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 10-S-01-1 10-S-01-26 US. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Rev. 11 1 Rev. 10

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 1 OCFR50 Appendix E,Section V changes to the following Emergency Plan Implementing Procedure(s):

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 Page 2 of 2 G N RO-2003/00073 cc:

Hoeg Levanway Reynolds Smith Thomas T. L.

(GGNS Senior Resident)

(w/a)

D. E.

(Wise Carter)

(w/a)

L. J.

(Wise Carter)

(w/a)

~~ N. S.

(w/a)

H. L.

(w/o)

US. Nuclear Regulatory Commission ATTN: Mr. Bruce Mallett (w/2) 61 1 Ryan Plaza Drive, Suite 400 Arlington, TX 7601 1-4005 U.S. Nuclear Regulatory Commission ATTN: Mr. Bhalchandra Vaidya, NRR/DLPM (w/2)

ATTN: FOR ADDRESSEE ONLY ATTN: U.S. Postal Delivery Address Only Mail Stop OWFN/7D-1 Washington, D.C. 20555-0001 I

ALL LETTERS - U.S.

POSTAL SERVICE MAIL DELIVERY ADDRESS ONLY

PLANT OPERATIONS MANUAL Volume 10 Section 01 10-s-01-1 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) Dated 3/19/03 List of TCNs Incorporated:

Revision 1-4 5

6 7

8 9

10 11 12 13 14/15 16 17 18 19 20 21 22 23 100 101 102 103-111 TCN None 1 1 2 3

4 5,6 None 7,8 None 9

10 None 11 None 12 None None None 13/14 None 15 None 16 None

Title:

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

OVERVIEW I SIGNATURES Safety Evaluation DescriPtion of Proposed Change SEE CURRENT REVISION STATEMENT d

SCREENING 50.59 EVALUATION EXEMPTION 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 editorialltypographical as 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 ##from Section 5.2.2.2).

1 Sections I, II, 111, and IV required 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 Emerqency Plan

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?

Revision: 111 Safety Evaluation Operating License Operating License TS NRC Orders 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). (See Section 5.1.13 for exceptions.)

LBDs controlled under 50.59 1 YES I NOA CHANGE #and/or SECTIONS TO BE REYISED 1

YES NO CHANGE #and/or SECTIONS TO BE REVISED CI a

cl FSAR TS Bases Technical Requirements Manual Core Operating Limits Report If YES, perform an ExemptionrReview per Section V OR perform a 50.59 Evaluation per Section Vl accordance with NMM LI-I13 (Reference 2.2.13).

lnftlate an LBD change in a

d II1 0

a d, 1

7 cl NRC Safetv Evaluation Reoorts cl 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-I 13 [Reference 2.2.131.

LBDs controlled under other YES regulaiions Quality Assurance Program Manualz 13 Emergency Plan D

Fire Protection Program 0

(includes the Fire Hazards Analysis)

2.

3.

NO CHANGE # andlor SECTIONS TO BE REYISEL)

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

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

perform a 50.59 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.)

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.)

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

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

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

T i t l e :

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

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 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 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.

Safety Evaluation C.

References Discuss the methodology for performing the LBD search. State the location of relevant licensing document information and 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:

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

Keywords:

Power block, decay heat D.

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

If Yes, list the required changes.

Title:

Activation of the Ernerqency Plan 111. ENVtRONMENTAL SCREENlNG No.: 10-5-01-1 Revision: 111 Safety Evaluation 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

1. a

2. 0

3.

cl

4. 0

5. 0

6.

7.

cl

8. 0

9. cl

10.

cl

11. 0

12.

cl

13. c]

14. 0

15. a No

-7

@ 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)?

excavations, reforestation, creating, or removing ponds)?

d Involve a land disturbance of undisturbed land areas (i.e., grading activities, construction, d

Involve dredging activities in a lake, river, pond, or stream?

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

rd Increase the concentration or quantity of chemicals being discharged to the river, lake, or d

Discharge any chemicals new or different from that previously discharged?

d Change the design or operation of the intake or discharge structures?

cz( Modify the design or operation of the cooling tower that will change water or air flow d

Modify the design or operation of the plant that will change the path of an existing water d

Modify existing stationary fuel burning equipment @e., diesel fuel oil, butane, gasoline, d l n v o l v e the instaltation of stationary fuel burning equipment or use of portable fuel burning d

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

d Involve the installation or modification of a stationary or mobile tank?

air?

characteristics?

discharge or that will result in a new water discharge?

propane, and kerosene)?f equipment (i.e., diesel fuel oil, butane, gasoline, propane, and kerosene)?

