Text

Changes to Emergency Plan Implementing Procedures, Rev. 109 10-S-01-1
	ML022330636
Person / Time
Site:	Grand Gulf
Issue date:	08/12/2002
From:	Bottemiller C; Entergy Operations
To:	; Document Control Desk, Office of Nuclear Security and Incident Response
References
	GNRO-2002/00068
	Download: ML022330636 (47)
	v • d • e

ter Waterloo Road P.O. Box 756 Port Gibson, MS 391 50 Tel 601 437 6299 Manager Plant Licensing August 12,2002 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

Subject:

Changes to Emergency Plan Implementing Procedures - August 12,2002 Grand Gulf Nuclear Station Docket No. 50-416 License No. NPF-29 GNRO-2002/00068 Ladies & Gentlemen:

Entergy Operations, Inc. submits in accordance with 10CFR50 Appendix E, Section V changes to the following Emergency Plan Implementing Procedure:

10-S-01-1 Rev. 109 This letter does not contain any commitments.

Yours truly, Charles A. Bottemiller, Licensing Manager MJL attachment:

1. Procedure 10-S-01-1 cc:

(See Next Page)

August 12,2002 GNRO-2002/00068 Page 2 of 2 cc:

Hoeg T. L.

(GGNS Senior Resident)

Levanway D. E.

(Wise Carter)

Reynolds N. S.

Smith L. J.

(Wise Carter)

Thomas H. L.

(w/a)

(w/o)

U.S. Nuclear Regulatory Commission ATTN: Mr. E. W. Merschoff (~12) 611 Ryan Plaza Drive, Suite 400 Arlington, TX 7601 1-4005 U.S. Nuclear Regulatory Commission ATTN: Mr. David H. Jaffe NRR/DLPM (~12)

ATTN: FOR ADDRESSEE ONLY ATTN: U.S. Postal Delivery Address Only Mail Stop OWFN17D-I Washington, D.C. 20555-0001 ALL LETTERS SERVICE MAIL DELIVERY ADDRESS ONLY

PLANT OPERATIONS MANU AL Volume 10 Section 01 10-s-01-1 Revision: 109 Date : 7 /3 1 /O 2 EMZRGENCY PLAN PROCEDrn SAFEm RELATED Prepared :

Reviewed :

Concurred:

OSRC :

Approved :

2x3 None List of Effective Pages:

Pages 1-11 Attachments I, I1 EPP 01-02 (Flowchart) Dated 7/29/02 List of TCNs Incorporated:

Revision TCN Revi s ion, 1-4 None 109 5

1,2 6

3 7

4 8

5, 6 9

None 10 7,8 11 None 12 9

13 1 0 14,15 None 16 11 17 None 18 12 19 None 20 None 21 None 22 13,14 23 None 100 15 101 None 102 16 103 None 104 None 105 None 106 None 107 None 108 None J:ADM~SRVS/TECH~PUB/REVISION/1OSOll.DOC

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE Emergency Plan Evaluation c]

c]

I.

OVERVIEW / SIGNATURES Facility: b6 N5 Document Reviewed:

/ ~ O ( - /

Change/Rev.

9 System Designator(s)/Description:

If the proposed activity, in its entirety, involves any one of the criteria below, check the appropriate box, provide a justification/basis in the Description above, and forward to a Reviewer. No further 50.59 Review is required. If none of the criteria is applicable, continue with the 50.59 Review.

c]

I2 The proposed activity is editorial/typographicai as defined in Section 5.2.2.1.

The proposed activity represents an FSAR-only change as allowed in Section 5.2.2.2

. (Insert item # from Section 5.2.2.2).

,,b(

The proposed activity is controlled by another regulation per Section 5.2.2.3.

If further 50.59 Review is required, check the applicable review(s):

(only the sections indicated must be included in the Review.)

SCREENING 50.59 EVALUATION -TION Sections I, 11, 111, and Sections I, LI, and I11 required Tv required 1 I2 1 50.59 EVALUATION (8:

)

1 Sections I, 11, 111, and V required 1

n Reviewer:

OSRC :

A/&

Chaikmans Name (print) / Signature / Date

[Required only for Programmatic Exclusion Screenings (see Section 5.8) and 50.59 Evaluations.]

List of Assisting/Contributing Personnel :

Name :

Scope of Assistance:

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE

Title:

Activation of the Emergency Plan No.: 10-S-01-1 Revision: 109 Page: i WTS FORM 10CFR50.59 R e v i e w R e q u i r e d ? 1 (M Yes I If Yes, attach 50.59 Review Form I ( 1 No I Not required per LI-101 J

Requirement Implemented by Directive Name Paragraph Number Directive Paragraph Number That Implenents Requirement ANSI N18.7 GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Fmer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Fmer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GNRI-93/00171 5.3.9.2.Sl 2.4.53 3.3.Sl 6.2.2.S3 & S4 5.4.5.a,b,c 5.4.4 3.1.S2 6.2.2.Sl & S2 4.l. 4. S3 4.1.S3 4.1. S13 3.3.S6.b 6.2.4.513 6.2.4.S14 4.1.4. S2 6.3.2 6.3.3, 6.3.4 9.3.s7 Table 4-1 7.5.3.a.2.e 93-13-01, Item 6 6.5.l.b.S5, S6 7.5.3.a.3.c 6.2.4.S2 6.2.4.S7 & S8 5.4.S6 3.3.s3 & s4 6.5.1.b 6.5.1.A.1 3.3.s5 6.2.4.sl1 & s12 6.3.1.sl & 52 1.1.1 2.1.2 2.1.1, 6.1.2 S2 2.2 2.3 6.1.2 6.1.2 (Note)

Attachment I 6.1.4, 6.3 6.1.3 (Note) 6.1.3 6.1.4.i(1) 6.1.4.i(2) 6.1.4.i(3) 6.1.4. j (1) 6.2.1 6.2.la 6.2.lb Attachment I1 (Note)

Attachment I 5.30 Attachment I, 17.1.1 6.1.4. j (1) 6.1.4.d 2.1.2 2.4 6.1.4.i(l),i(2),i(3) 2.4 6.1.4 6.1.4.g 2.1.2

Covered by directive as a whole or by various paragraphs of the directive.

