Text

Changes to Emergency Plan Implementing Procedures - December 2002
	ML023450136
Person / Time
Site:	Grand Gulf
Issue date:	12/05/2002
From:	Bottemiller C; Entergy Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	-RFPFR, GNRO-2002/00097
	Download: ML023450136 (60)
	v • d • e

Waterloo Road P.0, Box 756 Porl Gibson, MS 39150 Tel 601 437 6299 Manager Plant Licensing December 5 , 2002 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk

Subject:

Changes to Emergency Plan Implementing Procedures-December 2002 Grand Gulf Nuclear Station Docket No. 50-416 License No. NPF-29 GNRO-2002/00097 Ladies & Gentlemen:

Entergy Operations, Inc. submits in accordance with 10CFR50 Appendix E, Section V changes to the following Emergency Plan Implementing Procedure 10-S-01-12 Rev. 30 10-S-01-17 Rev. 15 This letter does contain any commitments.

Yours truly, CABIMJ L/jeo attachment: 1. 10-S-01-12 Rev. 30

2. 10-S-01-17 Rev. 15 cc: (See Next Page)

December 05,2002 GNRO-2002/00097 Page 2 of 2 cc:

Hoeg T. L. (GGNS Senior Resident) (w/a)

Levanway D. E. (Wise Carter) (wla)

Reynolds N. S. (w/a)

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

Thomas H. L. (w/o)

U.S. Nuclear Regulatory Commission ATTN: Mr. E. W. Merschoff (w/2)

Regional Administrator, Region IV 61 1 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 U S . Nuclear Regulatory Commission ATTN: Mr. David H. Jaffe NRR/DLPM (w/2)

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

PLANT OPERATIONS KABUAL Volume 10 10-s-01-12 section 01 Revision: 30 Date: 11/22/02 EMERGENCY PLAN PROCEDURE RADIOLOGICAL ASSESSMENT AND PROTECTIVE ACTION RECOMMENDATIONS SAFETY RELATED concurred:

L/'

List of Effective Pages:

Pages 1-12 Attachments I-V List of TCNs Incorporated:

Revision TCN 1-4 None 5 1 6-10 None 11 2 12 3t4 13 -15 None 16 5 17-30 None

Ic EN-S NUCLEAR QUALITYRELATED LI-101 Revision 2 MANAGEMENT ADMINISTRATIVE tw@ MANUAL INFORMATION USE ATTACHMENT 9.1 50.59 REVIEW FORM Page 1 of 5 I. OVERVIEW / SIGNATURES Facility: GGNS Document Reviewed: 10-S-01-12RadioloaicalAssessment and ProtectiveAction Recommendations ChangelRev. 30 System Designator(s)/Description: N/A Description of Proposed Chanse Clarifies use of Protected Area Fence and Site Boundary.

0 Grammatical changes.

Reorders Sections 2,3, and 5 alphabetically.

Added references to 10-S-01-1and EPA-400.

Added definitions of PAR and PAR change.

Revises 6.1.7 for clarity and to more clearly meet commitments.

Adds Section 6.2.2 to discuss ad-hoc PARSfor > l o miles 0 Adds Section 6.2.4 to more clearly define when each PAR is required Added Attachment I, 2.1 Note to clarify RX Shutdown datehime to be determined by the Emergency DirectorlOffsite Emergency Coordinator (CR-GGN-2002-0238 CA3).

Added Att l2.3.3.f NOTE to include only Iodine cartridge results when using Air Sample calculations (EPATS 1423).

Adds Attachment V -Wind Shift Example, to address CR-GGN-2002-0236.

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.

CI The proposed activity is editoriaMypographica1 as defined in Section 5.2.2.1.

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).

t3 The proposed activity is controlled by another regulation per Section 5.2.2.3.

El SCREENING Sections I,II, and Ill required

~ I 50.59 EVALUATION EXEMPTION I Sections I, 11, Ill,and IV required I I 13 I 50.59 EVALUATION (#: ) I Sections I, II, Ill, and V required I Preparer: Richard Sumrall /

Name (print) / Sig Reviewer: &~kwd V a l ~ D f Name (print) / Sig OSRC: N/A Chairmans Name (print) / Signature/ Date

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

List of AssistingKontributing Personnel:

Name: Scope of Assistance:

-Billy Middleton -Evaluate changes against Security Plan-

EN-S NUCLEAR QUALITY RELATED LI-101 Revision 2 MANAGEMENT ADMINISTRATIVE tef;tzy MANUAL 1NFORMATlON USE ATTACHMENT 9.1 50.59 REVIEW FORM Page 2 of 5

