster Plans, 1974, and to the requirements of an emergency medical services system as outlined in the Emergency Medical Services System Act of 1974 (P.L.93-154 and amendments in 1979 P.L.96-142), should be a part of and consistent with overall state or local disaster control plans and should be compatible with the specific overall emergency response plan for the facility.

2. Each licensee shall provide for onsite first aid capability Section 6.7
3. Each state shall develop lists indicating the location of public, private N/A and military hospitals and other emergency medical services facilities within the state or contiguous states considered capable of providing medical support for any contaminated injured individual. The listing shall include the name, location, type of facility and capacity and any special radiological capabilities. These emergency medical services should be able to radiologica lly monitor contamination personnel and have faci lities and trained personnel able to care for contaminated injured persons.
4. Each organization shall arrange for transporting victims of rad iological Sections 5.6.1, 6.7.3 accidents to med ical support facil it ies.

M. Recovery and Reentry Planning and Post-accident Operations Planning Standard General plans for recovery and reentry are developed.

Evaluation Criteria Cross Reference to Plan

1. Each organization, as appropriate, shall develop general plans and Sections 5.5, 9.0 procedures for reentry and recovery and describe the means by which decisions to relax protective measures (e.g., all ow reentry into an evacuated area) are reached. This process should consider both existing and potential conditions.
2. Each licensee plan shall contain the position/title, authority and Sections 5.4.2, 5.5, responsibilities of individuals who will fi ll key positions in the facility 9.0 recovery organization . Th is organization shall include technical personnel with responsibilities to develop, evaluate and direct recovery and reentry operations. The recovery organization recommended by the Atomic Industrial Forum's "Nuclear Power Plant Emergency Response Plan" dated October 11, 1979, is an acceptable framework.
3. Each licensee and slate plan shall specify means for informing members Section 9.0 of the response organizations that a recovery operation is to be initiated, and of any changes in the organizational structure that may occur.
4. Each plan shall establish a method for periodically estimating total Section 9.0 population exposure.

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GG Revision 80 FSAR 02 / 2020 N. Exercised and Drills Planning Standard Periodic exercises are (will be) conducted to evaluate major portions of emergency response capabilities, periodic drills are {will be) conducted to develop and maintain key skills, and deficiencies identified as a result of exercises or drills are (will be) corrected.

Evaluation Criteria Cross Reference to Plan

1. a. An exercise is an event that tests the integrated capability and a major Section 8.3 portion of the basic elements existing within emergency preparedness plans and organizations. The emergency preparedness exercise shall simulate an emergency that results in offsite radiological releases which would require response by offsite authorities. Exercises shall be conducted as set forth in NRC and FEMA rules.
b. An exercise shall include mobilization of state and local personnel and Section 8.3 resources adequate to verify the capability to respond to an accident scenario requiring response. The organization shall provide for a critique of the annual exercise by federal and state observers/evaluators. The scenario should be varied from year to year such that all major elements of the plans and preparedness organizations are tested within a five-year period. Each organization should make provisions to start an exercise between 6:00 p.m. and midnight, and another between midnight and 6:00 a.m. once every six years. Exercises should be conducted under various weather conditions. Some exercises should be unannounced.
2. A drill is a supervised instruction period aimed at testing, developing and maintaining skills in a particular operation. A drill is often a component of an exercise. A drill shall be supervised and evaluated by a qualified drill instructor. Each organization shall conduct drills, in addition to the annual exercise at the frequencies indicated below:
a. Communication Drills Section 8.3.2 Communications with state and local governments within the plume exposure pathway Emergency Planning Zone shall be tested monthly.

Communications with federal emergency response organizations and states within the ingestion pathway shall be tested quarterly.

Communications between the nuclear facility, state and local emergency operations centers, and field assessment teams shall be tested annually; Communication drills shall also include the aspect of understanding the content of messages.

b. Fire Drills Section 8.3.2 Fire drills shall be conducted in accordance with the plant (nuclear facility) technical specifications.