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

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 Ernexqency Plan

~~

~

~~~

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:

Revision: 111 Safety Evaluation

1.

2.

3.

4.

5.

6.

7.

8.

9.

10.

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

ceilings, floors, penetrations, and ballistic barriers)?

d Result in a breach to any security barrier(s) (e.g., HVAC ductwork, fences, doors, walls, d Cause materials or equipment to be placed or installed within the Security Isolation Zone?

6 Affect security lighting by adding or deleting lights, structures, buildings, or temporary Ed Modify or otherwise affect the intrusion detection systems (e.g., E-fields, microwave, fiber optics)?

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

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

d Modify or otherwise affect primary or secondary power supplies to access control facilities?

equipment, intrusion detection equipment, other security equipment, or to the Central Alarm Station or the Secondary Alarm Station?

including access roadways?

d Modify or otherwise affect the facilitys security-related signage or land vehicle barriers, 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 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

Revision: 111 Page: i Requirement Implemented by Directive Name Paraqraph Number ANSI N18.7 GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emew Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GGNS Emer Plan GNFtI-93/00171 Directive Paragraph Number That Implements Requirement 5.3.9.2. s1 2.4.53 3.3.Sl I

6.2.2.53 & S4 5.4.5.a, b, c 5.4.4 3.1.S2 6.2.2.51 & 52 4.1.4.s3 4.1.53 4.1.Sl3 3.3.S6.b 6.2.4.511 & 512 6.2.4.Sl3 6.2.4.514 4.1.4

.S2 6.3.1.51 6r S2 6.3.2 6.3.3, 6.3.4 9.3.57 Table 4-1 7.5.3.a.2.e 93-13-01, Item 6 6.5.1.b.55, S6 7.5.3.a.3.c 6.2.4.52 6.2.4.57 & S 8 5.4

. S 6 3.3.s3 & s4 6.5.l.b 6.5.1.A.

1 3.3.s5 6.1.2 1.1.1 2.1.2 2.1.1, 6.1.2 52 2.2 2.3 6.1.2 6.1.2 (Note)

Attachment I 6.1.4, 6.3 6.1.3 (Note) 6.1.3 6.1.4.1 (11 6.1.4.1 (2) 6.1.4.J (3) 6.1.4. k (1) 6.2.1 6.2.la 6.2.lb Attachment II (Note)

Attachment I 5.30 Attachment I, 17.1.1 6.1.4. k f l )

6.1.4.e 2.1.2 2.4 6.1.4.j (11, j (21, j (3) 2.4 6.1.4 6.1.4.h 2.1.2 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 NOTE

__I_

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.

Operations and Security.

interpretation.

The definition used in this procedure is consistent with Adds the definition of "Decay Heat Removal" to the procedure for consistent

QUALITY RELATED lNFORMATlON USE I

NUCLEAR MANAGfiMENT

- Entegy MANUAL Reviewed the ap~licable Dortions 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.

1 EP-305 REV. NO. 0 Page g

of fi ATTACHMENT 9.1 I

OCfR50.54(~) SCREENING

1.

DOCUMENT INFOFtlS!IATION Procedure/Document Number: 10-S-0 1-01 I Proc./Doc. Revision: 11 1 I

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.

4.

APPROVAL Screening Prepared By:

Signature Date Screening Reviewed By:

Is/L1/0 2 Signiture Date Screening Approved By: m&

4 g A. 3 Signature Date

Title:

Activation of the No.: 10-5-01-1 Revision: 111 TABLE OF CONTENTS Page: 1 1.0 PURPOSE AND DISCUSSION 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 6.3 Upgrading Emergency Classifications 6.4 Terminating Emergency 6.5 Records and Reports 6.6 EP form EPP 01-02 (Flow Chart) Revision Process Page 2

'10 11 11 12 12

GRAND GULF NUCLEAR STATION

Title:

Activation of the No.: 10-S-01-1 Revision: 111 Emergency Plan EMERGENCY PLAN PROCEDURE Page: 2 1.0 PURPOSE AND DISCUSSION 1.1 Purpose 1.1.1 This procedure provides guidance to:

a.

b.

Assign responsibilities for emergency actions.

c.

Establish lines of authority and communication.

d.

Initiate emergency actions to safeguard the public and plant Classify an emergency according to severity.

personnel.

Upgrade or terminate emergency classification when severity of event changes.

e.

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.

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

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

2.1.2 The Shift Manager assumes the role of Emergency Director upon

Title:

Activation of the No.: 10-5-01-1 Emerqency Plan 2.2 2.3

2.4 Revision

111 Page: 3 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.

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

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.

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

notification of an Unusual Event if he deems it necessary.

emergency classification has been made.

2.4.2 2.4.3 Reporting to the site to assume duties of Emergency Director upon 2.4.4 Evaluating the accident conditions and verifying that the correct

3.0 REFERENCES

I 3.1 NRC Memorandum dated July 11, 1994 concerning Branch Position on 3.2 GGNS Emergency Plan Acceptable Deviations to Appendix 1 to NfJREG-O654/FEMA-REP-l.

