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

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)

Text

ter Waterloo Road P.O. Box 756 Port Gibson, MS 39150 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) (w/a)

Levanway D. E. (Wise Carter) (w/a)

Reynolds N. S. (w/a)

Smith L. J. (Wise Carter) (w/a)

Thomas H. L. (w/o)

U.S. Nuclear Regulatory Commission ALL LETTERS ATTN: Mr. E. W. Merschoff ( ~ 1 2 )

611 Ryan Plaza Drive, Suite 400 Arlington, TX 7601 1-4005 U.S. Nuclear Regulatory Commission ATTN: Mr. David H. Jaffe NRR/DLPM ( ~ 1 2 ) SERVICE MAIL DELIVERY ATTN: FOR ADDRESSEE ONLY ADDRESS ONLY ATTN: U.S. Postal Delivery Address Only Mail Stop OWFN17D-I Washington, D.C. 20555-0001

PLANT OPERATIONS MANUAL Volume 10 10-s-01-1 Section 01 Revision: 109 Date : 7 /3 1/O 2 EMZRGENCY PLAN P R O C E D r n SAFEm RELATED Prepared :

Reviewed :

Concurred:

OSRC :

Approved :

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, 2x3 1-4 None 109 None 5 1,2 6 3 7 4 8 5,6 9 None 10 7,8 11 None 12 9 13 10 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 I. OVERVIEW / SIGNATURES Facility: b6N5 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] The proposed activity is editorial/typographicaias defined in Section 5.2.2.1.

I2 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): ( o n l y the sections indicated must be included in the Review.)

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

) 1 Sections I, 11, 111, and V required 1 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 No.: 10-S-01-1 Revision: 109 Page: i Emergency Plan 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 5 0 . 5 9 Review Form I ( 1 No I Not required per LI-101 J

Requirement Implemented by Directive Directive Paragraph Number Name Paragraph Number That Implenents Requirement ANSI N18.7 5.3.9.2.Sl

• GGNS Emer Plan 2.4.53 1.1.1 GGNS Emer Plan 3.3.Sl 2.1.2 GGNS Emer Plan 6.2.2.S3 & S4 2.1.1, 6.1.2 S2 GGNS Emer Plan 5.4.5.a,b,c 2.2 GGNS Emer Plan 5.4.4 2.3 GGNS Emer Plan 3.1.S2 6.1.2 GGNS Emer Plan 6.2.2.Sl & S2 6.1.2 (Note)

GGNS Emer Plan 4.l.4.S3 Attachment I GGNS Emer Plan 4.1.S3 6.1.4, 6.3 GGNS Emer Plan 4.1.S13 6.1.3 (Note)

GGNS Emer Plan 3.3 .S6 .b 6.1.3 GGNS Emer Plan 6.2.4.sl1 & s12 6.1.4.i(1)

GGNS Emer Plan 6.2.4.513 6.1.4.i(2)

GGNS Emer Plan 6.2.4.S14 6.1.4.i(3)

GGNS Emer Plan 4.1.4.S2 6.1.4.j (1)

GGNS Emer Plan 6.3.1.sl & 52 6.2.1 GGNS Emer Plan 6.3.2 6.2.la GGNS Emer Plan 6.3.3, 6.3.4 6.2.lb GGNS Emer Plan 9.3.s7 Attachment I1 (Note)

GGNS Emer Plan Table 4-1 Attachment I GGNS Fmer Plan 7.5.3.a.2.e 5.30 GNRI-93/00171 93-13-01, Item 6 Attachment I, 17.1.1 GGNS Emer Plan 6.5.l.b.S5, S6 6.1.4.j (1)

GGNS Emer Plan 7.5.3.a.3.c 6.1.4.d GGNS Emer Plan 6.2.4.S2 2.1.2 GGNS Emer Plan 6.2.4.S7 & S8 2.4 GGNS Fmer Plan 5.4.S6 6.1.4.i(l),i(2),i(3)

GGNS Emer Plan 3.3.s3 & s4 2.4 GGNS Emer Plan 6.5.1.b 6.1.4 GGNS Emer Plan 6.5.1.A.1 6.1.4.g GGNS Emer Plan 3.3.s5 2.1.2

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

Title:

Activation of the No.: 10-S-51-1 Revision: 109 Page: ii Emergency Plan The Component Database Change Request statement is applicable only to Volume 06 and 07 maintenance directives.