Title:

Activation of the Emergency Plan The Component Database Change Request statement is applicable only to Volume 06 and 07 maintenance directives.

No.: 10-S-51-1 Revision: 109 Page: ii Component Database Change Request generated and entation available for setpoint and/or calibration data only 0 Yes Current Revision Statement Revision 109:

Implements NRC requested site specific credible threat EAL.

Makes other administrative changes.

Title:

Activation of the Emergency Plan

$OCFR50,54(a) S creening No.: 10-S-01-1 Rev. 109 Emergency Plan Evaluation Procedure/Document Number:lO-S-Ol-l

/ Proc./Doc. Revision:109 Document Tit1e:Activation of the Eherqency Plan Brief Description of Proposed Revision: Adds site specific credible threat EAL to procedure as requested by the NRC. Other administrative changes. This procedure revision implements Revision 48 of the Emeraencv Plan.

2.

SCREEN1 A.)Does the proposed revision require a change to the Emergency Plan?

Yes __ x-No B.)Does the proposed revision change the site Emergency Action Levels (EALS)

?

Yes X No IE the answer to either question is S, then a 50.54(q) evaluation must be performed.

3.

APPROVAL Screening Completed By:

7 lzs loz Screening Reviewed By:

fi 7/a*&r Date Signature Date

G W

i GULF NUCLEPA STATION EMEXGENCY PLAN PROCEDLTE TiCle: Activation of the NO.: 1o-s-01-i Revision: 109 Emergencv Plan Page: 1 1.0 PURPOSE AND DISCUSSION 2.0 RESPONSIBILITIES 3.0 REFEXNCES 4.0 ATTACHMENTS 5.0 DEFINITIONS 6.0 DETAILS 6.1 Activation of Emergency Plan 6.2 Supplemental Actions 6.3 UpgradiRg Emergency Classifications 6.4 Terninating Emergency 6.5 Records and Reports 6.6 EP form EPP 01-02 (Flow Chart) Revision Process l?&r.!2 2

2 3

3 3

6 6

9 10 10 11

Title:

Activation of the Emergency Plan 2.0 No.: 10-S-01-1 Revision: 109 Page: 2 1.1 PurDose 1.1.1 This procedure provides guidance to:

a.

Classify an emergency according to severity.

b.

Assign responsibilities for emergency actions.

c.

Establish lines of authority and communication.

d.

Initiate emergency actions to safeguard the public and plant personnel.

e.

Upgrade or te,minate emergency classification when severity of event changes.

1.2 Discussion 1.2.1 Whenever plant conditions are identified that meet the Emergency Action Level Criteria in Attachment I or EPP 01-02 (Flowchart),

this emergency plan procedure shall be implemented.

1.3 Changes required for implementation of 1994 TSIP were incorporated in Revision 100. For historical reference this statement should not be deleted.

RESPONSIBILITIES 2.1 shift Manaqer - Is responsible for determining if emergency declaration is required.

2.1.1 If an Emergency Action Level (EAL) is reached or exceeded, the Shift Manager shall:

a.

Classify the emergency and make the appropriate declaration if required.

b.

Take action to ensure safe operation of plant and protection of plant personnel, the general public, and plant equipment.

c.

Perform assessment actions.

d.

Perform any other emergency actions as appropriate.

initial classification of an emergency, and becomes the Operations Coordinator, when relieved by the On-Call Manager (as Emergency Director), until relieved by the On-Call Operations Coordinator.

When relieved by the On-Call Operations Coordinator, the Shift Manager resumes normal Control Room duties.

2.1.2 The Shift Manager assumes the role of Emergency Director upon 2.2 OD erations Coordinator - Reports directly to the Emergency Director and is responsible for:

2.2.1 Coordinating all activities in the Control Room.

Title:

Activation of the Emergencv Plan 2.2.2 Coordinating Operations activities outside of the Control Room with the TSC Coordinator.

No.: 10-S-01-1 Revision: 109 Page: 3 2.2.3 Providing technical assistance to the Shift Manager.

2.3 Security Coo reinator - Reports directly to the Emergency Director and is responsible for managing the Security Force during an emergency.

2.4 Qn-Call Manauek

? - _ Is responsible for:

2.4.1 Reporting to the site to ass'me the duties of Emergency Director upon notification of an Alert or higher classification.

2.4.2 Assuming the duties of Emergency Director after the TSC is declared operational.

2.4.3 Reporting to the site to assume duties of Emergency Director upon notification of an Unusual Event if he deems it necessary.

2.4.4 Evaluating the accident conditions and verifying that the correct emergency classification has been made.

3.0 REFERENCES

3.1 &iC Memorandum dated July 11, 1994 concerning "Branch Position on 3.2 GGNS Emergency Plan Acceptable Deviations to Appendix 1 to NUREG-0654/FEMA-REP-ln.

4.0 ATTAC"TS 4.1 Attachment I - Emergency Classifications 4.2 Attachment I1 - Guidelines to Terminate Emergency 5.0 DEFINITIONS 5.1 Alert - An emergency classification in which events are in progress or have occurred that involve an actual or potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small fractions of the Environmental Protection Agency (EPA) Protective Action Guideline exposure levels.

5.2 Assessment Act ion - Actions taken during or after an accident to obtain and process information necessary to make decisions to implement specific emergency measures.

5.3

- Central Alarm Station 5.4 CDE (Thyroid) (Committed Dose Equivalent) - The radiation dose to the adult thyroid gland due to radioiodines over a fifty year period following inhalation or ingestion.

Title:

Activation of the No.: 10-S-01-1 Revision: 109 Emergency Plan 5.5 5.6 5. 7 5.8 5.9 Page: 4 Downwind - An area located beyond a fixed point in the same direction the wind is blowing. The area covers three sectors, the sector containing the plume centerline, and the two adjacent sectors. If the plume is on a sector line, four sectors are used until the three sector criteria can be identified.