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c. Medical Emergency Drills Section 8.3.2 A medical emergency drill involving a simulated contaminated individual which contains provisions for participation by the local support services agencies (i.e ., ambulance and offsite Evaluation Criteria Cross Reference to Plan medical treatment facility) shall be conducted annually. The offsite portions of the medical drill may be performed as part of the required annual exercise.
d. Radiological Monitoring Drills Section 8.3.2 Plant environs and radiological monitoring dril ls (onsite and offsite) shall be conducted annually. These drills shall include collection and analysis of all sample media (e.g., water, vegetation, soil and air), and provisions for communications and record keeping. The state drills need not be at each site. Where appropriate, local organizations sha ll participate.
e. Health Physics Dri ll s Section 8.3.2 (1) Health Physics drills shall be conducted semiannually which involve response to, and analysis of, simulated elevated airborne and liquid samples and direct radiation measurements in the environment. The slate drills need not be at each site.

(2) Analysis of inptant liquid samples with actual elevated radiation levels including use of the post-accident sampling system shall be included in Health Physics drills by licensees annually.

3. Each organization shall describe how exercises and drills are to be carried om to allow free play for decision making and to meet the following objectives. Pending the development of exercise scenarios and exercise evaluation guidance by NRC and FEMA the scenarios for use in exercises and drills shall include but not be limited to, the following:
a. The basic objective(s) of each drill and exercise and appropriate Section 8.3 .1 evaluation criteria;
b. The date(s), time period, place(s) and participating organizations; Section 8.3.1
c. The simulated events; Section 8.3.1
d. A time schedule of real and simulated initiating events; Section 8.3.1
e. A narrative summary describing the conduct of the exercises or drills to Section 8.3.1 include such things as simulated casualties, offsite fire department assistance, rescue of personnel, use of protective clothing, deployment of radiological monitoring teams, and public information activities; and
f. A description of the arrangements for and advance materials to be Section 8.3.1 provided to official observers.
4. Official observers from federal, state or local governments will observe, Section 8.3.1 evaluate, and critique the required exercises. A critique shall be scheduled at the conclusion of the exercise to evaluate the ability of organizations to respond as called for in the plan. The critique shall be conducted as soon as practicable after the exercise, and a formal evaluation should result from the critique.

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5. Each organization shall establish means for evaluating observer and Sections 8.3, 8.4, 8.5 participant comments on areas needing improvement, including emergency plan procedural changes, and for assigning responsibility for implementing corrective actions. Each organization shall establish management control used to ensure that corrective actions are implemented.
0. Radiological Emergency Response Training Planning Standard Radiological emergency response training is provided to those who may be called on to assist in an emergency.

Evaluation Criteria Cross Reference to Plan

1. Each organization shall assure the training of appropriate individuals. Sections 8.1, 8.2, 8.4
a. Each facility to which the plant applies shall provide site specific Sections 8.2, 8.4 emergency response training for those offsite emergency organizations who may be called upon to provide assistance in the event of an emergency. 1
b. Each offsite response organization shall participate in and receive N/A training. Where mutual aid agreements exist between local agencies such as fire, police and ambulance/rescue, the training shall also be offered to the other departments who are members of the mutual aid district 1/ Training for hospital personnel, ambulance/rescue, police and fire departments shall include the procedures for notification, basic radiation protection, and their expected roles. For those local services support organizations who will enter the site, training shall also include site access procedures and the identity (by position and title) of the individual in the onsite emergency organization who will control the organizations' support activities. Offsite emergency response support personnel should be provided with appropriate identification cards where required.
2. The training program for members of the onsite emergency Section 8.3 organization shall, besides classroom training, include practical drills in which each individual demonstrates ability to perform his assigned emergency function. During the practical drills, on-the-spot correction of erroneous performance shall be made, and a demonstration of the proper performance offered by the instructor.
3. Training for individuals assigned to licensee first aid teams shall include Section 6.7.2 courses equivalent to Red Cross Multi-Media.
4. Each organization shall establish a training program for instructing and Section 8.2 qualifying personnel who will implement radiological emergency response plans. The specialized initial training and periodic retraining programs (including the scope, nature and frequency) shall be provided in the following categories:

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a. Directors or coordinators of the response organizations;
b. Personnel responsible for accident assessment;
c. Radiological monitoring teams and rad iological analysis personnel:
d. Police, security and firefighting personnel;
e. Repair and damage control/correctional action' teams (onsite);
f. first aid and rescue personnel;
g. Local support services personnel including Civil Defense/Emergency Service personnel;
h. Medical support personnel;
i. Licensee's headquarters support personnel; 2/ If state and local governments lack the capability and resources to accomplish this training, they may look to the licensee and the Federal government (FEMA) for assistance in this training.
  • NRC and FEMA encourage state and local governments which have these capabilities to continue to include them in their training programs.
j. Personnel responsible for transmission of emergency information and instructions.
5. Each organization shall provide for the initial and annual retraining of Section 8.2 personnel personnel with emergency response responsibilities.