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 No.: 10-S-01-1 Rev. 109 Emergency Plan Evaluation

$OCFR50,54(a) Screening 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 5 0 . 5 4 ( q ) evaluation must be performed.

3. APPROVAL Screening Completed By: 7 lzs l o z Date Screening Reviewed By: fi 7/a*&r Signature Date

G W i GULF NUCLEPA STATION EMEXGENCY PLAN PROCEDLTE TiCle: Activation of the NO.: 1o-s-01-i Revision: 1 0 9 Page: 1 Emergencv Plan l?&r.!2 1.0 PURPOSE AND DISCUSSION 2 2.0 RESPONSIBILITIES 2 3.0 REFEXNCES 3 4.0 ATTACHMENTS 3 5.0 DEFINITIONS 3 6.0 DETAILS 6 6.1 Activation of Emergency Plan 6 6.2 Supplemental Actions 9 6.3 UpgradiRg Emergency Classifications 10 6.4 Terninating Emergency 10 6.5 Records and Reports 6.6 EP form EPP 01-02 ( F l o w Chart) Revision Process 11

Title:

Activation of the No.: 10-S-01-1 Revision: 109 Page: 2 Emergency Plan 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.

2.0 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.

2.1.2 The Shift Manager assumes the role of Emergency Director upon 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.

2.2 ODerations 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 No.: 10-S-01-1 Revision: 109 Page: 3 Emergencv Plan 2.2.2 Coordinating Operations activities outside of the Control Room with the TSC Coordinator.

2.2.3 Providing technical assistance to the Shift Manager.

2.3 Security Cooreinator - 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 Acceptable Deviations to Appendix 1 to NUREG-0654/FEMA-REP-ln.

3.2 GGNS Emergency Plan 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 Page: 4 Emergency Plan 5.5 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.

5.6 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.

5.7 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.

5.8 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 Emeroencv and General Emeraencv.

5.9 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 5.16 Genera1 Emeraencv - An emergency classification in which events are in 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.

5.17 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 No.: i0-S-01-1 Revision: 109 Page: 5 Emergency Plan 5.21 Qnsite - For accountability purposes, the area within the GGNS protected area 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 A l a m 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 nonpregnant adults from exposure and intake during an emergency situation.

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.)

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 No.: 10-S-01-1 Revision: 109 Page: 6 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 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 No.: 10-5-01-1 Revision: 109 Page: 7 Emergency Plan 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 Revision: 109 Page: 8 Emergency Plan 6.1.4 (Cont.)

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 Protective Action Recommendation EVACUATE: 2 Miles All Sectors General Emergency -

and Declared EVACUATE: 5 Miles in Downwind Sectors and SHELTER: Remainder of 10 Mile Emergency Planning Zone (EPZ)

General Emergency EVACUATE: 2 Miles All Sectors Declared and And EVACUATE: 10 Miles in Downwind Sectors Dose Projection or Field Measurement -

and at 2 5 miles corresponds to SHELTER: Remainder of 10 Mile Emergency 1 RernTEDE Planning Zone (EPZ)

Or 5 Rern ThyroidCDE

Title:

Activation of the No.: 10-S-01-1 Revision: 109 Page: 9 6.1.4 (Cont.)

k. Designate shift personnel to perform emergency corrective and assessment actions.

6.2 Sumlemental 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.

6.2.4 The Emergency Director (while in the TSC) may delegate to the TSC Coordinator and/or Radiation Protection Manager the responsibility for logging all information relative to the emergency (for event reconstruction).