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.

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

5. 2 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 Emergency Plan 5. 6 5. 7 5.8 5.9 5.10 5.11 5.12 5.13 5.14 5.15 5.16 5.17 5.18 5.19 5 - 2 0 5.21 Page: 4 Downwind - An area located beyond a fixed point in the same direction the wind is blowing. The area covers three sectors, the sector containing the plume centerline, and the two adjacent sectors. If the plume is on a sector line, four sectors are used until the three sector criteria can be identified.

Emerqency - 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.

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.

Emergency 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 increasing order of severity: Unusual Event, Alert, Site Area Emerqency and General Emergency.

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 Emergency Operations Facility (EOFJ - A near-site emergency center from which the offsite emergency support activities are controlled 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 EPP - Emergency Plan Procedure 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.

ESC - Energy Services Center 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 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.

LOCA - Loss of Coolant Accident OEC - Offsite Emergency coordinator Offsite - For accountability purposes, any area outside the GGNS protected area 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. 2 2 Onsite - For accountability purposes, the area within the GGNS protected 5. 2 3 Operations Support Center (OSC) - Location from which onsite non-Control 5. 2 4 PA - Public Address System 5.25 pAc: - Protective Action Guide 5.26 pAR - Protective Action Recommendation 5. 2 7 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.

area Room activities are staged and implemented 5.28 SAS - secondary Alarm Station 5. 2 9 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.

exceed EPA Protective Action Guideline exposure levels except near the site boundary.

Any releases are not expected to 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. 3 2 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 5. 3 5

- 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. 3 8 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.

nonpregnant adults from exposure and intake during an emergency situation.

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 6.1.2 6.1.3 6.1.4 Any person having knowledge of abnormal plant conditions should notify the Shift Supervisor/Manager.

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.

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 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

- 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.

general public.

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),

perform in accordance with 10-S-01-11.

h.

If an evacuation of affected areas of the plant is required,

Title:

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

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.

must be activated.

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

(2)

If an Alert has been declared, a l l emergency facilities

( 3 )

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 General Emergency as follows:

Condition General Emergency Declared General Emergency Declared Dose Projection or Field Measurement at 2 5 miles corresponds to I

RernTEDE Or 5 Rem ThyroidCDE Protective Action Recommendation EVACUATE: 2 Miles All Sectors and EVACUATE: 5 Miles in Downwind Sectors SHELTER:

EVACUATE: 2 Miles All Sectors Remainder of 10 Mile Emergency Planning Zone (EPZ) and EVACUATE: 10 Miles in Downwind Sectors SHELTER Remainder of I 0 Mile Emergency Planning Zone (EPZ)

Title:

Activation of the No.: 10-S-01-1 Revision: 111 6.1.4 6.1.5 Page: 9 (Cont - 1

1.

Designate shift personnel to perform emergency corrective and assessment actions.

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

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

b.

C.

d.

e.

f.

9.

h.

i.

j.

k.

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

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

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.

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

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

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

Do not activate the VIP-2000.

Do not order a site evacuation.

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

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

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 Emerqency Plan 6.2 Supplemental Actions Page: 10 6.2.1 6.2.2 6.2.3 6.2.4 6.2.5 of

a.

b.

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

