Text

Changes to Emergency Plan Implementing Procedures-December 8, 2003
	ML033430284
Person / Time
Site:	Grand Gulf
Issue date:	12/08/2003
From:	Bottemiller C; Entergy Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	-RFPFR, GNRO-2003/00073
	Download: ML033430284 (65)
	v • d • e

December 8,2003 US. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

Subject:

Changes to Emergency Plan Implementing Procedures -December 8, 2003 Grand Gulf Nuclear Station Docket No. 50-416 License No. NPF-29 GNRO-2003100073 Ladies & Gentlemen:

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

10-S-01-1 Rev. 111 10-S-01-26 Rev. 10 This letter does not contain any commitments.

Yours truly, Charles A. Bottemiller, Licensing Manager MJL attachment: 1. Procedure 10-S-01-1

2. Procedure 10-S-01-26 cc: (See Next Page)

December 8, 2003 GNRO-2003/00073 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 ATTN: Mr. Bruce Mallett (w/2) 61 1 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 I U.S. Nuclear Regulatory Commission ALL LETTERS - U.S.

ATTN: Mr. Bhalchandra Vaidya, NRR/DLPM (w/2) POSTAL SERVICE MAIL ATTN: FOR ADDRESSEE ONLY DELIVERY ADDRESS ATTN: U.S. Postal Delivery Address Only ONLY Mail Stop OWFN/7D-1 Washington, D.C. 20555-0001

PLANT OPERATIONS MANUAL Volume 10 10-s-01-1 Section 01 Revision: 111 Date; 12/1/03 BblERGENCY PLAN PROCEDURE ACTIVATXON OF THE EMERGENCY PLAN SAFETY RELATED Prepared :

Reviewed :

Concurred:

OSRC :

Approved :

List of Effective Pages:

Pages 1-12 Attachments I, I1 EPP 01-02 (Flowchart) D a t e d 3/19/03 List of TCNs Incorporated:

Revision 1-4 TCN None 5 112 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 16 103-111 None

Title:

Activation of the No.: 10-S-01-1 Revision: 111 Safety Emerqency Plan Evaluation I. OVERVIEW I SIGNATURES DescriPtion of Proposed Change SEE CURRENT REVISION STATEMENT If the proposed activity, in its entirety, involves any one of the criteria below, check the appropriate box, provide a justificationlbasis 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.

0 The proposed activity is editorialltypographicalas defined in Section 5.2.2.1.

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

(Insert item ##fromSection 5.2.2.2).

1 d SCREENING Sections I, II, 111, and IV required 50.59 EVALUATION EXEMPTION Sections I, II, Ill, IV, and V required OSRC h e Chairmans Signature I Date

[Required only for Programmatic Exclusion Screenings (see Section 5.9) and 50.59 Evaluations.]

List of AssistinglContributing Personnel:

Name: Scope of Assistance:

/r//

J:ADM_.SRVS/TECH~PWB/REVISION/lO/~OSOll~DOC

Title:

Activation of the NO.: 10-5-01-1 Revision: 111 Safety Emerqency Plan Evaluation

11. SCREENING A. Licensing Basis Document Review

1. Does the proposed activity impact the facility or a procedure as described in any of the following Licensing Basis Documents?

Operating License YES NO CHANGE #and/or SECTIONS TO BE REVISED Operating License CI -

TS a NRC Orders cl If YES, obtain NRC approval prior to Implementing the change by lnltiating an LED change in accordance with NMM LI-113 (reference 2.2.13). (SeeSection 5.1.13 for exceptions.)

LBDs controlled under 50.59 1 YES I NOA CHANGE #and/or SECTIONS TO BE REYISED 1 FSAR a d TS Bases II1 Technical RequirementsManual a d, Core Operating Limits Report 0 1 cl 7 NRC Safetv Evaluation Reoorts cl If YES, perform an ExemptionrReviewper Section V OR perform a 50.59 Evaluation per Section Vl lnftlate an LBD change in accordance with NMM LI-I13 (Reference2.2.13).

LBDs controlled under other YES NO CHANGE # andlor SECTIONS TO BE REYISEL) regulaiions Quality Assurance Program Manualz 13 Emergency Plan D Fire Protection Program 0 (includes the Fire Hazards Analysis) A Offsite Dose Calculation Manual3 ( O I c d J If YES, evaluate and changes in accordance with the appropriate regulation &Q initiate an LBD change in accordance with NMM LI-I13 [Reference 2.2.131.

2. Does the proposed activity involve a test or experiment not described in the FSAR?

If yes, perform an Exemption Review per Section V perform a 50.59 Evaluation per Section VI.

3. Does the proposed activity potentially impact equipment, procedures, or facilities utilized for storing spent fuel at an Independent Spent Fuel Storage Installation?

(Check N1A if dry fuel storage is not applicable to the facility.) NfA If yes,, perform a 72.48 Review in accordance with NMM Procedure Ll-I 12.

(See Sections 1.5 and 5.3.1.5 of the EOI 10CFR50.59 Review Program Goidetlnes.)

If YES, see Section 5.1.4. No LBD change is required.

If YES, notify the responsibledepartment and ensure a 50.54 Evaluation is performed. Attach the 50.54 Evaluation.

If YES, evaluate the change In accordance with the requirements of the facilitys Operating License Condition.

Title:

Activation of the No.: 10-S-01-1 Revision: 111 Safety Emerqency Plan Evaluation

0. Basis Provide a clear, concise basis for the answers given in the applicable sections above. Explain why the proposed activity does or does not impact the Operating License/Technical Specifications and/or the FSAR and why the proposed activity does or does not involve a new test or experiment not previously described in the FSAR. Adequate basis must be provided within the Screening such t h a t a third-party reviewer can reach the same conclusions. Simply stating that the change does not affect TS or the FSAR is not an acceptable basis. See EOI 50.59 Guidelines Section 5 . 6 . 6 for guidance.)

Chanae adds definitions of existinu terms used in EAL identification to enhance consistant internretation and amlication. Chancle does not alter intent or Derformance uuidance. but imwoves the standardization of r>erformance.

Performed keyword searches of the ontine OL, TS, NRC Orders, FSAR. TS Bases. TRM. COLR, ODCM. SERs. QAPM. Emergencv Plan. and fire Protection Proaram for the key words t>ower block and decay heat. Reviewed all hits returned, no conflicts were identified.

No definitions of Dower block were identified in any of the LBDs.

No definitions of decay heat removal were identified in any of the LBDs.

C. References Discuss the methodology for performing the LBD search. State the location of relevant licensing document informationand explain the scope of the review such as electronic search criteria used (e.g., key words) or the general extent of manual searches per Section 5.3.6.4 of LI-101. NOTE. Ensure that electronic and manual searches are performed using controlled copies of documents. If you have any questions, contact your site Licensing department.

LBDslDocuments reviewed via keyword search: Keywords:

OL, TS. NRC Orders, FSAR, TS Bases, TRM, Power block, decay heat COLR, ODCM. SERs, QAPM. Emernencv Plan, and Fire Protection Proaram LBDslDocuments reviewed manually:

D. Is the validity of this Review dependent on any other change? (See Section 5.3.4of the EOI 10CFR50.59 Program Review Guidefines)

If Y e s , list t h e required changes.

Title:

Activation of the No.: 10-5-01-1 Revision: 111 Safety Ernerqency Plan Evaluation 111. ENVtRONMENTAL SCREENlNG If any of the following questions is answered yes, an Environmental Review must be performed in accordance with NMM Procedure EV-115, Environmental Evaluations, and attached to this 50.59 Review. Consider both routine and non-routine (emergency) discharges when answering these questions.

Will the proposed Change being evaluated:

Yes No

-7

1. a @ Involve a land disturbance of previously disturbed land areas in excess of one acre (i.e.,

grading activities, construction of buildings, excavations, reforestation, creation or removal of ponds)?

2. 0 d Involve a land disturbance of undisturbed land areas (i.e., grading activities, construction, excavations, reforestation, creating, or removing ponds)?

3. cl d Involve dredging activities in a lake, river, pond, or stream?

4. 0 /Increase the amount of thermal heat being discharged to the river or lake?

5. 0 rd Increase the concentration or quantity of chemicals being discharged to the river, lake, or air?

6. d Discharge any chemicals new or different from that previously discharged?

7. cl d Change the design or operation of the intake or discharge structures?

8. 0 cz( Modify the design or operation of the cooling tower that will change water or air flow characteristics?

9. cl d Modify the design or operation of the plant that will change the path of an existing water discharge or that will result in a new water discharge?