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

c. If an evacuation is required, notify Security if possible and evacuate affected areas in accordance with Step 6.1.4g.

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.

Title:

Activation of the No.: 10-S-01-1 Revision: 109 Page: 11 Emergency Plan 6.5 Records and Reoorts 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 imu1ator (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 Revision 109 Attachment I Page 1 of 2 5 TABLE OF CONTENFS CATEGORY PAGE

1. Safety System Functions 2,3

2. Abnormal Primary Leak Rate/Low Reactor Water Level 4

3. Core Fuel Damage 5,6,7,8

4. Steam Leaks 8

5. Abnormal Effluent , Gaseous 9,10,11

6. Abnormal Effluent, Liquid 11

7. Major Electrical Failures, AC 12,13

8. Major Electrical Failures, DC 13

9. Control Room Evacuation 14

10. Fire 14

11. Plant Shutdown Function 15,16

12. Abnormal In-plant Radiation/Airborne Contamination Levels 17 13 - Fuel Handling Accident 17,18

14. Security Threat 19 15 - Hazards to Plant Operations 20,21,22

16. Natural Events 23

17. Loss of Assessment, Comunication, Annunciator Equipment 24

18. Discretionary 24,25 I

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

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

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

1. Safety/relief Valves 3.4.4 or

2. ECCS - Operating 3.5.1 Q.x

3. Primary Containment 3.6.1.1 or

4. Primary Containment Airlocks 3.6.1.2 or

5. Primary Containment Isolation Valves 3.6.1.3 a

6. Low Low Set Valves 3.6.1.6 or

7. Residual Heat Removal Containment Spray 3.6.1.7 or

3. Suppression Pool Average Temperature 3.6.2.1 or

3. Suppression Pool Level 3.6.2.2 (Continued)

GRAND GULF NUCLEAR STATION 10-s-01-1 Revision 109 Attachment I Page 3 of 25 EMERGEFFCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL CLASSIFICATION

1. Safety 1. Inability to reach or UNUSUAL m NT System required shutdown Functions within Technical 10. Suppression Pool (Cont.1 Specification time Makeup System 3.6.2.4 limits (Cont.)

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 2 . Failure of a safety/ 1. Shift Manager relief valve to close determines a SRV is following reduction stuck open in plant of applicable Mode 1, 2, or 3 .

pressure to below reset point ECCS - Emergency Core Cooling System

GRAND GULF NUCLEAR STATION 10-s-01-1 Revision 109 Attachment I Page 4 of 25 EMERGENCY CLASSIFICATION EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL CLASSIFICATION 2 Abnormal 1. Exceeding primary While in modes 1,2, or 3: UNUSUAL EVENT Primary coolant system leak 1. > 5 gpm unidentified Leak Rate/ rate leakage LOW Reactor Water Level OL-

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

2. Coolant leak rate 1. Total leakage ALERT

> 50 g p m calculated to be

> 50 gpm while in Plant Mode 1, 2 or 3 3 . Known loss of 1. RPV water level SITE AREA coolant greater than < -167 inch EMERGENCY makeup pump capacity and

2. Makeup capacity unable to increase reactor water level

GWiND GULF NUCLEAR STATION 10-5-01-1 Revision 109 Attachment I Page 5 of 2 5 EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL CLASSIFICATION

3. Core Fuel 1. Fuel damage UNUSUAL EVENT Damage indication

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

2. Severe loss of fuel ALERT cladding

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 1 i - Micro Cur: ?S

GFLAND GULF NUCLEAR STATION 10-s-01-1 Revision 109 Attachment I Page 6 of 25 EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEYEL CLASSIFICATION