P. Responsibility for the Planning Effort: Development. Periodic Review and Distribution of Emergency Plans Planning Standard Responsibilities for plan development and review and for distribution of emergency plans are established, and planners are properly trained.

Evaluation Criteria Cross Reference to Plan

1. Each organ ization shall provide for the training of individuals Section 8.4 responsible for the planning effort.
2. Each organization shall identify by title the individual with the overa ll Section 8.1, 8.4 authority and responsibility for radiological emergency response planning.
3. Each organization shall designate an Emergency Planning Coordinator Sections 8.1, 8.4 with responsibility for the development and updating of emergency plans and coordination of these plans with other response organizations.
4. Each organization shall update its plan and agreements as needed, Section 8.4, 8.5 review and certify it to be current on an annual basis. The update shall take into account changes identified by drills and exercises.
5. The emergency response plans and approved changes to the plans sha ll Section 8.5 be forwarded to all organizations and G - 23

GG Revision 80 FSAR 02 / 2020 Evaluation Criteria Cross Reference to Plan appropriate individuals with responsibility for implementation of tile plans. Revised pages shall be dated and marked to show where changes have been made.

6. Each plan shall contain a detailed listing of supporting plans and their A1;rnendix F source .
7. Each plan shall contain as an appendix listing, by title, procedures A1;rnendix A required to implement the plan. The listing shall include the section{s) of the plan to be implemented by each procedure.
8. Each plan shall contain a specific table of contents. Plans submitted for AQQendix G review should be cross-referenced to these criteria.
9. Each licensee shall arrange for and conduct independent reviews of the Section 8.5 emergency preparedness program at least every 12 months. (An independent review is one conducted by any competent organization either internal or external to the licensee's organization, but who are not immediately responsible for the emergency preparedness program.) The review shall include the emergency plan, its implementing procedures and practices, training, readiness testing, equipment, and interfaces with state and local governments.

Management controls shall be implemented for evaluation and correction of review findings. The result of the review, along with recommendations for improvements, shall be documented, reported to appropriate licensee corporate and plant management, and involved federal, state and local organizations, and retained for a period of five years.

10. Each organization shall provide for updating telephone numbers in Section 8.6 emergency procedures at least quarterly.

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GG Revision 80 FSAR 02 / 2020 APPENDIX H I. News Media Emergency Information Program for GGNS II. Public Education and Information Program for GGNS H-1

GG Revision 80 FSAR 02 I 2020 INTRODUCTION This section of the Emergency Plan deals with responses to an emergency in relation to news media activities, employee information, inquiry response, and coordination of public information activities with local, state, and federal agencies. It also describes the training to be conducted to ensure effective dissemination of information during an emergency.

The first part of this section is a brief synopsis of the overall news media emergency information program organized according to emergency classifications. This is implemented by 01-S-10-6, 10-S 6. 10-S-01-34.

The final part of this document is a description of public information-education activities underway for residents in the Grand Gulf area and the general public.

1.0 PURPOSE The News Media Emergency Information Program establishes the means of keeping media personnel informed of an emergency situation at Grand Gulf Nuclear Station (GGNS).

2.0 RESPONSIBILITIES FOR ACTIVATING THE PROGRAM Activation of the news media program begins with a call from the GGNS Computer Notification System or Emergency Director to the Company Spokesperson.

The Company Spokesperson determines, following consultation with the Emergency Director, whether the situation warrants media notification. Initial decisions are determined to a great extent by the classification given to the incident, of which there are four.

3.0 Deleted 4.0 OVERALL INFORMATION FLOW 4.1 Company Spokesperson GGNS management or designee fills the Company Spokesperson position throughout an emergency.

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GG Revision 80 FSAR 02 / 2020 4.2 Unusual Event Normally only the Company Spokesperson is called. He/ she may:

a. Stand by and follow developments
b. Consider additional notifications
c. Consider drafting news bulletin 4.3 Alert/ Site Area Emergency/ General Emergency Actions initiated at the Alert level continue through a Site Area Emergency and General Emergency. At these levels of an emergency the EOF sends information to the Company Spokesperson, or designee.