' conditions (i.e., radioactive releases).

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 (41 Determination o f offsite doses if applicable.

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

(1) Monitor meteorological data.

( 2 )

has taken place or is suspected.

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).

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.

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

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).

Log as 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 re construct ion 1.

Title:

Activation of the No.: 10-S-01-1 Revision: 111 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 Directorloffsite Emergency Coordinator should authorize preparation of an emergency organization shift schedule to support 24-hour emergency operation.

6.2.7 If extended emergency operations are necessary, the Emergency 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:

Page: 11

a.

b.

e.

d.

e.

f.

9.

Declare appropriate emergency classification in accordance with Step 6.1.2.

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

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

Initiate plant operating procedures and emergency plan procedures as required.

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

Determine offsite doses in accordance with Step 6.1.4k.

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-01-22 to 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 Emergency Plan 6. 5 Records and Reports Page: 12 6.5.1 The Manager, Emergency Preparedness is responsible for generating a report on the activation of the Emergency Plan.

should include the following:

a.

Copies of appropriate paperwork generated by the event The report 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 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)

S imul at or (1)

TSC (2 1 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 10-s-01-1 Attachment I EMERGENCY PLAN PROCEDURE Revision 111 Page 1 of 25

1.

2.

3.

4.

5.

6.

7.

8.

9.

10.

11.

12,

13.

14.

15.

16.

17.

18.

WRGENCY CLASSIFICATIONS TABLE OF CONTENTS CATEGORY Safety System Functions Abnormal Primary Leak RatelLow Reactor Water Level Core Fuel Damage Steam Leaks Abnormal Effluent, Gaseous Abnormal Effluent, Liquid Major Electrical Failures, AC Major Electrical Failures, DC Control Room Evacuation Fire Plant Shutdown Function Abnormal Ih-plant RadiationlAirborne Contamination Levels Fuel Handling Accident Security Threat Hazards to Plant Operations Natural Events Loss of Assessment, Communication, Annunciator Equipment Discretionary NOTE Any changes made to information in Attachment I may require changes to EPP 01-02 (Flowchart),

PAGE 2, 3 4

5,6,7,8 8

9,10,11 11 12, 13 13 14 14 15,16 17 17, i a 19 20,21,22 23 24 24,25

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

~evision 111 Page 2 of 25 EMERGENCY CLASSIFICATIONS CATEGORY

1.

Safety System Functions INITIATING CONDITION L. Inability to reach required shutdown within Technical Specification time limits EMERGENCY ACTION LEVEL Failure to reach the required Plant Mode within Technical specification action statement time frames for any of the following LCO' s :

L.

2.

3.

4.

5.

6.

7.

8.

9.

Safety/relief Valves 3.4.4 or ECCS - Operating 3.5.1 c

O f Primary Containment 3.6.1.1 or -

Primary Containment Airlocks 3.6.1.2 or c

Primary containment Isolation Valves 3.6.1.3 or

_I Low Low Set Valves 3.6.1.6 or I

Residual Heat Removal Containment Spray 3.6.1.7 or Suppression Pool Average Temperature 3.6.2.1 or suppression Pool Level 3.6.2.2 (Continued)

EMERGENCY

!LASS I FICAT ION lNWSUAL EVENT

GRANLl GULF NUCLEAR STATION 10-5-01-1 Attachment I CATEGORY L.

Safety System Functions (Cont.

1 Revision 111 Page 3 of 25 EMERGENCY CLASSIFICATIONS INITIATING CONDITION

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

)

2. Failure of a safety/

relief valve to close following reduction of applicable pressure to below reset point ECCS - Emergency Core Cooling System EMERGENCY ACTION LEVEL or lo. Suppression Pool Makeup System 3.6.2.4 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

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

EMERGENCY ZLASSIFICATION N S U A L EVENT

GRAND GULF NUCLEAR STATION 10-5-01-1 Attachment I CATEGORY 2. Abnormal Primary Leak Rate/

Low Reactor Water Level Revision 111 Page 4 of 25 EMERGENCY CLASSIFICATIONS INITIATING CONDITION

1. Exceeding primary coolant system leak rate

2. Coolant leak rate

> 5 0 gprn 3. Known loss of coolant greater than makeup pump capacity EMERGENCY ACTION LEVEL While in modes 1,2, or 3:

1. > 5 gpm unidentified leakage or

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

1. TQtal leakage calculated to be

> 5 0 gpm while in Plant Mode 1, 2 or 3

1. RPV water level c -167 inch