3. Core Fuel 3 . Degraded core with I. RDV water level SITE AREA Damage possible l o s s o f -167" or cannot EMERGENCY (Cont.1 coolant be deternined 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 %

pCi - micro Curies

GRAND GULF NUCLEAR STATION 10-s-01-1 Revision 109 Attachment I Page 7 of 25 EMERGZNCY CLASSIFICATIONS EMERGENCY INITIATING CONDITION EHERGENCY ACTION L W E L CLASSIFICATIOK

4. Loss of 2 of 3 1. Loss of any two of the GENERQ fission product following fission EMERGENCY barriers with a product boundaries with potential loss of 3rd a potential for loss of barrier 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 L o s s

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. >10R/hr incontainment flCi - Micro Curies

GWiND GULF NUCLEAR STATION 10-5-01-1 Revision 109 Attachment I Page 8 of 25 EZ-IERGEXCY CLASSIFICATIONS 1 EMERGENCY CLASSIFICATION CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL 3 . Core Fuel 4. Loss of 2 of 3 Primarv Containment GENERAL Damage Fission product s;Lnss EMERGENCY Barriers with a a. Primary Containment Potential l o s s of 3rd pressure > 5 6 psig barrier. (Cont. ) or

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

a. Primary containment pressure > 2 2 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. Main steam line break 1. Isolation initiated and ALERT outside the abnormal leakage down containment with stream of MSIVs significant MSIV ( > 10 gpm or 5000 lbm/hr) leakage.

2. RCIC steam line break 1. Isolation initiated and outside the abnormal leakage down containment with stream of isolation significant isolation valves ( > 10 gpm or 5000 valve leakage lbm/hr) 3 . Main steam line break 1. Isolation required due SITE AREA outside of to confirmed steam EMERGENCY containment which line break cannot be isolated.

One or more main steam lines fail to isolate

4. RCIC steam line break 1. Isolation required due outside of to confirmed steam line containment which break cannot be isolated. 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

GFANII GULF NUCLEAR STATION 10-s-01-1 Revision 109 Attachiient I Page 9 of 25 EMERGENCY CATEGORY INITIATING CONDITION EMERGEXCY ACTION LEVEL CLASSIFICATION

5. &normal 1. Radiological effluent 1. Entering the action UNUSUAL FrnT Effluent, release rate exceeds statement of the GASEOUS TRM Spec limit following LCOs in the Radioactive Gaseous Effluent section of the TRM Specs 6.11.4, 6.11.5, and 6.11.6

2. Radiological effluent 1. High high radiation ALERT

>lo times TRM Spec alarms on ONE OR MORE 1imit 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)

ZO - Limited mdition for Operation SGTS - Standby Gas Treatment System TRM 2 Technical Requirements Manual

GRAND GULF IWCLEAR STATION f 10-s-01-1 Revision 109 Attachment I Page 10 of 25 EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL CLASSIFICATION

5. Abnormal 3. Effluent monitors 1 I Any post accident SITE AREA Effluent , detect levels effluent radiation EMERGEVCY GASEOUS corresponding to monitor confirm release (Cont.1 site boundary rates corresponding to:

exposure of:

a. 0.5 Ci/sec Noble

a. 2 50 r W H r (for Gas for 30 minutes 30 minutes) Whole Body or Or

b. 6.0 E-4 Ci/sec

b. 2 500 m W H r (for Iodine for 30 minutes 2 minutes) Wnole -

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

c. 2 250 m W h r (for 30 min) to the QX Thyroid.

d. 6.0 E-3 Ci/sec Iodine for 2 minutes NOTE -or

\

Adverse 2 . Radiation monitoring Yeteorology teams report radiation

-Stability Class F, and/or Iodine And speed 1 m/sec, concentration readings site boundary X/Q at the site boundary LO80 E-6 sec/m3 corresponding to:

(FSAR Table 15 a. 50 mR/Hr 5-12] for 30 minutes or

b. 500 m R z r for 2 minutes or

c. 6.OE-6 pCi/cc Iodine QX 3 . Containment Post Accident Radiation Monitor :

a. >330 R/HR for 30 minutes 93:

b. >3300 R/HR for 2 minutes AR - Final S ety Analysis Report pCi - micro Curies Ci - Curies