Erneraencv - 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.

Emeraencv Action Levels (E-XLs) - Radiological dose rates, specific contamination levels of airborne, waterborne, or surface-deposited concentrations of radioactive materials; or specific instrument indications (including their rates of change) that are used as thresholds for initiating such specific emergency measures as designated for a particular class of emergency, initiating a notification procedure, or initiating a particular protective action.

Emeraencv Classification - Emergency conditions (four classes) covering the entire spectrum of possible situations from minor, local incidents to hypothetical, major radiological emergencies. The four classes are listed in iccreasing order of severity: Unusual Event, Alert, S ite Area Emeroe ncv and General Emeraencv.

Emeraencv Director - An individual designated onsite having the authority and responsibility to initiate the Emergency Plan and coordinate efforts to reduce the consequences of the event and bring it under control 5.10 Emeraencv ODerations Facilitv (EOF) - A near-site emergency center from which the offsite emergency support activities are controlled 5.11 Ehersencv Plannino Zone (EPZ) - Areas designated for which planning is provided to assure that prompt and effective action is initiated to protect the public in the ever,c of an emergency 5.12 EPE - Emergency Plan Procedure 5.13

- Emergency Response Data System. A near real-time data link from the GGNS Balance of Plant computer to the NRC Operations Center. This system monitors specific data and is activated by the Shift Manager no later than one hour after an ALERT (or higher) declaration.

5.14 ES.C - Energy Services Center 5.15 Exclusion Area - Area surrounding the plant, owned by the licensee, in which the licensee has the authority to determine all activities including exclusion or removal of personnel and/or property progress or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity.

Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area.

5.16 Genera 1 Emeraencv - An emergency classification in which events are in 5.17 LQC.23 - Loss of Coolant Accident 5.18

- Offsite Emergency Coordinator 5.19 Offsite - For accountability purposes, any area outside the GGNS protected area 5.20 OMT - Offsite Monitoring Team J:ADM~SRVS/TECH~PUB/REVISION/~OSO~~.DOC

Title:

Activation of the Emergency Plan 5.21 Qnsite - For accountability purposes, the area within the GGNS protected area No.: i0-S-01-1 Revision: 109 Page: 5 5.22 QDerations SuDDort Center (OSC) - Location from which onsite non-Control Room activities are staged and implemented 5.23

- Public Address System 5.24 PAG - Protective Action Guide 5.25 PAR - Protective Action Recommendation 5.26 SAS - Secondary Alam Station 5.27 Site Area Emeraency - An emergency classification in which events are in progress or have occurred which involve major failures of plant functions needed for protection of the public. Any releases are not expected to exceed EPA Protective Action Guideline exposure levels except near the site boundary.

5.28 =Standby Service Water 5.29 TEDE (Total Effective Dose Equivalent) - Sum of the EDE and CEDE to 5.30

- Thermo Luminescent Dosimeter 5. 3 1 m - Technical Support Center 5.32 Unusual Event - An emergency classification in which events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant. No releases of radioactive material reqdiring offsite response or monitoring are expected unless further degradation of safety systems occurs. (This is the same as the Notification of Unusual Event defined in "REG-0654; the two expressions are used interchangeably in the E-Plan and related procedures as appropriate.)

nonpregnant adults from exposure and intake during an emergency situation.

5.33 Vital Areas-Areas within the Protected Area that house safety-related equipment. The failure or destruction of this equipment could directly or indirectly endanger the public health and safety by exposure to radiation.

The following areas are considered Vital Areas: Auxiliary Building (including Containment), Control Building (including Control Room Complex),

Diesel Generator Building, Inverter Room (166' elevation Turbine Building),

SSW Pump and Valve rooms.

Title:

Activation of the Emergency Plan 6.0 DETAIT8S 6.1 Activation of Emersencv Flan 6.1.1 Any person having knowledge of abnomal plant conditions should notify the Shift Supervisor/Manager.

6.1.2 The Shift Supervisor/Manager, when notified of abnormal plant conditions, should refer to Attacbment I or EFP 01-02 (Flowchart) to determine if an emergency action level has been reached. If an emergency action level has been reached, the emergency plan shall be implemented.

I No.: 10-S-01-1 Revision: 109 Page: 6 The Shift Supervisor/Manager is responsible for determining if the declaration of an emergency is required.

If a declaration is required, he is responsible for activating the emergency plan.

6.1.3 Whenever there is doubt as to the classification of the emergency condition or if more than one Gn_L is reached, the more conservative classification should be used.

NOTE 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.

6.1.4 Once an emergency classification is declared, the following actions are taken by the Shift Manager/Emergency Director:

After becoming aware that an emergency condition exists, the Shift Manager/Emergency Director's first priorities are :

- Take actions to ensure safety of plant personnel and general public.

- Take actions to ensure safe operation of plant.

- Other duties and responsibilities of the Emergency Director are contained in 10-S-01-30, Technical Support Center (TSC)

Operations.

a.

Initiate Emergency Director's Checklist (EPP Form 01-1).

GFJLPTD GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE

Title:

Activation of the Emergency Plan No.: 10-5-01-1 Revision: 109 Page: 7 6.1.4 (Cont.

1

b.

Announce to Control Room personnel that you ar'? the Emergency Director.

The NRC shall be notified of the declaration of the emergency IMMEDIATELY AFTER THE NOTIFICATION OF THE STATE AND LOCAL AGENCIES and not later than one hour after the emergency declaration.

c.

Designate an indivi6ual as communicator to perform the initial notification in accordance with 10-S-01-6. The Shift Manager shall ensure that the primary or secondary state and local agencies are notified within 15 minutes of an emergency declaration or reclassification.

NOTE In the event of Security emergencies, each Security related incident should be evaluated. Only those support groups axxd facilities which are needed should be activated, regardless of the emergency classification, so as to minimize the risk to personnel. Utilization of the ERO call tree rather than VIP 2000 may be required to inform responders of emergency situation and prevent manning of unneeded facilities.

d.