10. cl d Modify existing stationary fuel burning equipment @e.,diesel fuel oil, butane, gasoline, propane, and kerosene)?f

11. 0 d l n v o l v e the instaltation of stationary fuel burning equipment or use of portable fuel burning equipment (i.e., diesel fuel oil, butane, gasoline, propane, and kerosene)?

12. cl d Involve the installation or use of equipment that will result in an air emission discharge?

13. c] d Involvethe installation or modification of a stationary or mobile tank?

14. 0 Involve the use or storage of oils or chemicals that could be directly released into the environment?

15. a Involve burial or placement of any solid wastes in the site area that may affect runoff, surface water, or groundwater?

See NMM Procedure EV-I 17, Ail Emissions Management Program,for guidance in answering this question.

Title:

Activation of the No.: 10-S-01-1 Revision: 111 Safety Ernexqency Plan Evaluation

~~ ~ ~~~

IV. SECURITY PLAN SCREENING If any of the following questions is answered yes, a Security Plan review must be performed by the Security Department to determine actual Impact to the Plan and the need for a change to the Plan.

A. Could the proposed activity being evaluated:

1. Add, delete, modify, or otherwise affect Security department responsibitities (e.g., including fire brigade, fire watch, and confined space rescue operations)?

2. d Result in a breach to any security barrier(s) (e.g., HVAC ductwork, fences, doors, walls, ceilings, floors, penetrations, and ballistic barriers)?

3. d Cause materials or equipment to be placed or installed within the Security Isolation Zone?

4. 6 Affect security lighting by adding or deleting lights, structures, buildings, or temporary facilities?

5. Ed Modify or otherwise affect the intrusion detection systems (e.g., E-fields, microwave, fiber optics)?

6.

7. 5 Modify or otherwise affect the operation or field of view of the security cameras?

Modify or otherwise affect (block, move, or alter) installed access control equipment, intrusion detection equipment, or other security equipment?

8. d Modify or otherwise affect primary or secondary power supplies to access control equipment, intrusion detection equipment, other security equipment, or to the Central Alarm Station or the Secondary Alarm Station?

9. d Modify or otherwise affect the facilitys security-related signage or land vehicle barriers, including access roadways?

10. d Modify or otherwise affect the facilitys telephone or security radio systems?

The Security Department answers the following questions if one of the questions was answered yes.

8. Is the Security Plan actually impacted by the Yes proposed activity? El No C. Is a change to the Security Plan required? Yes Change # (optional)

Q No DULL. l.4- 0 I 4 /L3 /a Ian reviewer (print) I Signature i Date

Title:

Activation of the No.: 10-S-01-1 Revision: 111 Page: i Emerqency Plan RPTS FORM 10CFR50.59 Review Required? [ (XI Yes I If Yes, attach 50.59 Review Form I ( ) No INot required per LI-101 Department Cross-Discipline Review6 Needed I

Requirement Implemented by Directive Directive Paragraph Number Name Paraqraph Number That Implements Requirement ANSI N18.7 5.3.9.2.s1

GGNS Emer Plan 2.4.53 1.1.1 GGNS Emer Plan 3.3.Sl 2.1.2 GGNS Emer Plan I 6.2.2.53 & S4 2.1.1, 6.1.2 52 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 6.2.2.51 & 52 6.1.2 (Note)

GGNS Emer Plan 4.1.4 .s3 Attachment I GGNS Emer Plan 4.1.53 6.1.4, 6.3 GGNS Emer Plan 4.1.Sl3 6.1.3 (Note)

GGNS Emer Plan 3.3 .S6.b 6.1.3 GGNS Emer Plan 6.2.4.511 & 512 6.1.4.1 (11 GGNS Emew Plan 6.2.4.Sl3 6.1.4.1 (2)

GGNS Emer Plan 6.2.4.514 6.1.4.J(3)

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

GGNS Emer Plan 6.3.1.51 6r S2 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 9.3.57 Attachment II (Note)

GGNS Emer Plan Table 4-1 Attachment I GGNS Emer Plan 7.5.3.a.2.e 5.30 GNFtI-93/00171 93-13-01, Item 6 Attachment I, 17.1.1 GGNS Emer Plan 6.5.1.b.55, S6 6.1.4 . k f l )

GGNS Emer Plan 7.5.3.a.3.c 6.1.4.e GGNS Emer Plan 6.2.4.52 2.1.2 GGNS Emer Plan 6.2.4.57 & S 8 2.4 GGNS Emer Plan 5.4. S 6 6.1.4.j(11,j (21,j (3)

GGNS Emer Plan 3.3.s3 & s4 2.4 GGNS Emer Plan 6.5.l.b 6.1.4 GGNS Emer Plan 6.5.1.A.1 6.1.4.h GGNS Emer Plan 3.3.s5 2.1.2 GGNS Emer Plan 6.1.2 6.1.4.d (Note), g (Note), 6.1

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

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE

[Title: Activation of the I NO.: 10-5-01-1 I Revision: 111 1 Page: ii t I

I NOTE

__I_

The Component Database Change Request statement is applicable only to Volume 06 and 07 maintenance directives.

Component Database Change Request generated and t backup documentation available for setpoint and/or calibration data only fl Yes e N / A CDBCR #

Current Revision Statement Revision 111:

Adds the definition of "Power Block" to the procedure for consistent interpretation. The definition used in this procedure is consistent with Operations and Security.

Adds the definition of "Decay Heat Removal" to the procedure for consistent interpretation.

- Entegy NUCLEAR MANAGfiMENT MANUAL I QUALITYRELATED lNFORMATlON USE EP-305 Page g REV. NO. 0 of fi ATTACHMENT9.1 IOCfR50.54(~)SCREENING

1. DOCUMENT INFOFtlS!IATION Procedure/Document Number: 10-S-01-01 I Proc./Doc.

I

- . Revision:

-- __ 1 1- 1_ I Document

Title:

Activation of the Emergency Plan Brief Description of Proposed Revision: Adds the definition of" Power Block" and Decay Heat removal"' to the procedure for clarification and consistent interwetation. 1

2. SCmENING A,) Does the proposed revision require a change to the Emergency Plan, change a commitment in the E-Plan, or potentially decrease the effectiveness of the E-Plan?

- Yes X No B.) Does the proposed revision change the Emergency Action Levels (EALs)?

-Yes X No If the answer to either question is YES, then a 10CFR50.54(q) evaluation must be performed. See attachment 9.2. If the answer is NO provide justification below.

1 Reviewed the ap~licableDortions ofthe Emergency Plan, This change is administrative in nature. This revision does not change or affect the E-Plan and therefore does not decrease the effectiveness of the Emergency Plan.

4. APPROVAL Screening Prepared By:

Signature Date Screening Reviewed By: Is/L1/02 Signiture Date Screening Approved By: m& Signature 4gA.3 Date

Title:

Activation of the No.: 10-5-01-1 Revision: 111 Page: 1 TABLE OF CONTENTS Page 1.0 PURPOSE AND DISCUSSION 2 2.0 RESPONSIBILITIES

3.0 REFERENCES

4.0 ATTACHMENTS 5.0 DEFINITIONS 6.0 DETAILS 6.1 Activation of Emergency Plan 6.2 Supplemental Actions '10 6.3 Upgrading Emergency Classifications 11 6.4 Terminating Emergency 11 6.5 Records and Reports 12 6.6 EP form EPP 01-02 (Flow Chart) Revision Process 12

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE

Title:

Activation of the No.: 10-S-01-1 Revision: 111 Page: 2 Emergency Plan 1.0 PURPOSE AND DISCUSSION 1.1 Purpose 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 terminate 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.

1.2.2 Emergency Plan section 6.1.2 allows suspension of normal Emergency Plan actions for Security Emergencies. This is permitted because of the potential risk to personnel safety which a security emergency may present. An armed attack against the plant is a unique security emergency that is expected to be an extremely fast moving event and present an immediate and serious threat to human life. Section 6.1.5 of this procedure contains special Emergency Plan actions for this unique event.

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.

Title:

Activation of the No.: 10-5-01-1 Revision: 111 Page: 3 Emerqency Plan 2.2 Operations Coordinator - Reports directly to the Emergency Director and is responsible for:

2.2.1 Coordinating all activities in the Control Room.

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

2.4 On-Call Manager - Is responsible for:

2.4.1 Reporting to the site to assume 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

I 3.1 NRC Memorandum dated July 11, 1994 concerning Branch Position on Acceptable Deviations to Appendix 1 to NfJREG-O654/FEMA-REP-l.