GRAND GULF NUCLEAR STATION 10-5-01-1 Revision 109 Attachment I Page 11 of 25 EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL CLASSIFICATION

5. Abnormal 4.Effluent monitor(s1 . Effluent monitor(s1 GENEXAL Effluent , (UNDER ACTVAL METEORO- (UNDER ACTUAL METEORO- EMERGENCY GASEOUS LOGICAL CONDITIONS1 LOGICAL COND ITIONS)

(Cont.1 detect levels confirms release rates corresponding to site corresponding to site bounda-ry exposure of: boundary exposure of:

1000 mRem Dose a. 1000 mRem TEDE Commitment Whole Body or or 5000 mRem Dose b. 5000 mRem Thyroid Commitment 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

6. Abnormal 1.Radiological Effluent Entering the action UNUSUAL F a N T Effluent , Release Rate exceed3 statement of TRM Spec LIOUID TRM Spec limit 6.11.1, in the Radioactive Liquid Effluent section of TRM Spec 2.Radiological Effluent Liquid release > 10 ALERT

>lo times TRM Spec times the limit of TRM 1imit Spec 6.11.1 in the Radioactive Liquid Effluent section of TRM Spec CDE - Total Ef ictive Dose Emivalent CDE - Committed Dose Equivalent TRM - Technical Requirements Manual

GRAND GULF NUCLEAR STATION 10-s-01-1 Revision 109 Attachment I Page 12 of 25 EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL CLASSIFICATION

7. Major 1. Total l o s s of offsite 1. Loss of offsite power UNUSUAL EVENT Electrical power to :

Failures (AC) QE a. 15AA Loss of onsite AC and power capability

b. 16AB and

c. 17AC Qx 2 . Loss of U three divisional diesel generators while in Plant Operational Condition 1, 2 or 3 2 . Total loss of offsite 1. Loss of offsite power ALERT power to :

and a. 15AA Loss of ALL onsite power 5 15 minutes

b. 16AB

c. 17AC and

2. Loss of all three divisional diesel generators d

3 . 515 minutes

GRAND GULF NUCLEAR STATION 10-s-01-1 Revision 109 Attachment I Page 13 of 25 EMERGENCY CLASSIFICATIOm EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL CLASSIFICATION

7. Major 3. Total loss of offsite 1. Loss of offsite power SITE AREA Electrical power to: EMERGENCY Failures (AC) and a. 15AA (Cont. I Loss of ALL onsite and power >15 minutes

5. 16AB and

c. 17AC and

2. Loss of all three divisional diesel generators and 3 . >15 minutes

8. Major 1. Loss of onsite ESF 1. Loss of Division 1, 2 ALERT Electrical DC power for 5 15 and 3 (125 Vdc for Failures minutes 115 minutes)

(DC) 2 . Loss of onsite ESF I . Loss of Division 1, 2 SITE AREA DC power for > 15 and 3 (125 Vdc or EMERGENCY minutes >15 MINUTES)

G W GULF hTCLEAR STATION 10-5-01-1 Revision 109 Attachment I Page 14 of 25 EXERGENCY CLASSIFICATXO@

EMERGENCY INITIATING CONDITION EMERGENCY ACTION LEYEL CLASSIFICATION

9. Control 1. Evacuation of the 1. Control Room evacuated ALERT Control Room Evacuation i2.n.d

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

2. Evacuation of the 1. Control Room evacuated SITE AREA Control Room EMERGENCY and and

2. Unable to establish Control not control of shutdown established at the systems at the remote remote shutdown panel shutdown panel within within 15 minutes 15 minutes of evacuating the Control Room

1. Fire lasting > 10 1. A fire within the power UNUSUAL EVENT minutes after block, fire water pump disc overy house or CO2 skid lasting >10 minutes from the time of notification