Activate and verify activation of the VIP 2000 per 10-5-01-6.

e.

Activate ERDS within one hour of an Alert or higher declaration Per 10-S-01-6.

f.

Announce nature and classification of event:

For security emergencies, inform all personnel to take shelter, to NOT move around in the plant, and to man only those emergency facilities which are necessary and that don't pose a risk to personnel.

(1) Over Plant PA System or phone #6426.

(2) Over Site Paging ( # 7 9 2 9 ).

g.

If an evacuation of affected areas of the plant is required, perform in accordance with 10-5-01-11.

Title:

Activation of the No.: 10-S-01-1 Emergency Plan 6.1.4 (Cont.

)

Revision: 109 Page: 8

h.

Implement plant operating procedures and emergency plan procedures as required to perform emergency corrective and assessment actions.

i Activate emergency facilities as follows:

(1) If Unusual Event has been declared, no activation of facilities is required unless the Emergency Director feels there is a reasonable possibility of escalation of emergency to a higher classification.

(2) If an Alert has been declared, all emergency facilities must be activated.

(3) If a Site Area Emergency or General Emergency has been declared, a Site Evacuation should be seriously considered.

j.

If an Alert, Site Area Emergency, or General Emergency has been declared, determine offsite doses in accordance with 10-s-01-12.

(1) Protective actions shall be recormended to State and Local Agencies upon declaration of a General Emergency as follows:

Condition General Emergency Declared General Emergency Declared And Dose Projection or Field Measurement at 2 5 miles corresponds to 1 RernTEDE Or 5 Rern ThyroidCDE Protective Action Recommendation EVACUATE: 2 Miles All Sectors and EVACUATE: 5 Miles in Downwind Sectors and SHELTER:

Remainder of 10 Mile Emergency Planning Zone (EPZ)

EVACUATE: 2 Miles All Sectors and EVACUATE: 10 Miles in Downwind Sectors and SHELTER:

Remainder of 10 Mile Emergency Planning Zone (EPZ)

Title:

Activation of the No.: 10-S-01-1 Revision: 109 6.1.4 (Cont.

)

Page: 9

k.

Designate shift personnel to perform emergency corrective and assessment actions.

6.2 Sumleme ntal 3,ctions 6.2.1 Continuous assessment is necessary to effectively coordinate and direct emergency response. In any emergency situation, attention must be paid to parameters that may indicate a possible worsening of conditions (i-e.,

radioactive releases).

a.

If an Alert condition is declared, the following assessment actions are required:

(1) Increased surveillance of applicable in-plant instrumentation.

(2) Visual observation of affected plant area.

(3) Onsite and offsite radiological monitoring if a release has taken place or is suspected.

(4) Determination of offsite doses if applicable.

b.

In addition to the above, a Site Area Emergency or General Emergency would require these additional assessment actions.

(1) Monitor meteorological data.

( 2 ) Dispatch offsite radiological monitoring teams down wind of the release in conjunction with state radiological monitoring efforts.

(3) Assess onsite and offsite radiation doses. (TEDE and Thyroid CDE).

6.2.2 Emergency Director should ensure that periodic announcements are made over the plant PA and site PA (#7929) concerning:

a.

Nature and location of event.

b.

Required personnel actions.

c.

Any other information necessary.

6.2.3 The Emergency Director (while in the Control Room) logs all information in the Shift Manager/Control Room Operator Log as necessary for event reconstruction.

Coordinator and/or Radiation Protection Manager the responsibility for logging all information relative to the emergency (for event reconstruction).

6.2.4 The Emergency Director (while in the TSC) may delegate to the TSC 6.2.5 The Offsite Emergency Coordinator may delegate to the Offsite Emergency Coordinator Technical Assistant the responsibility for logging all information relative to the emergency (for event reconstruction).

Title:

Activation of the Emergency Plan 6.2.6 Upon declaring the EOF operational, the following activities should be transferred to the OEC as soon as possible:

a.

Notifications to offsite agencies

b.

Offsite radiological and environrnental surveys

c.

Protective action recormendations to offsite agencies

d.

Classification of the elnergency 6.2.7 If extended emergency operations are necessary, the Emergency Director/Offsite Energency Coordinator should authorize preparation of an emergency organization shift schedule to support 24-hour emergency operation.

6.3 URCT radina Eneraencv Classifications 6.3.1 If conditions worsen, refer to Attachment I or EPP 01-02 (Flowchart) to determine if the emergency classification requires upgrading. If the classification is upgraded, ensure the following steps are taken:

a.

Declare appropriate emergency classification in accordance with Step 6.1.2.

b.

Announce nature and classification of event in accordance with Step 6.1.4.f.

evacuate affected areas in accordance with Step 6.1.4g.

c.

If an evacuation is required, notify Security if possible and

d.

Initiate plant operating procedures and emergency plan procedures as required.

e.

Activate additional emergency facilities as necessary in accordance with Step 6.1.4i.

f.

Determine offsite doses in accordance with Step 6.1.4-j.

g.

Conduct additional assessment actions as necessary in accordance with Step 6.2.

6.4 Terminating Emeraencv 6.4.1 Terminatinq If EALs are no longer met or exceeded, the Emergency Director/Offsite Emergency Coordinator refers to Attachment 11 to determine whether or not to terminate emergency.

6.4.2 ReentrJ and Recovery Once the corrective and protective actions taken have established effective control over the situation, the Emergency Director may refer to 10-5-01-23 and 10-S-01-22 to determine if reentry and recovery actions may be initiated. If the reentry/recovery criteria are met, the Emergency Director may advise the Offsite Emergency Coordinator that reentry/recovery may start.

No.: 10-S-01-1 Revision: 109 Page: 10

Title:

Activation of the Emergency Plan 6.5 Records and Reoorts No.: 10-S-01-1 Revision: 109 Page: 11 6. 5. 1 The Manager, Emergency Preparedness is responsible for generating a report on the activation of the Emergency Plan. The report should include the following:

a.

Copies of appropriate paperwork generated by the event including: notification forms, checklists, logbooks, survey maps, dose calculations etc.

b.