2. Makeup capacity unable to increase reactor water level EMERGENCY CLASSIFICATION UNUSUAL EVENT ALERT SITE AREA EMERGENCY

GRAND GULF NUCLEAR STATION 1o-s 1 Attachment I CATEGORY I. Core Fuel Damage Revision 111 Page 5 of 25 i - Micro Cui EMERGENCY CLASSIFICATIONS INITIATING CONDITION

1. Fuel damage indication I

2. Severe loss of fuel cladding 3 8 EMERGENCY ACTION LETEL

1. Increase of 285 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 for more than 4 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 4. Laboratory analysis of coolant sample indicates 4.0 pCi/ml dose equivalent 1-131 EMERGENCY

LASS I FICATION UNUSUAL EVENT AZERT

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

GRAND GULF NUCLEAR STATION 10-s-01-1 Attachment I Revision 111 Page 6 of 25 EMERGENCY CLASSIFICATIONS EMERGENCY INITIATING CONDITION

3. Degraded core with possible loss of coolant pci - micro Curies EMERGENCY ACTION LEVEL 1. RPV water level c -167" or cannot 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%

LASS IF I: CATION SITE AREA EMERGENCY

GRAND GULF NUCLEAR STATION 10-s-01-1 EMERGENCY PLAN PROCEDURE Revision 111 Attachment I Page 7 of 25 EMERGENCY CLASSIFICATIONS INITIATING CONDITION

b. LOSS of 2 of 3 fission product barriers with a potential loss of 3rd barrier EMERGENCY ACTION LEVEL L. Loss of any two of the following fission product boundaries with a potential for loss of the third:

Fuel Claddinq Loss

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

b. >lo00 R/Hr 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 EMERGENCY

!LASS I FI CAT ION GENERAL EMERGENCY

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

3. Core Fuel Damage (Cont.

)

4. steam Leaks MSIV - Main Stea Revision 111 Page 8 of 25 m R G E N C H CLASSIFICATIONS INITIATING CONDITION

4. Loss of 2 of 3 Fission product Barriers with a Potential loss of 3rd barrier. (Cont,)

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

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

2. RCIC steam line break

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

EMERGENCY ACTION LEVEL Primary Containment LOSS

a. Primary Containment pressure >56 psig or

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

__c Potential Loss a. Primary containment pressure >22 psig

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

PSP Curve.

c. Operation in the Unsafe ox O X Region of HDOL Curve with Hydrogen Igniters De-Energized abnormal leakage down stxeam of MSIVs

(> 10 gpm or 5000 lbrn/hr)

1. Isolation initiated and

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

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

1. Isolation required due to confirmed steam line break and RCIC steam line fails to isolate Isolation valve PSP - Pressure suppression limit RCIC - Reactor Core Isolation Cooling HCTL - Heat Capacity Temperature Limit HDOL - Hydrogen Deflagration Overpressure Limit EMERGENCY CLASSIFICATION GENERAL EMERGENCY ALERT SITE AREA EMERGENCY

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

5. Abnormal E f f l u e n t,

GASEOUS LCO - Limited Revision 111 Page 9 of 25 gMgRGE53CY CLASSIFICATIONS INITIATING CONDITION

1. Radiological effluent release rate exceeds TRM Spec limit 2. Radiological effluent

>lo times TRM Spec 1 imi t mdition for Operation SGTS - Standby Gas Treatment System TRM - Technical Requirements Manual EMERGENCY ACTION LEVEL I. Entering the action statement of the following LCOs in the Radioactive Gaseous Effluent section of the TRM Specs 6.11.4, 6.11.5, and 6.11.6

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

a. Radwaste Bldg vent

b. Fuel handling vent

c. Containment vent exhaust exhaust exhaust

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

EMERGENCY CLASSIFICATION UNUSUAL EVENT ALERT

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

5. Abnormal Revision 111 Page 10 of 25 Effluent GASEOUS (Cont. I SAR - Final I EMERGENCY CLASSIFICATIONS INITIATING CONDITION 3. Effluent monitors detect levels corresponding to site boundary exposure of:

a. 2 50 mR/Hr 30 minutes Body or (for Whole

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

c. 2 250 m/hr (for 30 min) to the Thyroid.

NOTE Ii Advers e Meteorology I

-Stability Class F, wind speed 1 mlsec, site boundary X f Q 1080 E-6 sec/m3 (FSAR Table 15 6 - 1 2 )

fety Analysis Report pCi - micro Curies Ci - Curies EMERGENCY ACTION LEVEL

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

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

b. 6.0 E-4 Cilsec Iodine for 30 minutes or

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

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

a. 50 mR/Hr for 30 minutes

b. 500 mR/Hr

2. Radiation monitoring or for 2 minutes or -

C. 6.OE-6 pCi/cc Iodine 3. Containmenipost or Accident Radiation Monitor:

a. >330 R/HR for 30 minutes Or

b. >3300 WHR for 2 minute s EMERGENCY lLASSIF1CATION SITE AREA EMERGENCY

G W