2. Fire potentially 1. A fire defeating ALERT affects safety safety system electrical systems division

3. Fire compromising the 1. A fire defeating MORE SITE AREA functions of ESF THAN ONE safety system EMERGENCY Systems i electrical division

GRANE GULF NUCLEAR STATION 10-s-01-1 Revision 109 Attachment I Page 15 of 25 EKERGBNCY CLASSIFICATIONS EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL CLASSIFICATION

11. Plant 1. Complete l o s s of 1. All control rods fully ALERT Shutdown functions needed for inserted Function plant COLD shutdown.

and

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

2. Failure of the 1. Scram conditions Reactor Protection confirmed System to initiate and complete a scram and which brings the reactor subcritical 2a. More than one rod is greater than position 02 or rod position is unknown for more than one rod and 2b. 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)

APRM - Average ower Range Monitor

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

3. Complete loss of 1. HPCS and RCIC not SITE AREA functions needed for functional EMERGENCY plant EX shutdown and

2. Not able to depressurize with SRVs and 3 . Main Condenser is not available

4. Transient requiring I . Scram conditions operation of shutdown confirmed systems with failure to scram and continued and power generation

2. All control rods NOT inserted to between 00 and 02

5. Reactor power 2 4 % on APRM J:ADM-SRVS/TECH-PUB/RENISION/iOSOll.DOC

GRAND GULF NUCLGZR STATION 10-s-01-1 Revision 109 Attacl-unent I Page 17 of 25 PSIIERGENCY CLASSI F I C A T I O E c---CATEGORY 12.Abnormal In-plant Radiation/

INITIATING CONDITION

1. Radiation levels or airborne contamination indicate EMERGENCY ACTION LETEL

1. Verification o f area radiation monitor reading =. 1000 times EMERGENCY CLASSIFICATION ALERT Airborne a severe degradation setpoint Contam- in the control of ination radioactive materials Qx Levels Verification o f CAM reading >lo00 times setpoint

1. Fuel damage accident 1. Notification of a spent ALERT Hand1ing with release o f fuel damaging accident Accident radioactivity to Containment or m d Auxiliarj Building 2 . High high radiation alarms on either

a. Fuel handling vent exhaust or

b. Containment vent exhaust

2. Major damage to spent 1.a. Notification of a SITE ?AEZi fuel assembly in spent fuel damaging EMERGENCY Containvent or accident Auxilia-ry Building 01

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

and (Continued)

CAM - Continuous .r Monitor

GRAND GULF NUCLEAR STATION 10-5-01-1 Revision 109 Attachment I Page 18 of 2 5 EMERGENCY CW l S S I F I C A T I O ~

EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL CLASSIFICATION

2. Major damage to spent

13. Fuel fuel assembly in 2. Any post accident SITE AREA Handling Containment or effluent radiation EMERGENCY Accident Auxiliary Building monitor confirms Noble (Cont.) (Cont.) 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 Ci - Curies pCi - Micro Curies

GRAND GULF NUCLEAR STATION 10-s-01-1 Revision 109 Attachment I Page 19 of 25 1 I I EMERGENCY CLASSIFICATIONS EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL CLASSIFICATION

14. Security 1. Security threat 1. Based upon the U M J S U U EVENT Threat assessment of the alarm or

- or the event reported by Security. Actual Attempted entry threat must be determined p r i o r to or

- establishing an emergency Attempted sabotage classification.

2. A credible site - 1. The Shift Manager specific security determines that GGNS threat notification 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 Office, Plant Manaqement, etc.1 3 . On-going Security 1. Identification of ALERT compromise adversaries attempting to command areas of the ..

plant, but not controllinq shutdown capability or vital areas.

4. Imminent loss of 1. Physical attack on the SITE AREA physical control of plant involving imminent EMERGENCY the plant. occupancy of the Control Room, Remote Shutdown Panel or vital areas.