4.3 .1 Company Spokesperson :

a. Reports to the Joint Information Center
b. Establishes contact with the EOF
c. Coordinates directly with State representatives at the JIC
d. Ensures that the Inquiry Response is activated and provided with news bulletins to use in response to inquiries from the media and public.
e. Issues news bulletins and conducts news briefings once the JIC is operational 4.3.2 Inquiry Response Coordinator:
a. Reports to the JIC
b. Ensures that the Inquiry Response is operational and establishes contact with the JIC
c. Ensures that current news bulletins are provided to the Inquiry Response Staff 4.3.3 News Briefings - News briefings are conducted at the JIC as needed and news media inquiries are referred to the JJC. Copies of news bulletins are also available to the Inquiry Response and the Entergy Operations CEC.

4.3.4 Coordinating News Releases from the JIC - GGNS Personnel issue bulletins concerning conditions at the plant. Statements relative to offsite conditions and operations are done by the Governor's Press Secretary and/or the Director of the Mississippi Emergency Management Agency or their designee.

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GG Revision 80 FSAR 02 I 2020 Statements relative to Louisiana conditions and operations are done by a representative for the State of Louisiana.

4.3.5 Contacts with other agencies - The JIC assumes responsibility when it is activated for sharing bulletin messages with CCCD, TPHS/EP, MEMA, LDEQ, NRC Regional Office, and other government agencies with representatives at the JIC. The JIC is responsible for sending bulletin messages to the Entergy Operations CEC, Inquiry Response. and SMEPA.

5.0 EXCEPTIONS Exceptions to this information flow plan are made in case of either a rapidly developing

- or rapidly terminating - emergency at Grand Gulf.

5.1 Rapidly Developing Emergency - In this circumstance the Company Spokesperson, in consultation with the ED, is authorized to issue news bulletins.

5.2 Rapidly Terminating Emergency - In this case a public statement is developed by the Company Spokesperson detailing the nature of the incident and telling how it was resolved. This statement is given to the news media as rapidly as possible.

6.0 TRAINING Individuals involved in the GGNS News Media Emergency Information Program complete training activities and participate in drills! exercises in order to be thoroughly familiar with their duties. Training is documented by the Manager. Emergency Preparedness.

6.1 News Media Training - An annual program is provided to acquaint the news media with the methodology for obtaining information during an emergency as well as information about overall emergency preparedness for GGNS. The training includes information about the plant, radiation, and the roles of emergency news centers.

6.2 Overall Training - Appropriate training activities are conducted annually for those involved in the News Media Emergency Information Program.

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GG Revision 80 FSAR 02 / 2020 II. PUBLIC EDUCATION AND INFORMATION PROGRAMS FOR GGNS 1.0 Purpose and Objectives This program acquaints the general public with the emergency preparedness plans made in connection with the operation of Grand Gulf Nuclear Station {GGNS) located in Claiborne County in Southwest Mississippi.

Entergy Operations, Inc., operator of the facility has established a policy of full disclosure of any incident relating to the safety of operation of the plant. Entergy Operations therefore.

maintains a free and open relationship with the public and others concerned with the safety of operations in the vicinity of GGNS.

2.0 Methods To Reach The Public Prior To Emergency Situations Several communication methods are used to acquaint the public with plans made for their protection during any emergency at GGNS. These methods are described below:

2.1 Material Placed in Schools: Literature is offered to schools in the area, both in Claiborne County and Tensas Parish. The information tells locations of shelters and reception centers for students in Claiborne County, Mississippi. and Tensas Parish Louisiana.

2.2 Grand Gulf Emergency Preparedness Public Information website and mobile application:

The Public Information Website and smartphone application contain basic information on nuclear power and emergency planning to aid the public during any emergency. The mobile application is free to download. Information about this website and mobile application is mailed annually via postcard to the residents in Claiborne County and Tensas Parish areas.

2.2.1 The annual postcard will also contain information on how to obtain a hardcopy of the material contained on the website and mobile application for individuals who do not have access to the website or mobile devices. Hardcopies of the information may be printed from the Public Information Website.

2.2.2 Hard copies of the information will be provided, upon request, to individuals who are unable to access the website or mobile application.

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GG Revision 80 FSAR 02 I 2020 2.3 Display of Posters: One of the ways to acquaint the overall population, especially Transients, with the emergency plans is the placing in public places of posters with a map of the evacuation routes and other pertinent information.

H-6

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