3.2 GGNS Emergency Plan 4.0 ATTACHMENTS 4.1 Attachment I - Emergency Classifications 4.2 Attachment II - 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 Action - Actions taken during or after an accident to obtain and process information necessary to make decisions to implement specific emergency measures.

5.3 -

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

5.5 Decay Heat Removal - As long as plant parameters can be controlled within the limits of 05-S-01-EP-2,adequate core cooling and control of decay heat removal exists. Loss of the SSW Basins (Ultimate Heat Sink) capability to remove heat does not by itself cause loss of control of decay heat removal.

Title:

Activation of the No.: 10-S-01-1 Revision: 111 Page: 4 Emergency Plan 5.6 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, f o u r sectors are used until the three sector criteria can be identified.

5.7 Emerqency - A sudden, urgent, usually unforeseen occurrence o r 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.

5.8 Emergency Action Levels (EALs) - 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.

5.9 Emergency Classification - Emergency conditions (four classes) covering the entire spectrum o f possible situations from minor, local incidents to hypothetical, major radiological emergencies. The four classes are listed in increasing order of severity: Unusual Event, Alert, Site Area Emerqency and General Emergency.

5.10 Emergency 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 5.11 Emergency Operations Facility (EOFJ - A near-site emergency center from which the offsite emergency support activities are controlled 5.12 Emerqency Planning Zone (EPZ) - Areas designated for which planning is provided to assure that prompt and effective action is initiated to protect the public in the event of an emergency 5.13 EPP - Emergency Plan Procedure 5.14 ERDS - 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.

5.15 ESC -- Energy Services Center 5.16 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 5.17 General Emerqency - 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.

5.18 LOCA - Loss of Coolant Accident 5.19 OEC-- Offsite Emergency coordinator 5 - 2 0 Offsite - For accountability purposes, any area outside the GGNS protected area 5.21 OMT-- Offsite Monitoring Team

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE I

Title:

Activation of the ]No.: 10-S-01-1 IRevision: 111 I Page: 5 1 I Emerqency Plan I I I i 5.22 Onsite - For accountability purposes, the area within the GGNS protected area 5.23 Operations Support Center (OSC) - Location from which onsite non-Control Room activities are staged and implemented 5.24 PA - Public Address System 5.25 pAc: - Protective Action Guide 5.26 pAR - Protective Action Recommendation 5.27 Power Block - The power block consists of the following areas; Unit I & I1 Turbine Building, Unit I 11 Auxiliary Building, Control Building, Radwaste Building, Water Treatment Building, Circulating Water Pump House, Diesel Generator Rooms and Standby Service Water Basins.

5.28 SAS - secondary Alarm Station 5.29 Site Area Emergency - 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.

5.30 Site Security Code Yellow - Armed adversary attempting to or has entered company property .

5.31 Site Security Code Oranqe - Armed adversary attempting to or has crossed the Protected Area fence.

5.32 Site Security Code Red - Armed adversary has entered any power block building or vital area.

5.33 =Standby Service Water 5.34 TEDE (Total Effective Dose Equivalent) - Sum of the EDE and CEDE to nonpregnant adults from exposure and intake during an emergency situation.

5.35 - Thermo Luminescent Dosimeter 5 . 3 6 E - Technical Support Center 5.37Unusual 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 requiring 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 NUREG-0654; the two expressions are used interchangeably in the E-Plan and related procedures as appropriate.)

5.38 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.

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE I

Title:

Activation of the I No.: 10-S-01-1 I Revision: 111 I Page: 6 6.0 DETAILS 6.1 Activation of Emergency Plan 6.1.1 Any person having knowledge of abnormal plant conditions should notify the Shift Supervisor/Manager.

6.1.2 The Shift Supervisor/Manager, when notified of abnormal plant conditions, should refer to Attachment I or EPP 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.

NOTE 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 EAL 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.

1 6.1.4 Once an emergency classification is declared, the following actions are taken by the Shift Manager/Emergency Director:

NOTE After becoming aware that an emergency condition exists, the Shift ManagerlEmergency Director's first priorities are :

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

- Take actions to ensure safe operation of plant.

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

Operations.

a. In the event of Site Security Code Yellow, Orange or Red, go to section 6.1.5 and do not return to this section until the event is over.

b. Initiate Emergency Director's Checklist (EPP Form 01-11.

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE i

Title:

Activation of the I No.: 10-S-01-1 I Revision: 111 I Page: 7 I I Emergency Plan I t I I 6.1.4 (Cont. I

c. Announce to Control Room personnel that you are the Emergency Director.

NOTE

_ 111_

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.

d. Designate an individual a s communicator to perform the initial notification in accordance with 10-5-01-6. 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 and 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.

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

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

g. 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.

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

(2) Over Site Paging (#7929),

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

Title:

Activation o f the No.: 10-5-01-1 Revision: 111 Page: 8 Emerqency Plan 6.1.4 (Cont. I

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

j. Activate emergency facilities as follows:

(1) If Unusual Event has been declared, no activation of facilities is required unless the Emergency Director feels there 3s a reasonable possibility of escalation of emergency to a higher classification.

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

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

k. 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 recommended to State and Local Agencies upon declaration of a G e n e r a l Emergency as follows:

Condition ProtectiveAction Recommendation EVACUATE: 2 Miles All Sectors General Emergency -

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

General Emergency EVACUATE: 2 Miles All Sectors Declared and EVACUATE: 10 Miles in Downwind Sectors Dose Projection or Field Measurement at 2 5 miles corresponds to SHELTER Remainder of I 0 Mile Emergency IRernTEDE Planning Zone (EPZ)

Or 5 Rem ThyroidCDE

Title:

Activation of the No.: 10-S-01-1 Revision: 111 Page: 9 6.1.4 (Cont- 1

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

6.1.5 Activation of the Emergency Plan during an armed attack against the plant.

CAUTION The following guidance is only to be used for events involving an I

armed attack against the plant. Do not use these instruction6 for any other event.

I I CAUTION An armed attack against the plant is a unique security emergency that is expected to be an extremely fast moving event and presents an immediate and serious threat to human life. It is imperative for personnel to take cover immediately to minimize loss of life.

Normal activation of the Emergency Plan is inappropriate for this event.

a'. Initiate Emergency Director's Checklist (EPP Form 01-01) (CR) or EPP Form 30-01 (TSC)).

b . Announce to the Control Room that you are the Emergency Director.

C. Make an announcement over the Plant PA System and over Site Paging phone # 7929 to the affect that there is a Site Security Code (Yellow/Orange/Red) in affect and all personnel are to take cover immediately until further notice.

d. Take actions as directed by 05-1-02-VI-4,Security Threat ONEP.

e . Do not announce the classification of the event over the Plant PA System.

f . Do not activate any on site or off site Emergency Response Facilities. (OSC, TSC, EOF, ENMC, EIC)

9. Do not activate the VIP-2000.

h. Do not order a site evacuation.

i. Designate an individual as communicator to perform notification in accordance with 10-5-01-6, if available.

j . If the event lasts more than 15 minutes, strongly consider manning the backup EOF (Baxter Wilson) with offsite personnel only using ERO Call Tree.

k. When notified that the security threat is over, return to step 6.1.4.b.

Title:

Activation of the NO.: 10-S-01-1 Revision: 111 Page: 10 Emerqency Plan 6.2 Supplemental Actions 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:

(I) 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.

(41 Determination o f 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 reconstruction1 .

Title:

Activation of the No.: 10-S-01-1 Revision: 111 Page: 11 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 environmental surveys

c. Protective action recommendations to offsite agencies

d. Classification of the emergency 6.2.7 If extended emergency operations are necessary, the Emergency Directorloffsite Emergency Coordinator should authorize preparation of an emergency organization shift schedule to support 24-hour emergency operation.

6.3 Upqradinq Emerqency 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 . g .

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

d. Initiate plant operating procedures and emergency plan procedures as required.

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

f. Determine offsite doses in accordance with Step 6.1.4k.

9. conduct additional assessment actions as necessary in accordance with Step 6.2.

6.4 Terminating Emerqency 6.4.1 Terminatinq If EALs are no longer met or exceeded, the Emergency Directorloffsite Emergency Coordinator refers to Attachment I1 to determine whether or not to terminate emergency.

6.4.2 Reentry 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-01-22to determine if reentry and recovery actions may be initiated. If the reentrylrecovery criteria are met, the Emergency Director may advise the Offsite Emergency Coordinator that reentrylrecovery may start.