GULF NUCLEAR STATION 10-s-01-1 Revision 111 Attachment I Page 11 of 25 5. Abnormal Effluent,

(Cent. )

I

6. Abnormal

Effluent, LIQUID L TEDE - Total E:

CDE - Committet EHBRGEXCY CLASSIFICATIONS INITIATING CONDITION

&.Effluent monitor(8)

LOGICAL CONDITIONS) detect levels corresponding to site boundary exposure of:

1000 mRem Dose Commitment Whole Body (UNDER ACTUAL METEORO-or 5000 mRem Dose Commitment Thyroid 1.Radiological Effluent Release Rate exceeds TRM Spec limit 2.RadiologicaL Effluent s10 times TRM Spec limit eetive Dose Equivalent Dose Equivalent TRM - Technical Requirements Manual EMERGENCY ACTION LEVEL

1. Effluent monitor(s1 (UNDER ACTUAL METEORO-LOGICAL CONDITIONS) confirms release rates corresponding to site boundary exposure of:

a. 1000 mRem TEDE or -

b. 5000 mRem 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

1. Entering the action statement of TRM Spec 6.11.1, in the Radioactive Liquid Effluent section of TRM Spec

1. Liquid release > 10 times the limit of TRM Spec 6.11.1 in the Radioactive Liquid Effluent section of TRM Spec EMERGENCY

'LASS I FI CATION GENERAL EMERGENCY WNUSUAL E n N T ALERT

GRAND GULF NUCLEAR STATION 10-s-01-1 Attachment I CATEGORY 7, Major Electrical Failures (AC)

Revision 111 Page 12 of 25 EMERGENCY CLASSIFICATIONS INITIATING CONDITION

1. Total loss of offsite power or Loss of onsite AC power capability

2. Total loss of o f f s i t e and LOSS of onsite power 5 15 minutes power -

EMERGENCY ACTION LEVEL

t. LOSS of offsite power to :

a. 15AA and -

b. 16AB

c. 17AC or 2. LOSS of ALL three divisional diesel generators while in Plant Operational Condition 1, 2 or 3

1. Loss of offsite power to :

a. 15AA and

b. 16AB and

c. 17AC and 2. LOSS of three divisional diesel generators and

3. 515 minutes EMERGENCY

!LASS I FICATION WNUSUAL EVENT ALERT

GRAND GULF NUCLEAR STATION 10-5-01-1 Attachment I CATEGORY 7. Major Electrical Failures (AC)

(Cont.

1 Revision 111 Page 13 of 25 8. Major Electrical Failures BMERGENCY CLASSIFICATIONS INITIATING CONDITION

3. Total loss of offsite power and Loss of A1;L onsite power >15 minutes 1.' Loss of onsite ESF DC power for 5 15 minutes

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

1. Loss of offsite power to :

a. 15AA and

b. 16AB and -

c. 17AC and

_I__

2. Loss of three divisional diesel generators and

_I_

3. >15 minutes

1. Loss of Division 1, 2 and 3 (125 Vdc for S15 minutes)

1. Loss of Division 1, 2 and 3 (125 V d c or

>I5 MINUTES)

EMERGENCY 3LAS S I FI CATION SITE AREA EMERGENCY ALERT SITE AREA EMERGENCY

GRAND GULF NUCLEAR STATION 10-s-01-1 Attachment I EMERGENCY PLAN PROCEDURE Revision 111 Page 14 of 25 CATEGORY

9. Control Room Evacuation

10. Fire EMERGENCY CLASSIFICATIONS INITIATING CONDITION

1. Evacuation of the Control Room and -

Control established at the xemote shutdown panel 2. Evacuation of the Control Room and -

Control not established at the remote shutdown panel within 15 minutes

1. Fire lasting > 10 minutes after discovery 2. Fire potentially affects safety sys tems 3. Fire compromising the functions of ESF Systems EMERGENCY ACTION LEVEL 2. Control Room evacuated and 2. Control of shutdown systems established at the remote shutdown panel

1. Control Room evacuated and -

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

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

1. A fire defeating ONE safety system electrical division

1. A fire defeating THAN ONE safety system electrical division EMERGENCY CLASSIFICATION AL.ERT SITE AREA EMERGENCY SITE AREA EMERGENCY

GRAND GULF NUCLEAR STATION 10-s-01-1 Attachment I CATEGORY Revision 111 Page 15 of 25

11. Plant shut down Function APRM - Average EbfBRGEWCY CLASSIFICATIONS INITIATING CONDITION

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

2. Failure o f the Reactor Protection System to initiate and complete a scram which brings the reactor subcritical

?ower Range Monitor EMERGENCY ACTION LEVEL L. All control rods fully inserted and -

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

1. Scram conditions conf irmed and 2a.

2b.

More than one rod is greater than position 02 or rod position is unknown or more than one rod and -

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)

EMERGENCY

'LASS I FICATION ALERT

GRAND GULF NUCLEAR STATION 10-5-01-1 Attachment I Revision 111 Page 16 of 25 EMERGENCY CLASSIFICATIONS CATEGORY

11. Plant Shutdown INITIATING CONDITION 3.

Complete loss of functions needed for 4. Transient requiring operation of shutdown systems with failure to scram and continued power generation EMERGENCY ACTION LEVEL

1. HPCS and RCIC not functional and 2. Not able to -

depressurize with SRVs 3. Main Condenser is not avai 1 ab 1 e

1. scram conditions confirmed and -

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

3. Reactor power 24% on APRM EMERGENCY CLASSIFICATION SITE AREA EMERGENCY