Observations and comments from the personnel involved in the

event, 6.5.2 The Manager, Emergency Preparedness is responsible for ensuring that all observations and comments are tracked in Emergency Preparedness Action Tracking System, in accordance with 01-5-10-3.

6.6 EP Form EPP 01-02 (Flow Chart) Revision Process 6.6.1 The Manager, Emergency Preparedness is responsible for reviewing all changes to Attachment I, Emergency Classifications, for Impact on ETP 01-02 (Flow Chart).

a.

If EPP 01-02 (Flow Chart) is changed, before procedure 1O-S-01-1 is issued, the Manager, Emergency Preparedness is responsible for verifying the following and that documentation on EP Form EMP 01-03 is complete.

(1) All required training is complete.

(2) Color laminated copies of the revised EPP 01-02 (Flow Chart) are available and stamped with the correct controlled copy number for the following locations:

Control Room (1)

S imu 1 at o r (1)

TSC

( 2 )

EOF (2)

Back up TSC (1)

Back Up EOF (1)

(3) Non-color copies of the revised EPP 01-02 (Flow Chart) are available and stamped with the correct controlled copy number for all controlled copies of procedure 10-S-01-1, Activation of the Emergency Plan.

b.

Once procedure revision for 10-S-01-1, Activation of the Emergency Plan is approved for issue, the distribution of color laminated copies of EPP 01-02 and 10-5-01-1, Activation of the Emergency Plan procedure from document control must be coordinated to ensure all required elements are issued concurrently.

GRkW GULF NUCLEAR STATION 10-s-01-1 Attachment I Revision 109 Page 1 of 25

1.

2.

3.

4.

5.

6.

7.

8.

9.

10.

11.

12.

1 3 -

14.

1 5 -

1 6.

17.

18.

TABLE OF CONT ENFS CATEGORY Safety System Functions Abnormal Primary Leak Rate/Low Reactor Water Level Core Fuel Damage Steam Leaks Abnormal Effluent, Gaseous Abnormal Effluent, Liquid Major Electrical Failures, AC Major Electrical Failures, DC Control Room Evacuation Fire Plant Shutdown Function Abnormal In-plant Radiation/Airborne Contamination Levels Fuel Handling Accident Security Threat Hazards to Plant Operations Natural Events Loss of Assessment, Comunication, Annunciator Equipment Discretionary I

Any changes made to information in Attachment I may require changes t o EPP 01-02 (Flowchart).

PAGE 2,3 4

5,6,7,8 8

9,10,11 11 12,13 13 1 4 1 4 15,16 17 17,18 19 20,21,22 23 24 24,25

GRdND GULF NUCLEAR STATION 15-S-01-1 Attachment I Revision 109 Page 2 of 25 EMERGENCY CLASSIFICATIONS CATSGORY

1. Safety System Functions INITIATING CONDITION

1. Inability to reach required shutdown within Technical Specification time limits EMERGENCY ACTION LEVEL Failure to reach the required Plant Mode within Technical Specification action statement time frames for sny of the following LCO's:

1.

2.

3.

4.

5.

6.

7.

3.

Safety/relief Valves 3.4.4 or ECCS - Operating 3.5.1 Q.x Primary Containment 3.6.1.1 or Primary Containment Airlocks 3.6.1.2 or Primary Containment Isolation Valves 3.6.1.3 a

Low Low Set Valves 3.6.1.6 or Residual Heat Removal Containment Spray 3.6.1.7 or Suppression Pool Average Temperature 3.6.2.1 or Suppression Pool Level 3.6.2.2 (Continued)

EMERGENCY CLASSIFICATION

GRAND GULF NUCLEAR STATION 10-s-01-1 Attachment I CATEGORY Revision 109 Page 3 of 25

1. Safety System Functions (Cont.

1 INITIATING CONDITION

1. Inability to reach required shutdown within Technical Specification time limits (Cont.

)

2. Failure of a safety/

relief valve to close following reduction of applicable pressure to below reset point ECCS - Emergency Core Cooling System EMERGENCY ACTION LEVEL or

10. Suppression Pool Makeup System 3.6.2.4 PT

11. Secocd Containment 3.6.4.1 or

12. Second Containment Isolation Valve 3.6.4.2 or

13. Standby Gas Treatment System 3.6.4.3 9.x

14. Drywell 3.6.5.1 or

15. Drywell Airlocks 3.6.5.2 Qx

16. Drydell Isolation Valves 3.6.5.3

1. Shift Manager determines a SRV is stuck open in plant Mode 1, 2, or 3.

EMERGEFFCY CLASSIFICATION UNUSUAL mNT

GRAND GULF NUCLEAR STATION 10-s-01-1 Attachment I Revision 109 Page 4 of 25 CATEGORY 2

Abnormal Primary Leak Rate/

LOW Reactor Water Level EMERGENCY CLASSIFICATION INITIATING CONDITION

1. Exceeding primary coolant system leak rate

2. Coolant leak rate

> 50 g p m 3. Known loss of coolant greater than makeup pump capacity EMERGENCY ACTION LEVEL While in modes 1,2, or 3:

1. > 5 gpm unidentified leakage OL-

2. > 30 gprn total leakage Averages over previous 24 hr period calculated to be

> 50 gpm while in Plant Mode 1, 2 or 3

1. Total leakage

1. RPV water level

< -167 inch and

2. Makeup capacity unable to increase reactor water level EMERGENCY CLASS IF ICATI ON UNUSUAL EVENT ALERT SITE AREA EMERGENCY

1 10-5-01-1 Attachment I GWiND GULF NUCLEAR STATION Revision 109 Page 5 of 2 5 CATEGORY

3. Core Fuel Damage i - Micro Cur:

INITIATING CONDITION

1. Fuel damage indication

2. Severe loss of fuel cladding

?S EMERGENCY ACTION LEVEL

1. Increase of 285 mR/hr in 30 minutes on OFFGAS pretreatment monitor

2. OFFGAS pretreatment monitor reading > 1,400 mR/Hr or 3. Laboratory analysis of coolant sample indicates > 0.2 pCi/ml dose equivalent 1-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or