5. Loss of physical 1. Physical attack on the GENEP&

control of the plant. plant has resulted in EMERGENCY unauthorized personnel occupying the Control Room or the Remote Shutdown Panel or controlling Decay Heat Removal, Reactor Water Level or Reactivity Control capability.

GRAND GULF NUCLEAlY STATION 10-s-01-1 Revision 109 Attachment I Page 2 0 of 25 EMERGENCY CLASSIFICATIOW EMERGENCY CATEGORY INITIATING COi'+TITIOM EMERGENCY ACTION LEVEL CLASSIFICATION

15. Hazards to 1 Hazards being 1. Notification of an UNUSUAL WENT Plant experienced or aircraft crash onsite Operations projected with the outside the protected potential or area dearadat ion of the level of safety of -

or the plant 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

GR4PJ-D GULF NUCLEAR STATION 10-s-01-1 Revision 109 Attachment I Page 21 of 25 EMERGENCY CLASSIPfCATIOW EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL CLASSIFICATION

15. Hazards to 2. Hazards being 1. Notification of an air- ALERT Plant experienced or craft crash onsite Operations projected with actual inside the protected (Cont.1 or Dotential area, no damage to plant substantial vital areas degradation of the level of safety of the plant

2. Notification of missile impacts on plant non-vital structures 3 . Notification of an onsite explosion affecting plant operation 41:

4. Determination that the entry of toxic or flammable gases into facility structures has threatened to render Safety Related equipment Inoperable 41:

5. Notification of a turbine failure that has resulted in casing penetration I

GRAi'JD GULF NUCLEAR STATION 10-s-01-1 Revision 109 Attachment I Page 22 of 25 EMERGENCY CLASSIFICATIONS EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY P.CTIC)N L n E L CLASSIFICATION

15. Hazards to 3. Hazards being 1. Notification of an SITE AREA Plant experienced or aircraft crash into EMERGENCY Operations projected with the plant vital areas functions needed for 01 protection of the public 2. Notification of severe Gamage to safe shutdown equipment from missiles or explosion

-or

3. Determination that the entry of toxic or flammable gases into vital areas

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE 110-s-01-1 I Revision 109 I Attachment I Page 23 of 25 EMERGENCY CLASSIFICATIOW EMERGEKCY INITIATING CONDITION EMERGENCY ACTION LEVEL CLASSIFICATION

16. Natural 1. Natural events being 1. A verified earthquake uNusu.u GVENT experienced or detected by in-plant pro] ected beyond seismic instrumentation usual levels

2. A tornado observed onsite or 3 . A hurricane warning issued that includes the site area

2. Severe natural event 1. A verified earthquake ALERT near site being detected by in-plant experienced or seismic instrumentation projected -

> OBE levels Qx 2 . A tornado causing damage to Safety Related structures

3. Sustained winds

->73 mph onsite

3. Severe natural event I. A verified earthquake SITE AREA.

near site being detected by in-plant EMERGENCY experienced or seismic instrumentation projected with plant -> SSE levels in Modes 1, 2, or 3 QK

2. Sustained winds 290 rnph onsite a . Major internal 1. Fires, earthquakes, GENERAL or etc., substantially EMERGENCY external events beyond design basis which could or have caused massive common damage to plant systems OBE - Operating arthwake SSE - Safe Shutdown Earthquake

GXAND GULF NUCLEAR STATION 10-5-01-1 Revision 109 Attachment I Page 2 4 of 25 1

EXERGEN- CLASSIFICATIOW EMERGENCY ACTION EMERGENCY CATEGORY INITIATING CONDITION CLASSIFICATION

17. Loss of 1. Significant loss of 1. Total loss of UNUSUAL EVENT assessxent, vital accident vital accident communications, assessment or assessment equipment annunciators communications such as:

equipment capability

a. All vessel level instruments IZL,

b. All containment monitoring instruments, etc.

or

2. Degraciation of the offsite communication system to only one source 2 . Loss of ALL 1. Loss of &I& ALERT annunciators annunciators on the P680, P601, and P870 panels

18. Discretionary 1. Other plant 1. Plant conditions exist UNUSUAL E3fENT conditions exist that warrant a that warrant precautionary increased awareness notification to local on the part of the and state authorities.

plant operating staff .