Title:

Activation of the NO.: 10-S-01-1 Revision: 111 Page: 12 Emergency Plan 6.5 Records and Reports 6.5.1 The Manager, Emergency Preparedness is responsible f o r 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 f o r reviewing all changes to Attachment I, Emergency Classifications, for Impact on EPP 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 EPP 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 11)

Simulator (1)

TSC (21 EOF (2)

Back up TSC 11)

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 10-5-01-1,Activation of the Emergency Plan.

b. Once procedure revision for 10-5-01-1, 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.

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE 10-s-01-1 Revision 111 Attachment I Page 1 of 25 W R G E N C Y CLASSIFICATIONS TABLE OF CONTENTS CATEGORY -

PAGE

1. Safety System Functions 2,3

2. Abnormal Primary Leak RatelLow 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 Ih-plant RadiationlAirborne Contamination Levels 17

13. Fuel Handling Accident 17, i a

14. Security Threat 19

15. Hazards to Plant Operations 20,21,22

16. Natural Events 23

17. Loss of Assessment, Communication, Annunciator Equipment 24

18. Discretionary 24,25 NOTE Any changes made to information in Attachment I may require changes to EPP 01-02 (Flowchart),

GRAND GULF NUCLEAR STATION 10-s-01-1 ~evision111 Attachment I Page 2 of 25 EMERGENCY CLASSIFICATIONS EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL !LASSIFICATION

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

L. Safety/relief Valves 3.4.4 or c

2. ECCS - Operating 3.5.1 Of

3. Primary Containment 3.6.1.1 or

4. Primary Containment Airlocks 3.6.1.2 or c

5. Primary containment Isolation Valves 3.6.1.3 or

_ I

6. Low Low Set Valves 3.6.1.6 or I

7. Residual Heat Removal Containment Spray 3.6.1.7 or

8. Suppression Pool Average Temperature 3.6.2.1

-or

9. suppression Pool Level 3.6.2.2 (Continued)

GRANLl GULF NUCLEAR STATION 10-5-01-1 Revision 111 Attachment I Page 3 of 25 EMERGENCY CLASSIFICATIONS EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL ZLASSIFICATION L. Safety 1. Inability to reach or

- N S U A L EVENT System required shutdown Functions within Technical lo. Suppression Pool (Cont.1 Specification time Makeup System 3.6.2.4 limits (Cont.)

or

11. Second 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 Or

14. Drywell 3.6.5.1 Or

15. Drywell Airlocks 3.6.5.2 or

16. Drywell 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 10-5-01-1 Revision 111 Attachment I Page 4 of 25 EMERGENCY CLASSIFICATIONS 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 or

2. > 30 gpm total leakage Averages over previous 2 4 hr period

2. Coolant leak rate 1. TQtal leakage ALERT

> 5 0 gprn calculated to be

> 5 0 gpm while in Plant Mode 1, 2 or 3 3 . Known loss of 1. RPV water level SITE AREA coolant greater than c -167 inch EMERGENCY makeup pump c a p a c i t y 2 . Makeup capacity unable to increase reactor water level

GRAND GULF NUCLEAR STATION 1o-s-01-1 Revision 111 Attachment I Page 5 of 25 EMERGENCY CLASSIFICATIONS EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LETEL :LASSIFICATION I . Core Fuel 1. Fuel damage UNUSUAL EVENT Damage indication

1. Increase of 2 8 5 mR/hr in 30 minutes on OFFGAS pretreatment monitor OK

2. OFFGAS pretreatment monitor reading > 1,400 mR/Hr 3 . Laboratory analysis of coolant sample indicates > 0.2 pCi/ml dose equivalent 1-131 f o r more than 4 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

4. Laboratory analysis of coolant sample I

indicates 4.0 pCi/ml dose equivalent 1-131

2. Severe loss of fuel AZERT cladding

1. OffGAS pretreatment 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 i - Micro Cui 38

GRAND GULF NUCLEAR STATION 10-s-01-1 Revision 111 Attachment I Page 6 of 25 EMERGENCY CLASSIFICATIONS EMERGENCY INITIATING CONDITION EMERGENCY ACTION LEVEL :LASS IF I:CATION

3. Degraded core with 1 . RPV water level SITE AREA possible loss of c -167" or cannot EMERGENCY coolant be determined

2. a. H i g h coolant activity indicated by analysis of sample > 300 fiCi/ml dose equivalent; 2-131 ar

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

pci - micro Curies

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE 10-s-01-1 Revision 111 Attachment I Page 7 of 2 5 EMERGENCY CLASSIFICATIONS EMERGENCY INITIATING CONDITION EMERGENCY ACTION LEVEL !LASSIFICATION

b. LOSS of 2 of 3 L. Loss of any two of the GENERAL 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 Loss

a. Coolant sample analysis indicates >300 pCi/ml dose equivalent 1-131 or

b. >lo00 R / H r in Drywell Potential Loss

a. RPV water level cannot be restored and maintained 5 -167 in.

or

b. RPV pressure cannot be restored and maintained

> 57 psig when in RPV flooding.

or x

c. >lo0 R/Hr in Drywell Reactor Pressure Boundary

-Loss

a. Drywell pressure ~1.23 p i g and indication of a steam leak in the drywell or

b. Main steam line not isolated or

c. RCIC steam line break outside containment with inability to isolate Potential Loss

a. Total reactor coolant leakage calculated to be 250 gpm or

b. >10 R / h r iTContainment

GRAND GULF NUCLEAR STATION 10-5-01-1 Revision 111 Attachment I Page 8 of 25 m R G E N C H CLASSIFICATIONS EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL CLASSIFICATION

3. Core Fuel 4. Loss of 2 of 3 Primary Containment GENERAL Damage Fission product LOSS

__c EMERGENCY (Cont.) Barriers with a a. Primary Containment Potential l o s s of 3rd pressure >56 psig barrier. (Cont,) or

b. Loss orability to isolate Drywell or primary containment Leakage into Areas Outside the Primary Containment Potential Loss a . Primary containment pressure >22 psig ox

b. Operation in the Unsafe Region of HCTL ~ 1PSP :

Curve.

OX

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

4. steam Leaks 1. Main steam line break 1. Isolation initiated and ALERT outside the abnormal leakage down containment with stxeam of MSIVs significant MSIV ( > 10 gpm o r 5000 lbrn/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.

and 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. -

and RCIC steam line fails to isolate MSIV - Main Stea Isolation valve PSP - Pressure suppression limit RCIC - Reactor Core Isolation Cooling HCTL - Heat Capacity Temperature Limit HDOL - Hydrogen Deflagration Overpressure Limit

GRAND GULF NUCLEAR STATION 10-5-01-1 Revision 111 Attachment I Page 9 of 25 gMgRGE53CY CLASSIFICATIONS EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL CLASSIFICATION

5. Abnormal 1. Radiological effluent I. Entering the action UNUSUAL EVENT 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)

LCO - Limited mdition f o r Operation SGTS - Standby Gas Treatment System TRM - Technical Requirements Manual

GRAND GULF NUCLEAR STATION 10-5-01-1 Revision 111 Attachment I Page 10 of 25 EMERGENCY CLASSIFICATIONS EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL lLASSIF1CATION

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

exposure of:

a. 0.5 Ci/sec Noble

a. 2 5 0 mR/Hr (for Gas for 30 minutes 30 minutes Whole Body or or

b. 6.0 E-4 Cilsec

b. 1 5 0 0 mR/Hr (for Iodine for 30 minutes 2 minutes) Whole or Body or

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

c. 2 250 m/hr ( f o r 30 min) to the Thyroid.

or

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

or Ii Adverse 2 . Radiation monitoring Meteorology I teams report radiation

-Stability Class F, and/or Iodine wind speed 1 mlsec, concentration readings site boundary X f Q at the site boundary 1080 E-6 sec/m3 corresponding to:

(FSAR Table 15 a. 50 mR/Hr 6-12) for 30 minutes or

b. 500 mR/Hr for 2 minutes or C. 6.OE-6 pCi/cc Iodine or 3 . Containmenipost Accident Radiation Monitor:

a. >330 R/HR for 30 minutes Or

b. >3300 WHR for 2 minutes SAR - Final I fety Analysis Report pCi - micro Curies Ci - Curies

G W GULF NUCLEAR STATION 10-s-01-1 Revision 111 Attachment I Page 11 of 25 EHBRGEXCY CLASSIFICATIONS EMERGENCY INITIATING CONDITION EMERGENCY ACTION LEVEL 'LASS IFICATION

5. Abnormal &.Effluent monitor(8) 1. Effluent monitor(s1 GENERAL Effluent , (UNDER ACTUAL METEORO- (UNDER ACTUAL METEORO- EMERGENCY I .