4. Laboratory analysis of coolant sample indicates > 4.0 pCi/ml dose equivalent 1-131

1. OffGAS pretreatnent monitor reading

> 14,000 mR/HR or

2. Coolant sample analysis indicates >300 pCi/ml dose equivalent 1-131 or 3. Main steam line radiation exceeds radiation monitor trip setpoint EMERGENCY CLASSIFICATION UNUSUAL EVENT ALERT

GFLAND GULF NUCLEAR STATION 10-s-01-1 CATEGORY Revision 109

3. Core Fuel Damage (Cont.

1 Attachment I pCi - micro Curies Page 6 of 25 INITIATING CONDITION 3. Degraded core with possible loss o f coolant EMERGENCY ACTION LEYEL I. RDV water level be deternined

-167" or cannot 2. a. High coolant activity indicated by analysis of sample > 300 pCi/ml dose equivalent 1-131 4_r

b. Containment or Dry-well hjjdrogen concentration greater than 0.5%

EMERGENCY CLASS I FICAT I ON SITE AREA EMERGENCY

GRAND GULF NUCLEAR STATION 10-s-01-1 Attachment I Revision 109 Page 7 of 25 flCi - Micro Curies EMERGZNCY CLASSIFICATIONS INITIATING CONDITION

4. Loss of 2 of 3 fission product barriers with a potential loss of 3rd barrier EHERGENCY ACTION LWEL

1. Loss of any two of the following fission product boundaries with a potential for loss of the third:

Fuel Claddinq m

a. Coolant sample analysis indicates >30C yCi/ml dose equivalent 1-131 -

or

b. >lo00 R/Hr in Drywell Potential Loss

a. RPV water level cannot be restored and maintained > -167 in.

or

b. RPV pressure cannot be restored and maintained

> 57 psig when in R?V flooding.

or

c. >lo0 R/Hr in Drywell Teactor Pressure Boundarv Loss

a. Drywell pressure >1.23 psig and indication of a steam leak in the drywell or

b. Main steam line not isolated 9t;:

c. RCIC steaz line break outside containment with inability to isolate Potential Loss Total reactor coolant leakage calculated to be 250 gpm or 1. >10 R/hr incontainment EMERGENCY CLASSIFICATIOK GENERQ EMERGENCY

GWiND GULF NUCLEAR STATION 10-5-01-1 Attachment I Revision 109 Page 8 of 25 1

CATEGORY 3. Core Fuel Damage EZ-IERGEXCY CLASSIFICATIONS INITIATING CONDITION

4. Loss of 2 of 3 Fission product Barriers with a Potential l o s s of 3rd barrier. (Cont. )

1. Main steam line break outside the containment with significant MSIV leakage.

2. RCIC steam line break outside the containment with significant isolation valve leakage 3. Main steam line break outside of containment which cannot be isolated.

4. RCIC steam line break outside of containment which cannot be isolated.

EMERGENCY ACTION LEVEL Primarv C on ta inmen t s;Lnss

a. Primary Containment pressure >56 psig or

b. Loss ofability to isolate Drywell or primary containment Leakage into Areas Outside the Primary Containment

a. Primary containment pressure >22 psig or

b. Operation in the Unsafe Region of HCTL a PSP Curve.

or

c. Operation in the Unsafe Region of HDOL Curve with Hydrogen Igniters De-Energized

1. Isolation initiated and abnormal leakage down stream of MSIVs

( > 10 gpm or 5000 lbm/hr)

1. Isolation initiated and abnormal leakage down stream of isolation valves ( > 10 gpm or 5000 lbm/hr)

1. Isolation required due to confirmed steam line break One or more main steam lines fail to isolate

1. Isolation required due to confirmed steam line break aad RCIC steam line fails to isolate MSIV - Main Steam Isolation Valve PSP - Pressure Suppression limit RCIC - Reactor Core Isolation Cooling HCTL - Heat Capacity Temperature Limit HDOL - Hydrogen Deflagration Overpressure Limit EMERGENCY CLASSIFICATION GENERAL EMERGENCY ALERT SITE AREA EMERGENCY

GFANII GULF NUCLEAR STATION 10-s-01-1 Attachiient I CATEGORY

5. &normal

Effluent, GASEOUS Revision 109 Page 9 of 25 ZO - Limited INITIATING CONDITION

1. Radiological effluent release rate exceeds TRM Spec limit

2. Radiological effluent

>lo times TRM Spec 1 imi t mdition for Operation SGTS - Standby Gas Treatment System TRM 2 Technical Requirements Manual EMERGEXCY ACTION LEVEL

1. Entering the action statement of the following LCOs in the Radioactive Gaseous Effluent section of the TRM Specs 6.11.4, 6.11.5, and 6.11.6

1. High high radiation alarms on ONE OR MORE monitors :

a. Radwaste Bldg vent exhaust

b. Fuel handling vent exhaust

c. Containment vent exhaust

d. Turbine Bldg vent exhaust and Summation of monitors (including SGTS A and B) exceeds 10 times TRM Spec limit (6.11.4)

EMERGENCY CLASSIFICATION UNUSUAL FrnT ALERT

GRAND GULF IWCLEAR STATION f 10-s-01-1 Revision 109 Attachment I Page 10 of 25 CATEGORY

5. Abnormal Effluent,

GASEOUS (Cont.

1 AR - Final S INITIATING CONDITION

3. Effluent monitors detect levels corresponding to site boundary exposure of:

a. 2 50 r W H r (for 30 minutes) Whole Body -

Or

b. 2 500 m W H r (for 2 minutes) Wnole Body QX

c. 2 250 mWhr (for 30 min) to the Thyroid.

NOTE

\\

Adverse Yeteorology

-Stability Class F, And speed 1 m/sec, site boundary X/Q LO80 E-6 sec/m3 (FSAR Table 15 5-12]

ety Analysis Report pCi - micro Curies Ci - Curies EMERGENCY ACTION LEVEL 1 I

2.