GRAND GULF NUCLEAR STATION 10 -s 1 Attachment I CATEGORY Revision 111 Page 17 of 25 12.Abnormal In-plant Radiation/

Airborne Contam-ination Levels

13. Fuel Handling Ac cideat EMERGENCY CLASSIFICATIONS INITIATING CONDITION

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

1. Fuel. damage accident with release of radioactivity to Containment or Auxiliary Building 2. Major damage to spent fuel assembly in Containment or Auxiliary Building dr Monitor EMERGENCY ACTION LEVEL L. Verification of area radiation monitor reading > 1000 times s etpoint Verification of CAM reading >lo00 times setpoint

1. Notification o f a spent fuel damaging accident and 2. High high radiation alarms on either

a. Fuel handling vent exhaust

b. Containment vent exhaust 1.a. Notification of a spent fuel damaging accident or

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

and (Cont inued 1

- EMERGENCY

LASS I FI CATION ALERT ALERT SITE m E A EMERGENCY

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

Title:

Offsite Emergency Response Description of Proposed Change Revision 10:

Updates procedure references. 01-SO-04-21 procedure TQ-110.

a Corrects names of the Vicksburg hospitals Vicksburg Medical Center and Parkview Med No.: 10-S-01-26 Revision: 10 Safety Evaluation was cancelled and replaced by

~~

SCREENING 0 50.59 EVALUATION EXEMPTION listed in the procedure.

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

Sections I, rI, III, and rv required Sections I, IT, 1x1, IV, and V required Changes the GGNS restricted area to protected area for consistent Changes the Health Physic8 Department name to Radiation Protection.

e Changes Radiologically Controlled Area to Controlled Access Area.

definition use.

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..

required.

R e v i e w.

No further 50.59 Review is If none of the criteria is applicable, continue with the 50.59 CJ 0

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

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: 50,59 Review is required, check the applicable review(s):

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

50.59 EVALUATION (#:

f Sections I, XI, 111, XV, and VI required

Title:

Offsite Emergency Response Preparer:

Richard Van Den Akker

- /EOI/NSA-EP/ 6- /6-d3 Name (print) / Signam@ / Company / Department / Date No.: 10-S-01-26 Revision: 10 Safety kra lua t ion 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 operating License TS YES NO CHANGE # and/or SECTIONS IMPACTED n

a I

p

~

~-

a m

- -~

I YES I No i LBDS controlled under 50.59 NRC Orders o

m C H m G E # (if applicable1 and/or SECTIONS IMPACTED

-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 TS Bases Technical Requirements Core Operating Limits NRC safety Evaluation Reports Manual Report a

m D B I u t a u

m c

1 w

LBDs controlled under Y E S other regulations Quality Assurance Program C

l m

Emergency Plan2 I J H Manual2 Fire Protection Program3 C l E l (includes the Fire? Hazards Analysis) offsite D o s e Calculations o

m Manual NO CHANGE # (if applicable) and/or SECTIONS IMPACTED

Title:

Offsite Emergency Response No.: 10-5-01-26 3. Does the proposed activity potentially impact equipment, Yes procedures, or facilities utilized or storing spent fuel at an No (Check "N/Arf i f d r y fuel 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 EOI 10CFR50.59 Review Program Guidelines. )

Independent Spent Fuel Storage Installation?

la N/A Revision: 10 Safety Evaluation B. 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 ox does not 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.

5.6.6 for guidance.)

See EOI 5 0. 5 9 Guidelines Section 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 Gulf 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.

s i t e Licensing department.

If you have any questions, contact your LBDs/Documents reviewed via keyword Keywords:

search:

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

LBDs/Documents reviewed manually:

Emergency Plan 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 I No EOI 10CFR50.59 Program Review Guidelines.)

If Y e s, I list the required changes.

Title:

Offsite Emergency Response No.: 10-S-01-26 111. 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.

Revision:

20 Safety Evaluation Will the proposed Change being evaluated:

1.

2.

3.

4.

5.

6.

7.

8.

9.

10.

11.

12.

13.

14.

15.

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)?

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

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

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

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

Discharge any chemicals new or different from that previously discharged?

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

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

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?