(Cent )

LOGICAL CONDITIONS) d e t e c t levels corresponding to site boundary exposure of:

LOGICAL CONDITIONS) confirms release rates corresponding to site 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

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

a. 1000 mRem TEDE or

b. 1.2E-5 pCi/cc Iodine

6. Abnormal 1.Radiological Effluent 1. Entering the action WNUSUAL E n N T Effluent, Release Rate exceeds statement of TRM Spec LIQUID TRM Spec limit 6.11.1, in the Radioactive Liquid Effluent section of TRM Spec 2.RadiologicaL Effluent 1. Liquid release > 10 ALERT s10 times TRM Spec times the limit of TRM limit Spec 6.11.1 in the Radioactive Liquid Effluent section of L

TRM Spec TEDE - Total E: eetive Dose Equivalent CDE - Committet Dose Equivalent TRM - Technical Requirements Manual

GRAND GULF NUCLEAR STATION 10-s-01-1 Revision 111 Attachment I Page 12 of 25 EMERGENCY CLASSIFICATIONS EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL !LASSIFICATION 7, Major 1. Total loss of offsite t. LOSS of offsite power WNUSUAL EVENT Electrical power to :

Failures (AC) -

or a. 15AA Loss of onsite AC power capability and

b. 16AB

c. 17AC or

2. LOSS of ALL t h r e e divisional diesel generators while in Plant Operational Condition 1, 2 or 3

2. Total loss of o f f s i t e 1. Loss of offsite power ALERT power to :

and a. 15AA LOSS of onsite and power 5 15 minutes

b. 16AB and

c. 17AC

-and 2 . LOSS of three divisional d i e s e l generators and

3. 515 minutes

GRAND GULF NUCLEAR STATION 10-5-01-1 Revision 111 Attachment I Page 13 of 25 BMERGENCY CLASSIFICATIONS EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL 3LASSIFICATION 7 . Major 3. Total l o s s of offsite 1. Loss of offsite power SITE AREA Electrical power to : EMERGENCY Failures (AC)

(Cont.1 and a. 15AA Loss of A1;L onsite and power >15 minutes

b. 16AB and

c. 17AC and

_I__

2. Loss of three divisional diesel generators and

_ I_

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 f o r Failures minutes S15 minutes)

2. Loss of onsite ESF 1. Loss of Division 1, 2 SITE AREA DC power for > 15 and 3 (125 V d c o r EMERGENCY minutes >I5 MINUTES)

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE 10-s-01-1 Revision 111 Attachment I Page 14 of 25 EMERGENCY CLASSIFICATIONS EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL CLASSIFICATION

9. Control 1. Evacuation of the 2 . Control Room evacuated AL.ERT Room Control Room Evacuation and and 2 . Control of shutdown Control established systems established at the xemote 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

10. Fire 1. Fire lasting > 10 1. A fire within the power minutes after block, fire water pump discovery house or COz skid lasting >lo minutes from the time of notification

2. Fire potentially 1. A fire defeating ONE affects safety safety system electrical systems division 3 . Fire compromising the 1. A fire defeating SITE AREA functions of ESF THAN ONE safety system EMERGENCY Systems electrical division

GRAND GULF NUCLEAR STATION 10-s-01-1 Revision 111 Attachment I Page 15 of 25 EbfBRGEWCY CLASSIFICATIONS EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL 'LASS IFICATION

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

-and

1. The determination that there are no longer enough systems functional to attain or maintain the reactor coolant c200°F

2. Failure o f 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 or more than one rod and 2b. SRM's are either upscale or countrate is increasing (Assuming SRMs are full in) and

3. Reactor power < 4 % on APRM (APRM Downscale light on)

APRM - Average ?ower Range Monitor

GRAND GULF NUCLEAR STATION 10-5-01-1 Revision 111 Attachment I Page 16 of 2 5 EMERGENCY CLASSIFICATIONS EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL CLASSIFICATION

11. Plant 3. Complete loss of 1. HPCS and RCIC not SITE AREA Shutdown functions needed for functional EMERGENCY and

2. Not able to depressurize with SRVs

3. Main Condenser is not avai 1ab 1e

4. Transient requiring 1. scram conditions operation of shutdown confirmed systems with failure to scram and continued power generation and

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

3. Reactor power 24% on APRM

GRAND GULF NUCLEAR STATION 10 - s 1 Revision 111 Attachment I Page 17 o f 2 5 EMERGENCY CLASSIFICATIONS EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL :LASSIFICATION 12.Abnormal 1. Radiation levels or L. Verification of area ALERT In-plant airborne radiation monitor Radiation/ contamination indicate reading > 1000 times Airborne a severe degradation setpoint Contam- in the control of ination radioactive materials Levels Verification of CAM reading >lo00 times setpoint

13. Fuel 1. Fuel. damage accident 1. Notification o f a spent ALERT Handling with release of fuel damaging accident Ac cideat radioactivity to Containment or Auxiliary Building and

2. High high radiation alarms on either

a. Fuel handling vent exhaust

b. Containment vent exhaust 2 . Major damage to spent 1.a. Notification of a SITE m E A fuel assembly in spent fuel damaging EMERGENCY Containment or accident Auxiliary Building or

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

and (Continued1 d r Monitor

GRAND GULF NUCLEAR STATION 10-5-01-1 Revision 111 Attachment I Page 18 of 25 t

EMERGENCY CLASSIFICATIONS EMERGENCY CATEGORY INITSATING CONDITION EMERGENCY ACTION LEVEL ILASSI F ICATION 2 . Major damage to spent

13. Fuel fuel assembly in - 2. Any post accident SITE AREA Handling Containment or effluent radiation EMERGENCY Ac cident Auxiliary Building monitor confirms Noble (Cont.1 (Cont . I Gas, Iodine release rates corresponding to :

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

_ I

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

c. 5.0 Ci/sec Noble Gas

( 2 minutes) or

d. 6.0 E - 3 Ci/sec Iodine

( 2 minutes) 3 . Radiation monitoring teams r e p o r t Radiation and/or Iodine concentration readings at t h e site boundary corresponding to:

a. 50 mR/Hr (for 30 minutes) 02

b. 500 mR/Hr ( f o r 2 minutes)

-or

c. 6.0 E-6 pCi/cc Iodine Ci - Curies FCi - Micro Curies

GRAND GULF NUCLEAR STATION 10-5-01-1 Revision 111 Attachment I Page 19 of 25 EMERGENCY CLASSIFICATIONS EMERGENCY INITIATING CONDITION EMERGENCY ACTION LEVEL CLASSIFICATION L. A credible site - 1. The Shift Manaqer u"JSUAL EVENT specific security deterrnines 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 Management, Site Security, etc.1 Example: A report from Site Security of an unauthorized attempted PA entry should be considered a credible threat.

2. Attempted Entry 2. Site Security Code Yellow (Armed adversary attempting to or has entered company property. 1 3 . On-going Security 1. Site security Code ALERT compromise Orange (Armed adversary attempting to or has crossed Protected Area fence. f

4. Imminent loss of 1. Site Security Code Red SITE AREA physical control of (Armed adversary has EMERGENCY the plant. entered any power block building or vital area. 1

5. Loss of physical 1. Physical attack on the GENERAL control of t h e p l a n t . plant has resulted in EMERGENCY unauthorized personnel occupying the Control Room or the Remote Shutdown Panel or controlling Decay Heat Removal, Reactor Water Level o r Reactivity Control capability.