3.

Any post accident effluent radiation monitor confirm release rates corresponding to:

a. 0.5 Ci/sec Noble Gas for 30 minutes or

b. 6.0 E-4 Ci/sec Iodine for 30 minutes or

c. 5.0 Ci/sec Noble Gas for 2 minutes QX

d. 6.0 E-3 Ci/sec Iodine for 2 minutes or Radiation monitoring teams report radiation and/or Iodine concentration readings at the site boundary corresponding to:

a. 50 mR/Hr for 30 minutes or

b. 500 mRzr for 2 minutes or

c. 6.OE-6 pCi/cc Containment Post Accident Radiation Monitor :

a. >330 R/HR for 30 93:

Iodine QX minutes

b. >3300 R/HR for 2 minutes EMERGENCY CLASSIFICATION SITE AREA EMERGEVCY

GRAND GULF NUCLEAR STATION 10-5-01-1 Attachment I Revision 109 Page 11 of 25 CATEGORY

5. Abnormal Effluent,

GASEOUS (Cont.

1

6. Abnormal Effluent,

LIOUID CDE - Total Ef INITIATING CONDITION 4.Effluent monitor(s1 (UNDER ACTVAL METEORO-LOGICAL CONDITIONS 1

detect levels corresponding to site bounda-ry exposure of:

1000 mRem Dose Commitment Whole Body or 5000 mRem Dose Commitment Thyroid 1.Radiological Effluent Release Rate exceed3 TRM Spec limit 2.Radiological Effluent

>lo times TRM Spec 1 imi t ictive Dose Emivalent CDE - Committed Dose Equivalent TRM - Technical Requirements Manual EMERGENCY ACTION LEVEL

. Effluent monitor(s1 LOGICAL COND ITIONS

)

confirms release rates corresponding to site boundary exposure of:

(UNDER ACTUAL METEORO-

a. 1000 mRem TEDE or

b. 5000 mRem Thyroid CDE or

. Radiation monitoring teams report radiation and/or iodine concen-trations readings (at the site boundary) corresponding to:

a. 1000 m e m TEDE O r

b. 1.2E-5 pCi/cc Iodine Entering the action statement of TRM Spec 6.11.1, in the Radioactive Liquid Effluent section of TRM Spec Liquid release > 10 times the limit of TRM Spec 6.11.1 in the Radioactive Liquid Effluent section of TRM Spec EMERGENCY CLASSIFICATION GENEXAL EMERGENCY UNUSUAL F a N T ALERT

GRAND GULF NUCLEAR STATION 10-s-01-1 Attachment I Revision 109 Page 12 of 25 CATEGORY

7. Major Electrical Failures (AC)

INITIATING CONDITION

1. Total l o s s of offsite power QE Loss of onsite AC power capability 2. Total loss of offsite and Loss of ALL onsite power 5 15 minutes power EMERGENCY ACTION LEVEL

1.

2.

Loss of offsite power to :

a. 15AA and

b. 16AB and

c. 17AC Qx Loss of U three divisional diesel generators while in Plant Operational Condition 1, 2 or 3

1. Loss of offsite power to :

a. 15AA

b. 16AB

c. 17AC and

2. Loss of all three divisional diesel generators d

3. 515 minutes EMERGENCY CLASSIFICATION UNUSUAL EVENT ALERT

GRAND GULF NUCLEAR STATION 10-s-01-1 At tachmen t I CATEGORY Revision 109 Page 13 of 25

7. Major Electrical Failures (AC)

(Cont

. I

8. Major Electrical Failures (DC)

EMERGENCY CLASSIFICATIOm INITIATING CONDITION

3. Total loss of offsite power and Loss of ALL onsite power >15 minutes

1. Loss of onsite ESF DC power for 5 15 minutes 2. Loss of onsite ESF DC power for > 15 minutes EMERGENCY ACTION LEVEL

1. Loss of offsite power to:

a. 15AA and

5. 16AB and

c. 17AC and

2. Loss of all three divisional diesel generators -

and 3. >15 minutes

1. Loss of Division 1, 2 and 3 (125 Vdc for 115 minutes)

I. Loss of Division 1, 2 and 3 (125 Vdc or

>15 MINUTES)

EMERGENCY CLASSIFICATION SITE AREA EMERGENCY ALERT SITE AREA EMERGENCY

G W

GULF hTCLEAR STATION 10-5-01-1 Attachment I Revision 109 Page 14 of 25

9. Control Evacuation EXERGENCY C LASSIFICAT XO@

INITIATING CONDITION

1. Evacuation of the Control Room Control established at the remote shutdown panel

2. Evacuation of the Control Room and Control not established at the remote shutdown panel within 15 minutes

1. Fire lasting > 10 minutes after di s c overy 2. Fire potentially affects safety systems

3. Fire compromising the i

functions of ESF Sys t ems EMERGENCY ACTION LEYEL

1. Control Room evacuated i2.n.d

2. Control of shutdown systems established at the remote shutdown panel

1. Control Room evacuated and

2. Unable to establish control of shutdown systems at the remote shutdown panel within 15 minutes of evacuating the Control Room

1. A fire within the power block, fire water pump house or CO2 skid lasting >10 minutes from the time of notification

1. A fire defeating safety system electrical division

1. A fire defeating MORE THAN ONE safety system electrical division EMERGENCY CLASSIFICATION ALERT SITE AREA EMERGENCY UNUSUAL EVENT ALERT SITE AREA EMERGENCY

GRANE GULF NUCLEAR STATION 10-s-01-1 Attachment I CATEGORY Revision 109 Page 15 of 25

11. Plant Shutdown Function APRM - Average EKERGBNCY CLASSIFICATIONS INITIATING CONDITION

1. Complete loss of functions needed for plant COLD shutdown.

2. Failure of the Reactor Protection System to initiate and complete a scram which brings the reactor subcritical ower Range Monitor EMERGENCY ACTION LEVEL