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

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

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

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

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

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

I 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 -

NO 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)?

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

3.

0 E l

4.

E l 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.

E l 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 pro posed 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

Title:

Offsite Emergency

Response

EMERGENCY PLAN PROCEDURE NO.: 10-5-01-26 Revision: 10 Page: i Department C r o s s - D i s c i p l i n e Reviews Needed 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 Signoff (signed, electronic, telcont P r e p a r e r Initials>>>

.- Name FSAR 10CFR19.12 GGCR-1997-0635-00 Paraqraph Number That Implements Requirement 9B 2.1.7 6.5 Note 52 6.4.3 Does this directive contain Tech Spec Triggers? ( ) YES Kl NO REQUIREXEHTS CROSS-REFERENCE LXST

[Requirement Implemented by Directive 1 Directive Paragraph Number 1

1 f

Covered by d i r e c t i v e as a whale o r by various paragraphs 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-04-21 was cancelled and replace by procedure 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 Area.

TQ-3.10.

I EP-305 REV. NO. 0 Page of 2 I

QUALITY RELATED lNFORMAliON USE I

NUCLEAR MANAGEMENT MANUAL ProcedureDocument Number: 10-S-01-26 Document

Title:

Offsite Emergency Response I Proc./Doc. Revision: 10 ATTACHMENT 9.1 1 OCFR50.54(a) SCREENING

1.

DOCUMENT XMFORMATION 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 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,

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

Response

1.0 PURPOSE 1.1 Provide instructions to Offsite Emergency Personnel who are requested to 1.2 Provide instructions for the control of emergency vehicles reporting to the report to the site during a GGNS emergency.

site during a GGNS emergency.

2.0 BE SPONSIBILITIES 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 NO.: 10-S-01-26 Revision: 10 Page: 1 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

Response

Revision: 10 Page: 2 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.

b.

C.

a, 6.4 Site Access Follow the directional arrows and instructions uDon entrv into the Protected Area (when thev are dislslaved).

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.

Adhere the FRISKING requirements as established.

OSC Coordinator may furnish additional instructions/

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

6.4.1 Persons who enter the GGNS Protected Area to support: an emergency 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 I

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.

manner consistent with GGNS procedures, for radiological exposure comensurate with the expected hazards which they may encounter during performance of their duties.

6.4.4 When on GGNS property, offsite persomel will be monitored, i n a 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 T i t l e :

O f f s i t e Emergency NO.: 10-5-01-26 Revision: 10

Response

Page: 4 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.

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.

c.

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 dulance crews transporting contaminated individuals. This dosimetry is collected by the person accompanying the dulance 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

1.

2.

3.

4.

5.

6.

7.

8.

9.

10.

11.

12 I

13.

24.

15.

VISZTOR S 1 OCFRlS INDOCTRIUATION Inform your employer of previous or concurrent radiation exposure.

Obey stop work and evacuation orders of Radiation Protection personnel.

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

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

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

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

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

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.

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

Do not loiter in Controlled Access Areas.

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

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.

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

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 Dos imetrv immed iatelv.

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 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.

I I

REM/OSC HP Coord. Initial Visitor Name/Signature Date Visitor SSN Organization

/

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

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