GRAND GULF NUCLEAR STATION 10-5-01-1 Revision 111 Attachment I Page 20 of 25 EMERGENCY CLASSIFICATIONS EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL ZLASSIFICATION

15. Hazards to 1. Hazards being 1. Notification of an UNUSUAL EVENT Plant experienced or aircraft crash onsite Operations projected with the outside the protected otential. for area Pdegradation of the l e v e l of s a f e t y o f the plant or 2 . Notification of unusua aircraft activity over the facility (Example:

Spraying or dropping something on company property) or 3 . Notification of an onsite explosion (does not affect plant operationf Or

4. Determination that a release of toxic, oxygen displacing, or flammable gas will significantly hamper the ability of personnel to perform activities affecting plant: safety

5. A manual or automatic scram initiated because of a turbine blade failure that has not penetrated the casing

GRAND GULF NUCLEAR STATION 10-s-01-1 Revision 111 Attachment I Page 21 of 25 m R G E N C Y CLASSIFICATIONS EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL ZLASSIFICATION

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 potential area, no damage to plant substantial vital areas degradation of the level of safety of the plant Or

2. Notification of missile impacts on plant non-vital structures or

3. Notification of an onsite explosion affecting plant ope ration 1

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

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

GRAND GULF NUCLEAR STATION 10-5-01-1 Revision 111 Attachment I Page 22 of 25 EXRRGBNCY CLASSIFICATIONS EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL 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 f o r -

or protection of the public 2. Notification of severe damage to safe shutdown equipment from missiles or explosion or 3 . Determination that the entry of toxic or flammable gases into v i t a l areas

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE 110-S-01-1 1 Revision 111 Attachment I Page 23 of 25 EMERGENCY CLASSIFICATIONS EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL 2LAS SIFICATION

.6. Natural L. Natural events being _. A verified earthquake UNUSUAL EVENT Events experienced or detected by in-plant projected beyond seismic instrumentation usual levels or

? . 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 I

or

2. A tornado causing damage to Safety Related structures or 3 . Sustained winds r 7 3 mph onsite

_I 3 . Severe natural event 1. 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 or

2. Sustained winds 290 mph onsite 4 . Major internal 1. Fires, earthquakes, GENERAL or etc., substantially EMERGENCY external e v e n t s beyond design basis which could or have caused massive common damage to plant systems IE - Operatin: Sarthquake SSE - Safe Shut ~ w nEarthquake

GRAND GULF NUCLEAR STATION 10-s-01-1 Revision 111 Attachment I Page 24 of 25 EMERGENCY CZASSLFICATIONS EMERGENCY ACTION EMERGENCY CATEGORY INITIATING CONDITION LEVEL :LASSIFICATION

17. Loss o f 1. Significant loss of 1. T o t a l lass of umsuAt EmNT assessment, vital accident vital accident communications, assessment or assessment equipment annunciators communications such as:

equipment capability

a. All v e s s e l level instruments or,

b. All containment monitoring instruments, etc, or

2. Degradation of the offsite communication system to only one Source

2. Loss of ALL 1. LOSS of zu;L ALERT annunciators annunciators on the P680, P601, and P870 panels

1. Other plant 1. Plant conditions exist UNUSUAL EVENT conditions exist that warrant a that warrant precautionary increased awareness notification t o local on the part of the and state authorities.

plant operating staff.

AND/OR State and Local Authorities

2. Plant conditions I. Plant conditions ALERT exists that warrant exists that warrant precautionary activation of the TSC activation of the or EOF TSC and placing the EOF and key p l a n t personnel on i

TSC EOF Technical Suppc standby.

t Center Emergency Operations Facility

GRAND GULF NUCLEAR STATION 10-s-01-1 Revision 111 Attachment I Page 25 of 25 EMBRGXNCY CLASSSPICATIONS EMERGENCY CATEGORY INITIATING CONDITION EMERGENCY ACTION LEVEL lLASSIF1CATION

18. Discretionary 3 . Other plant conditions 1. Plant conditions exist SITE AREA exist that warrant that indicate a release EMERGENCY activation of is in progress or Emergency Facilities imminent: that could and monitoring teams or affect the near site a precautionary public.

notification to the public near t h e site.

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

activity in a short (Not limited to the time possible following examples) :

Core damage is predicted to occur (within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) and Containment pressure is > 22 psig or containment is breached J:ADM _.SRVS/TECH-PUB/REVISION/~O/~OSO~~.DOC

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE 110-5-01-1 1 Revision 111 Attachment II Page 1 of 2 GUIDELINES T O TERE6INATE EMERGENCY PURPOSE: To establish general guidelines to be followed should changing plant conditions warrant termination of an emergency classification, NOTE The Emergency Director/Offsite Emergency Coordinator must discuss existing offsite conditions with appropriated State officials prior to terminating an emergency.

1 I 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 of an event is removed, isolated or under control.

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 contained.

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 111 Attachment I1 Page 2 of 2 GUIDELINES TO TERMINATE EMERGENCY B. Specific Examples (cont.)

CATEGORY TERMINATION GUIDELINES 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.

p1ant 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 Threai Threat to s i t e is terminated. Probability of recurrence has been removed, with the concurrence of Security Supervisor and State, Local and Federal Officials.

PWLNT OPERATIONS MWUAL Volume 10 10-S-01-26 Section 01 Revision: 10 Date: 12/1/03 ENERGENCY PLAN PROCEDURE:

OFFSITE W R G E N C Y RESPONSE SAFETY RELATED R

Prepared :

Reviewed :

Concurred:

OSRC :

Approved : I tr,P1"rmt Gen-Manager Manager, 'Emercrency Preparedness List o f Effective Pages:

Pages 1-4 Attachment I List of TCF;Js Incorporated:

pevi sion TCN I_

0 None 1 None 2 None 3 None 4 None 5 None 6 None 7 None 8 None 9 None 10 None

Title:

Offsite Emergency Response No.: 10-S-01-26 Revision: 10 Safety Evaluation Description of Proposed Change Revision 10:

Updates procedure references. 01-SO-04-21 was cancelled and replaced by procedure TQ-110.

a Corrects names o f the Vicksburg hospitals listed in the procedure.

Vicksburg Medical Center and Parkview Med cal Center were closed and River Region Medical Center now provides services to GGNS.

Changes the GGNS restricted area to protected area for consistent definition use.

Changes the Health Physic8 Department name to Radiation Protection.

e Changes Radiologically Controlled Area to Controlled Access Area.

If the proposed activity, in its entirety, involves any one of the criteria below, check the appropriate box, provide a justificationfbasis in the Description above, and forward to a Reviewer.. No further 5 0 . 5 9 Review is required. If none of the criteria is applicable, continue with the 50.59 Review.

CJ The proposed activity is editorial/typographical as defined in Section 5 . 2 . 2 .l.

0 The proposed activity represents an "FSAR-only" change as allowed in Section 5.2.2.2 . (Insert item # from Section 5.2.2.2).

If further: 5 0 , 5 9 Review is required, check the applicable review(s): (Only the sections indicated must be included in the Review.)

~~

SCREENING Sections I, r I , III, and rv required 0 50.59 EVALUATION EXEMPTION Sections I, IT, 1x1, IV, and V required 5 0 . 5 9 EVALUATION (#: Sections I, XI, 111, f XV, and VI required

Title:

Offsite Emergency Response No.: 10-S-01-26 Revision: 10 Safety kraluat ion Preparer: Richard Van Den Akker - /EOI/NSA-EP/ 6-/6-d3 Name (print) / S i g n a m @ / Company / Department / Date OSRC :

AlA Chairman's 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 PIANPROCEDURE

Title:

Offsite Emergency Response No.: 10-S-01-26 Revision: 10 Safety Evaluation opera tiny License YES NO CHANGE # and/or SECTIONS IMPACTED operating License n a TS a

p I

m ~ ~-

NRC Orders o m -1 If YESrf, obtain NRC approval prior to implementing the change by initiating an LBD change in accordance with NWM LI-113 (Reference 2 . 2 . 1 3 ) . (See Section 5.1.13 for exceptions.)

- -~

FSAR LBDS controlled under 50.59

- ~

I a Im i YES No C H m G E # (if applicable1 and/or SECTIONS IMPACTED TS Bases D B I Technical Requirements u t a Manual Core Operating Limits u m Report NRC safety Evaluation c 1 w Reports LBDs controlled under YES NO CHANGE # (if applicable) and/or other regulations SECTIONS IMPACTED Quality Assurance Program C l m Manual2 Emergency Plan2 I J H Fire Protection Program3 C l E l (includes the Fire? Hazards Analysis) offsite D o s e Calculations o m Manual

Title:

Offsite Emergency Response No.: 10-5-01-26 Revision: 10 Safety Evaluation

3. Does the proposed activity potentially impact equipment, Yes procedures, or facilities utilized o r storing spent fuel at an No Independent Spent Fuel Storage Installation? la N/A (Check "N/Arf i f d r y f u e l storage is not applicable to the facility.)

If "yes," perform a 7 2 . 4 8 Review in accordance with NMM procedure LI-112.

(See Sections 1.5 and 5.3.1.5 of the E O I 10CFR50.59 Review Program Guidelines.)