11. SCREENING A. Licensina Basis Document Review

1. Does the proposed activity impact the facility or a procedure as described in any of the following Licensing Basis Documents? (Check MAfor those documents that are not applicable to the facility.)

r- Operating License I YES I NO I NIA I CHANGE # and/or SECTIONS IMPACTEDp-/

I Ooeratina License I U I B I I 1 TS U B NRC Orders n E 7 0 I I I LBDs controlled under 50.59 1 YES 1 NO 1 N/A I CHANGE # (if aRRlicableland/or SECTIONS IMPACTED 1 FSAR n e TS Bases n e Technical Requirements Manual n E l I t t Core Operating Limits Report n E 7 Offsite Dose Calculations Manual U B NRC Safety Evaluation Reports U B LBDs controlled under other regulations YES NO WA CHANGE # (if applicable) and/or SECTIONS IMPACTED Quality Assurance Program Manualz n E l Emergency Plan2 U B security Plan n E l Fire Protection Program4 n E l 0 (includes the Fire Hazards Analysis)

I I I I If YES, waluatelprocessany changes in accordancewith the appropriate regulation. I

2. Does the proposed activity involve a test or experiment not described in the 0 Yes FSAR? El No If yes, perform an Exemption Review per Section IV perform a 50.59 Evaluation per Section V.

3. Does the proposed activity potentially impact equipment, procedures, or 0 Yes facilities utilized for storing spent fuel at an Independent Spent Fuel Storage No Installation? N/A (Check MA if dry fuel storage is not applicable to the facility.)

ff yes, perform a 72.48 Review in accordance.with NMM Procedure 11-112.

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

If YES, see Section 5.15.

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

The Security Plan is classified as safeguards and can only be reviewed by personnel with the appropriate security clearance. The Preparer should notify the security department of potential changes to the Securii Plan.

IfYES,evaluate the chanae in accordance with the reauirements of the facilitvs Otxratina License Condition. I

EN-S NUCLEAR QUALITY RELATED LI-I 01 Revision 2 MANAGEMENT ADMINISTRATIVE

~-~~~~~ MANUAL INFORMATION USE ATTACHMENT 9.1 50.59REVIEW FORM , Page , 3 ,of 5 ,

B. -Basis (Provide a clear, concise basis for the answers given in the applicable sections above. 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.)

Performed search of online TECHSPECS, UFSAR, QAPM. EMERGENCY PLAN, AND FULFIND for the keywords "reactor shutdown time". PAR, PAR chanae, PAR revision, "Protective Action Recommendation", "revisinn Protective Action Recommendation", "wind shift", "wind". Reviewed all returned hits.

Manuallv reviewed Emergencv Plan Section 6.5. Protective Actions and Table 6-1 Manuallv reviewed EPA-400 Table 2-1. Section 6.5 discusses the minimum standard PAR and evacuation of areas 5-10 miles downwind if PA 400 guidelines are exceeded. E-plan 6.5.1 .b.S8 states "Recommendations are based upon emergency classification and proiected dose to public, and are consistent with EPA Protective Action Guides (PAG's)."

Manuallv reviewed 10CFR50.47.B.10 and 10CFR50.E.IV.B. Both sections discuss that a ranne of protective actions are developed for the plume exposure pathwav and inQestionexposure pathwav.

10CFRSO.E.IV.B states in part "emernencv action levels that are to be used for determining when and what tvpe of protective measures should be considered within and outside the site boundary to protect health and safetv."

The proposed change maintains the current PARs, herein defined as the Standard PAR and Extended PAR, and also adds the ad-hoc PAR for areas outside the 10 mile EPZ. The ad-hoc PAR guidelines are consistent with the 10 mile EPZ PARs and EPA-400 nuidelines. The ad-hoc PAR for areas outside the 10 mile EPZ is not discussed in the Emergencv Plan, as Emergencv Planning efforts are limited to the 10 mile EPZ. The ad-hoc PAR is added to more clearlv indicate the licensee's responsibilitv to issue PARs for protection of the public, even outside the 10 mile EPZ. The ad-hoc PARs are consistent with the PARs of E-plan Table 6-land the PAGs of EPA-400-R92-001 Table 2-1.

The NRC's Position on PAR'S outside the 10 mile EPZ is discussed in the NRC ROP Performance Indicator FAQ documentation. The NRC position is that IOCFR50.47.B.10 and 10CFR50.E.IV.B expect PARs to be issued outside the 10 mile EPZ if determined that these PARs are warranted.