State and Local Authorities 2 . other plant 1. Plant conditions exist ALERT conditions that warrant warrant activation precautionary of TSC activation of the TSC and placing the EOF and key plant personnel on standby.

1 TSC - Technical SUDDO : Center EOF - Emergency @p&Eations Facility

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

EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL CLASSIFICATION

18. Discretionary 3 . Other plant conditions 1. Plant conditions exist SITE AREA exist that warrant that warrant: EMERGENCY activation o f Emergency Facilities a. The activation of the EOF or

b. A precautionary notification to the public near the site

4. Other plant 1. Plant conditions exist GENERAL conditions exist that make the release o f EMERGENCY that make release large amounts of of larue amounts of radioactivity in a short amounts of radio- period o f time likely.

activitv in a short (Not limited to the time possible following examples1 :

Core damage is predicted to occur (within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 1 and Containment pressure is z 22 psig or containment is breached

GRAND GULF NUCLEAR STATION 10-s-01-1 Revision 109 Attachment I1 Page 1 of 2 WIDELINES TO TERMINATE EMERGEZK!Y PURDOSE: To establish general guidelines to be followed should changing plant conditions warrant termination of an emergency classification.

iY!2E The Emergency Director/Offsite Emergency Coordinator must discuss existing offsite conditions with appropriated State officials prior to terminating an emergency.

I. Termination Guidelines A. General

1. Conditions which caused the event have been terminated.

2. Circumstances which have arisen from the event are under control and the results of any and all pertinent data are evaluated.

3. All probability of recurrence o f an event is removed, isolated or under control.

B. Specific Examples CATEGORY I TERMINATION GUIDELINES Fires Removal/separation of any element of fire triangle. Fire under control/not spreading.

Spill Tanks, pipes, valves, any other problem sources are empty, isolated, and out of service.

Airborne Source identified and isolated and/or containeci.

Area controlled.

Explosion Existing and potential hazards removed, destroyed and/or isolated.

Abnormal Liquid discharge is terminated, sampling is completed, Effluent and statistics verified. Public exposure to Offsite radioactive material is reduced or eliminated.

Airborne - Source identified and analysis complete.

Release is terminated and its cause is under control.

All Onsite and Offsite monitoring data is evaluated.

Public exposure to Offsite radioactive material is reduced or eliminated.

GRAND GULF NUCLEAR STATION 10-5-01-1 Revision 109 Attachment I1 Page 2 of 2 WIDELINES TO TERMIN.&TE EMERGEWa I B. Specific Examples (Cont.)

CATEGORY TERMINATION GUZDELINES Control Room Plant in normal emergency shutdown from remote Evacuation stations. Cause of evacuation identified and under control. No radiological conditions exist which cause the Control Room to become uninhabitable.

Plant Shutdown Unit is shut down by normal or emergency means.

Functions (not Unit is in cold shutdown and there is no potential available or for uncontrolled criticality.

failed)

Fuel Handling Fuel elements, segments, pellets not in a critical Accident - New configuration. Airborne activity has been evaluated or Spent Fuel and accountability of components complete.

Damage, Channeled or Unchanneled Water Loss - Source of water loss is defined. Ability to restore or LOCA Abnormal maintain water level adequate for proper cooling.

Primary Coolant Leak Earthquake or The plant has been returned to a safe condition.

Other Natural Threat of aftershock has passed and any damage Disaster has been evaluated as to risk, if any.

Security Threat Threat to site is terminated. Probability of recurrence has been removed, with the concurrence of Security Supervisor and State, Local and Federal Officials.

i