B. Basis provide a clear, concise basis f o r the answers given in the applicable sections above. Explain why the proposed activity does or does not impact the Operating License/Technical Specifications and/or the FSAR and why the proposed activity does ox does n o t involve a new test or experiment not previously described in the FSAR. Adequate basis must be provided within the Screening such that a third-party reviewer can reach the same conclusions. Simply stating that the change does not affect TS or the FSAR is not an acceptable basis. See EOI 5 0 . 5 9 Guidelines Section 5.6.6 for guidance.)

Performed keyword searches of the on-line COLR, Fire Protection Program, UFSnR, TECHSPEkS, ODCM, QAPM, SERs, and Emerqency Plan for the keywords:

restricted area, protected area, health physics, radiological controlled area, hospital and medical center.

Reviewed all hits associated with the keywords. Performed manual reviews of Emergency Plan section 5.6 - Local Services Support Reviews showed that the changes from 'restricted area', 'health physics' and 'radioloqically controlled area' to 'protected area', 'radiation protection' and 'controlled access area', respectively, are consistent with the terms and definitions found in the UFSAR and GGNS Emergency Plan. In addition the change from Vicksburq and Parkview hospitals to Riverland Medical Center is consistent with chanqes previously made to the UFSAR and the CGNS Emergency Plan.

The proposed change to this procedure does not conflict with the documents above and will have no impact on any Grand G u l f licensinq basis documents.

This change does not involve a test or experiment nor does it impact equipment, procedures, or facilities of Grand Gulf Nuclear Station.

GRAND GULF NUCLEAR. STATION EMERGENCY PLANPROCEDURE

Title:

Offsite Emergency Response No.: 10-5-01-26 Revision: 10 Safety Evaluation

c. References Discuss the methodology for performing the LBD search. State the location o f relevant licensing document information and explain the scope of the review such as electronic search criteria used (e.g.,key words)

OK the general extent of manual searches per Section 5.3.6.4 of LI-101.

NOTE: Ensure that electronic and manual searches are performed using controlled copies of documents. If you have any questions, contact your s i t e Licensing department.

LBDs/Documents reviewed via keyword Keywords:

search:

restricted area, protected area, UFSAR, TECHSPECS ODCM, QAPM health physics, radioloqical EMERGENCY PLA.N, SERS controlled area, hospital and medical center.

LBDs/Documents reviewed manually:

Emergency P l a n section section 5.6 -

Local Services Support.

D. Is the validity of this Revview dependent on [I1 Yes any other change? (See Section 5.3.4 of the INo EOI 10CFR50.59 Program Review Guidelines.)

If Y e s , I list the required changes.

Title:

Offsite Emergency Response No.: 10-S-01-26 Revision: 20 Safety Evaluation 111. BNVXR0"TAL SCREENING If any of the following questions is answered an Environmental Review must be! performed in accordance with NMM Procedure EY-115, "Environmental Evaluations,"

and attached to this 50.59 Review. Consider both routine and non-routine (emergency) discharges when answering these questions.

Will the proposed Change being evaluated:

1. Involve a land disturbance of previously disturbed land areas in excess of one acre (i.e., grading activities, construction of buildings, excavations, reforestation, creation or removal of ponds)?

2. Involve a land disturbance of undisturbed land areas (Le., grading activities, construction, excavations, reforestation, creating, or removing ponds)?

3. lnvolve dredging activities in a lake, river, pond, or stream?

4. Increase the amount of thermal heat being discharged to the river or lake?

5. Increase the concentration or quantity of chemicals being discharged to the river, lake, or air?

6. Discharge any chemicals new or different from that previously discharged?

7. Change the design or operation of the intake or discharge structures?

I

8. Modify the design or operation of the cooling tower that will change water or air flow characteristics?

9. Modify the design or operation of the p\ant that will change the path of an existing water discharge or that will result in a new water discharge?

10. Modify existing stationary fuel burning equipment (Le., diesel fuel oil, butane, gasoline, propane, and kerosene)?'

11. Involve the installation of stationary fuel burning equipment or use of portable fuel burning equipment (Le., diesel fuel oil, butane, gasoline, propane, and kerosene)?'

12. Involve the installation or use of equipment that will result in an air emission discharge?

13. fnvofve the installation or modification of a stationary or mobile tank?

14. Involve the use or storage of oils or chemicals that could be directly released into the environment?

15. lnvdve burial or placement of any solid wastes in the site area that may affect runoff, surface water, or groundwater?

See NMM Procedure EV-117, "Air Emissions Management Program," for guidance in answering this question.

GRAND GULF NUCLEAR STATION EMERGENCY PLANPROCEDURE

Title:

Offsite Emergency Response No.: 10-5-01-26 Revision: 20 Safety Evaluation IV. SECURITY PLAN SCREENING If any of the following questions is answered yes, a Security Plan review must be performed by the Security Department to determine actual impact to the Plan and the need for a change to the Plan.

A. Could the proposed activity being evaluated:

Y e -N O S

1. El Add, delete, modify, or otherwise affect Security department responsibilities (e.g., including fire brigade, fire watch, and confined space rescue operations)?

2. 0 El Result in a breach to any security barrier(s) (e.g., HVAC ductwork, fences, doors, walls, ceilings, floors, penetrations, and ballistic barriers)?

3. 0 El Cause materials or equipment to be placed or installed within the Security Isolation Zone?

4. El El Affect security lighting by adding or deleting lights, structures, buildings, or temporary facilities?

5. 0 El Modify or otherwise affect the intrusion detection systems (e.g., E-fields, microwave, fiber optics)?

6. El El Modify or otherwise affect the operation or field of view of the security cameras?

7. Cl EJ Modify or otherwise affect (block, move, or alter) installed access control equipment, intrusion detection equipment, or other security equipment?

8. cl El Modify or otherwise affect primary or secondary power supplies to access control equipment, intrusion detection equipment, other security equipment, or to the Central Alarm Station or the Secondary Alarm Station?

9. 0 El Modify or otherwise affect the facilitys security-related signage or land vehicle barriers, including access roadways?

10. c3 El Modify or otherwise affect the facilitys telephone or security radio systems?

The Security Department answers the following questions if one of the questions was answered yes.

B. Is the Security Plan actually impacted by the 0 Yes proposed activity? 0 No C. Is a change to the Security Plan required? 0 Yes Change # (optional) 0 No Name of Security Plan reviewer (print) I Signature I Date

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE

Title:

Offsite Emergency NO.: 10-5-01-26 Revision: 10 Page: i

Response

RPTS FORM 10CFR50.59 Review Required? 1 (W Yes I If Yes, attach 50.59 Review Form 1 ( 1 No 1 Not required per LI-101 P r e p a r e r Initials>>>

D e p a r t m e n t C r o s s - D i s c i p l i n e Reviews Needed Signoff (signed, electronic, telcont Does this directive contain Tech Spec Triggers? ( ) YES Kl NO REQUIREXEHTS CROSS-REFERENCE LXST

[Requirement Implemented by Directive 1 Directive Paragraph Number 1 Name Paraqraph Number That Implements Requirement FSAR 9B 2.1.7 6.5 Note 10CFR19.12 52

GGCR-1997-0635-00

6.4.3 f 1

Covered by d i r e c t i v e as a whale o r by v a r i o u s p a r a g r a p h s of the directive.

NOTE The Component Database Change Request statement is applicable only to Volume 06 and 07 maintenance directives.

Component Database Change Request generated and the backup documentation available for setpoint and/or calibration data only c] Y e s Fcp N/A CDBCR #

Current Revision Statement Revision 10:

0 Updates procedure references. 01-S-04-21was cancelled and replace by procedure TQ-3.10.

e Corrects the names of the Vicksburg hospitals listed in the procedure. Vicksburg Medical Center and Parkview Medical Center were closed and River Region Medical Center now provide6 services to GGNS.

0 Changes the GGNS restricted area to protected area for consistent definition use.

0 Changes the Health Physics Department name to Radiation Protection.

0 Changes the Radiological Controlled Area to Controlled Access A r e a .

ATTACHMENT9.1 NUCLEAR MANAGEMENT MANUAL I QUALITY RELATED lNFORMAliON USE I EP-305 Page REV. NO.0 of 2 10CFR50.54(a) SCREENING I

1. DOCUMENT XMFORMATION ProcedureDocument Number: 10-S-01-26 I Proc./Doc. Revision: 10 Document

Title:

Offsite Emergency Response -

Brief Description of Proposed Revision: Updates procedure references. 01-S-04-21 was cancelled and replace by procedure TO-1 10. Corrects the names of the Vicksburiz, hospitals listed in the procedure.