1. All control rods fully inserted and

2. The determination that there are no longer enough systems functional to attain or maintain the reactor coolant <20O0F

1. Scram conditions confirmed 2a.

2b.

and More than one rod is greater than position 02 or rod position is unknown for more than one rod and SRM's are either upscale or countrate is increasing (Assuming SRMs are f u l l in) and 3. Reactor power ~

4 on APRM (APRM Downscale light on)

EMERGENCY CLASSIFICATION ALERT

G Z W GULF NUCLEFiR STATION 10-s-01-1 Attachment I Revision 109 Page 16 of 25 INITIATING CONDITION

3. Complete loss of functions needed for plant EX shutdown

4. Transient requiring operation of shutdown systems with failure to scram and continued power generation EMERGENCY ACTION LEVEL

1. HPCS and RCIC not functional and

2. Not able to depressurize with SRVs and 3. Main Condenser is not available I. Scram conditions confirmed and inserted to between 00 and 02 2. All control rods NOT

5. Reactor power 24% on APRM EMERGENCY CLASS IF ICAT I Oh SITE AREA EMERGENCY J:ADM-SRVS/TECH-PUB/RENISION/iOSOll.DOC

GRAND GULF NUCLGZR STATION 10-s-01-1 Attacl-unent I CATEGORY c---

Revision 109 Page 17 of 25

12. Abnormal In-plant Radiation/

Airborne Con tam-inat ion Levels Hand1 ing Accident CAM - Continuous PSIIERGENCY CLASS I F I C A T I O E INITIATING CONDITION

1. Radiation levels or airborne contamination indicate a severe degradation in the control of radioactive materials

1. Fuel damage accident with release o f radioactivity to Containment or Auxiliarj Building 2. Major damage to spent fuel assembly in Containvent or Auxilia-ry Building

.r Monitor EMERGENCY ACTION LETEL

1. Verification o f area radiation monitor reading =. 1000 times setpoint Qx Verification o f CAM reading >lo00 times setpoint

1. Notification of a spent fuel damaging accident m d 2. High high radiation alarms on either

a. Fuel handling vent exhaust or

b. Containment vent exhaus t 1.a. Notification of a spent fuel damaging accident 01

b. Low water level in spent fuel pool below top of spent fuel and unable to restore level to above fuel.

and (Continued)

EMERGENCY CLASSIFICATION ALERT ALERT SITE ?AEZi EMERGENCY

GRAND GULF NUCLEAR STATION 10-5-01-1 Attachment I CATEGORY

13. Fuel Handling Accident (Cont.

)

Revision 109 Page 18 of 2 5 Ci - Curies pCi - Micro Curies EMERGENCY C WlSSIFICATIO~

INITIATING CONDITION fuel assembly in Containment or Auxiliary Building

2. Major damage to spent (Cont.)

EMERGENCY ACTION LEVEL

2. Any post accident effluent radiation monitor confirms Noble Gas, Iodine release rates corresponding to :

a. 0.5 Ci/sec Noble Gas (30 minutes) 01

b. 6.0 E-4 Ci/sec Iodine (30 minutes)

Or

c. 5.0 Ci/sec Noble Gas (2 minutes) 01:

d. 6.0 E-3 Ci/sec Iodine (2 minutes) or

3. Radiation monitoring teams report Radiation and/or Iodine concentration readings at the site boundary corresponding to:

a. 50 mR/Hr (for 30 minutes) or

b. 500 mR/Hr (for 2 minutes)

c. 6.0 E-6 pCi/cc Iodine EMERGENCY CLASS I FICATION SITE AREA EMERGENCY

GRAND GULF NUCLEAR STATION 10-s-01-1 Attachment I CATEGORY

14. Security Threat Revision 109 Page 19 of 25 1

I I

EMERGENCY CLASSIFICATIONS INITIATING CONDITION

1. Security threat or Attempted entry or Attempted sabotage

2. A credible site -

specific security threat notification 3. On-going Security compromise 4. Imminent loss of physical control of the plant.

5. Loss of physical control of the plant.

EMERGENCY ACTION LEVEL

1. Based upon the assessment of the alarm or the event reported by Security. Actual threat must be determined prior to establishing an emergency classification.

1. The Shift Manager determines that GGNS has received a credible threat against the site. Credible means the threat notification has been received from, or validated by, a trustworthy source (FBI, NRC, Claiborne County Sheriff's Off ice, Plant Manaqement, etc.1

1. Identification of adversaries attempting to command areas of the..

plant, but not controllinq shutdown capability or vital areas.

1. Physical attack on the plant involving imminent occupancy of the Control Room, Remote Shutdown Panel or vital areas.

1. Physical attack on the plant has resulted in unauthorized personnel occupying the Control Room or the Remote Shutdown Panel or controlling Decay Heat Removal, Reactor Water Level or Reactivity Control capability.

EMERGENCY CLASSIFICATION UMJSUU EVENT ALERT SITE AREA EMERGENCY GENEP&

EMERGENCY

GRAND GULF NUCLEAlY STATION 10-s-01-1 Attachment I CATEGORY Revision 109 Page 20 of 25

15. Hazards to Plant Operations EMERGENCY C LASSIFICATIOW INITIATING COi'+TITIOM 1 Hazards being experienced or projected with the potential or dearadat ion of the level of safety of the plant EMERGENCY ACTION LEVEL

1. Notification of an aircraft crash onsite outside the protected area or Notification of unusual aircraft activity over the facility

95.

Notification of an onsite explosion (does not affect plant operation) 01 Determination that a release of toxic, oxygen displacing, or flanunable gas will significantly hamper the ability of personnel to perform activities affecting plant safety QZ A manual or automatic scram initiated because of a turbine blade failure that has not penetrated the casing EMERGENCY CLASSIFICATION UNUSUAL WENT

GR4PJ-D GULF NUCLEAR STATION 10-s-01-1 Revision 109 Attachment I Page 21 of 25 CATEGORY

15. Hazards to Plant Operations (Cont.

1 I

GNRO-2002/00068, Changes to Emergency Plan Implementing Procedures, Rev. 109 10-S-01-1

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