Vicksburg Medical Center and Parkview Medical Center were closed and River Region Medical Center now provides services to GGNS. Changes the GGNS restricted area to protected area for consistent definition use. Chanpes the Health Physics Department name to Radiation Protection and other administrative changes.

2. SCREENING A.) Does the proposed revision require a change to the Emergency Plan, change a commitment in the E-Plan, or potentially decrease the effectiveness of the E-Plan?

-Yes X No B.) Does the proposed revision change the Emergency Action Levels (EALs)?

-Yes X No If the answer to either question is YES, then a 10CFR50.54(q) evaluation must be performed. See attachment 9.2. If the answer is NO provide justification below, Reviewed the applicable portions of the Emergency Plan. The Emergency Plan has been revised and contains the changes made in this procedure. This revision does not change or affect the E-Plan and therefore does not decrease the effectiveness of the Emergency Plan. This procedure does not contain any EAL information and therefore does not change the GGNS EALs. J

4. APPROVAL Screening- Prepared By:

Date Screening Reviewed By: l?--/w 3 t signature Date Screening Approved By: 8/zs/u3 Signature Date

Title:

Offsite Emergency NO.: 10-S-01-26 Revision: 10 Page: 1

Response

1.0 PURPOSE 1.1 Provide instructions to Offsite Emergency Personnel who are requested to report to the site during a GGNS emergency.

1.2 Provide instructions for the control of emergency vehicles reporting to the site during a GGNS emergency.

2.0 BESPONSIBILITIES 2.1 Manaaer, Ehercrencv PreDaredness - Ensure that all emergency personnel are trained to respond to an emergency at GGNS in accordance with this procedure.

3.0 REFERENCES

3.1 Nuclear Management Manual TQ-110, Emergency Preparedness Training Program 3.2 Emergency Plan Procedure 10-5-01-17,Emergency Personnel Exposure Control 4.0 4.1 Visitor's 10CFR19 Indoctrination 5.0 PEFINITIONS 5.1 pneruencv Personnel - Emergency Response Personnel and Offsite Ekergency Personnel.

5.2 a- Operations Support Center 5.3 - Emergency Operations Facility 5.4 ESC - Energy Services Center 5.5 a- Health Physicist 6.0 DETAILS 6.1 Personnel 6.1.1 All personnel requiring access to the protected area must proceed through Security Island and report to the OSC. If the OSC and Security Island are evacuated, personnel should report to the EOF.

6.1.2 EOF personnel are NOT REQUIRED to go to the OSC:

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE

Title:

Offsite Ehergency NO.: 10-S-01-26 Revision: 10 Page: 2

Response

6.2 Security controlled Access 6.2.1 Security personnel control access to the Protected Area at the security Island. In the event that Security Island is not habitable, the Security Coordinator should initiate other means of access control in accordance with Security procedures.

6.3 Protected Area Access Instructions 6.3.1 Report to the OSC as follows:

a. Follow the directional arrows and instructions uDon entrv into the Protected Area (when thev are dislslaved).

b. Proceed directly to the established entry point for the OSC.

Entry is normally through the small door at the rear of the maintenance shop, unless otherwise authorized by the OSC coordinator.

C. Adhere the FRISKING requirements as established.

a, OSC Coordinator may furnish additional instructions/

precautions or allow personnel to proceed directly to their work area.

6.4 Site Access 6.4.1 Persons who enter the GGNS Protected Area to support: an emergency I response shall receive GGNS training commensurate with the radiological hazards they may encounter during performance of their duties.

6.4.2 The following agencieslpersomel normally receive annual radiological training and are exempt from 6.4.1 (above) when on GGNS property during an emergency response:

a. MS Emergency Management Agency.

b. MS Depth of Health

c. Claiborne County Sheriff Dept.

d. Port Gibson Police Dept.

e. Claiborne County Fire Dept.

f. Claiborne County Haspital

g. River Region Medical Center

h. Vicksburg Fire Department

GRAND GULF NUCLEAR STATION EMERGENCY PLNJ PROCEDURE

Title:

offsite Emergency NO.: 10-5-01-26 Revision: 10 Page: 3 6.4.2 (Cant.1

i. Nuclear Regulatory Conmission

j. Federal Emergency Management Agency

k. Department of Energy

1. Environmental Protection Agency rn. Stone and Webster

n. Westinghouse

o. General Electric 6.4.3 Offsite personnel (including GGNS contractor personnel) who are not listed above and those listed above who do not have radiological training, shall be provided a copy of Attachment I to read, sign, and return to the Radiation Ehergency Manager or other designated individuals.

6.4.4 When on GGNS property, offsite persomel will be monitored, i n a manner consistent with GGNS procedures, for radiological exposure comensurate with the expected hazards which they may encounter during performance of their duties.

6.5 OFFSITE EMERGENCY ASSISTANCE VEHICLES NOTE Authorization for vehicle entry into the protected area must be given in accordance with security Procedure.

Offsite emergency assistance vehicles are required to stop at Security Island prior to entering the protected area.

The Claiborne County Fire Department will provide backup support for the onsite fire brigade when requested.

6.5.1 ReDortinq

a. Once it has been determined that offsite assistance is required, the Shift Manager/Emergency Director informs the Central Alarm Station that outside assistance will be arriving.

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE

Title:

Offsite Emergency NO.: 10-5-01-26 Revision: 10 Page: 4

Response

6.5.1 (Cont.1

b. Security Island personnel must notify the OSC (if activated) and the Control Room that an offsite emergency vehicle is coming on site.

6.5.2 Dosimetrv

a. Visitors key cards with TLDs attached are issued by the Security Island personnel.

b. During a declared emergency, additional dosimetry is issued as necessary by the OSC personnel in accordance with Reference 3.2.

c. All dosimetry is collected by the vehicle escort upon exiting the site, with the exception of ambulance crews transporting contaminated individuals. This dosimetry is collected after patient transport is completed.

6.5.3 Escorts for offsite Emercrencv Vehicles NOTE Security provides escorts or vehicles only. Individual personnel escorts may be necessary if emergency personnel will be away from the vehicle while it is onsite.

a. The person escorting an offsite emergency vehicle is responsible for:

(1) Directing the vehicle to and from the emergency location (2) Returning dosimetry to the OSC HP Coordinator for processing with the exception of d u l a n c e crews transporting contaminated individuals. This dosimetry is collected by the person accompanying the d u l a n c e to the offsite medical facility after patient transport is complete.

(3) Notifying Radiation Protection {as necessary) to ensure offsite vehicles and personnel are surveyed and deconned prior to exiting the site

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE 10-5-01-26 VISZTOR S 10CFRlS INDOCTRIUATION

1. Inform your employer of previous or concurrent radiation exposure.

2. Obey stop work and evacuation orders of Radiation Protection personnel.

3. Obey all posted, verbal, andlor written Radiation Protection instructions; maintain contact with and follow directions of your escort.

4. Wear your TLD and/or Dosimeter on the upper front torso of your body, or as instructed by Radiation Protection personnel.

5. Utilize time, distance, and shielding whenever possible to keep dose ALARA.

6. For a known or possible radiological problem, notify Radiation Protection personnel promptly.

7. m o w that you have the right to request your exposure records.

8. Be aware that radiation exposure has some health risk involved. However, if your dose is kept within legal limits and guidelines, the risk is said to be acceptable.

9. Keep track of your radiation exposure status and avoid exceeding exposure guidelines.

10. Do not loiter in Controlled Access Areas.

11. Do not smokeleat, drink, or chew in Controlled Access Areas.

12 I Regulatory Guide 8.13 recommends limiting exposure to a pregnant woman to 500 mR for the entire gestation period. For a copy of this Regulatory Guide and the Entergy policy concerning exposure of fertile/pregnant woman, please ask a Dosimetry representative.

13. Obtain permission from Radiation Protection prior to entering any posted radiological area, other than a Radioactive Materials Area, Radioactive I

Materials Storage Area, or Radiation Area.

24. If you have had a medically administered radioisotope (tread mill test, thyroid test, GI tract scan, Barium cocktail, etc.) within the past three months, inform Dosimetrv immediatelv.

15. Stop at the 93 elevation o f the Control Building at the Radiation Protection Lab or at the Operations Support Center and sign in on an RWP prior to entering any Controlled Access Area.

I I have read, understand, and will comply with the above instructions/information. I have had the opportunity to ask questions regarding this information, and if done, have received appropriate information regarding those questions.

Visitor Name/Signature Date

/

REM/OSC HP Coord. Initial Visitor SSN Organization

GNRO-2003/00073, Changes to Emergency Plan Implementing Procedures-December 8, 2003

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