Section 2.3 of the FSAR discusses Meteoroloav, but does not discuss revisinn PARs based on wind direction.

Section 3.3 of the FSAR discusses wind and tornado loadinas and damaae, but does not address revisinn PARs based on wind direction.

Securitv has reviewed the channe and determined that it will not affect the Security Plan.

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-101.1 LBDs/Documents Reviewed: Keywords:

TECHSPECS, UFSAR, QAPM, EMERGENCY "reactor shutdown time", PAR, "Protective Action PLAN, and SER Recommendation".

I EN-S NUCLEAR QUALITYRELATED Ll-101 Revision 2 MANAGEMENT tw ADMINISTRATIVE MANUAL INFORMATION USE ATTACHMENT 9.1 50.59 REVIEW FORM Page 4 of s D. Is the validity of this Review dependent on any other El Yes change? (See Section 5.3.4 of the EOI 10CFR50.59 Program El No Review Guidelines.)

If Yes, list the required changes.

-

EN-S NUCLEAR QUALITY RELATED LI-101 Revision 2 MANAGEMENT ADMlNlSTRATlVE tw MANUAL lNFORMATlONUSE ATTACHMENT 9.1 50.59 REVIEW FORM Page 5 of 5 111. ENVIRONMENTAL SCREENING If any of the following questions is answered "yes," an EnvironmentalReview must be performed in accordance with NMM Procedure EV-115, "Environmental Evaluations," and attached to this 50.59 Review.

Will the proposed Change being evaluated:

Yes -

No cl El 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)?

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

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

a El Increase the amount of thermal heat being dischargedto the river or lake?

a El Increase the concentrationor quantity of chemicals being discharged to the river, lake, or air?

a El Discharge any chemicals new or different from that previously discharged?

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

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

cl El 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?

cl El Modify existing stationary fuel burning equipment (i.e., diesel fuel oil, butane, gasoline, propane, and kerosene)?'

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

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

0 El Involve the installation or modification of a stationary or mobile tank?

0 El Involve the use or storage of oils or chemicals?

cl El Involve burial or placement of any solid wastes in the site area that may effect runoff, surface water, or groundwater?

' See NMM Procedure EV-i 17. "Air Emissions Manaaement Proaram."for auidance in answerina this auestion. I

T i t l e : Radiological NO. : 10-5-01-12 Revision: 30 Page: i Assessment And Protective Action Recommendations I

Preparer Initials>>> I g5 I Requirement Implemented by Directive Directive Paragraph Number Name Paraqraph Number That Implements Requirement GGNS Emer Plan 7.6.1.E.2

GGNS Emer Plan 7.6.l.c.S6 Attachment I GGNS Emer Plan 7.6.l.b.S5 Attachment I GGNS Emer Plan 6.5.l.b.S5,S6,S7 6.2.1 I AECM 84/0397 P2, Para.1 Attachment 11, 6.1.7 GNRO-97/00080 97-09-01.Item4 6.1, Attachment I1 GNR0-97/00113 97-15-03.Item2 5.21, 6.1(Note), 6.1.4, 6.1.7, GNRI-97/00162 GNRI-97/00162 IF1 97-15-03 IF1 97-15-04 Attachment 11, 6.2.4 6.2.4(Note) 6.1 (Note)

I CR-GGN-1999-0656 CA.2 6.4 CR-GGN-2000-1317 CA.12 5.17, 6.1.6 (Note), 6.1.7 (Note)

CR-GGN-2002-0236 CA. 2 Attachment V CR-GGN-2002-0238 CA. 3 Attachment I Section 2.1 (Note)

Covered by directive a5 a whole or by various paragraphs of the directive.

I 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] Yes E] N/A CDBCR #

Title:

Radiological NO.: 10-S-01-12 Revision: 30 Page: ii Assessment And Protective Action Recommendations Current Revision Statement Revision 30:

Clarifies use of "Protected Area Fence" and Site Boundary.

Grammatical changes.

Reorders Sections 2, 3, and 5 alphabetically.

0 Added references to 10-S-01-1and EPA-400.

0 Added definitions of PAR and PAR change.

Revises 6.1.7 for clarity and to more clearly meet commitments.

Adds Section 6 . 2 . 2 to discuss ad-hoc PARS for >lo miles Adds Section 6.2.4 to more clearly define when each PAR is required Added Attachment I, 2.1 Note to clarify RX Shutdown date/time to be determined by the Emergency Director/Offsite Emergency Coordinator (CR-GGN-2002-0238-3).

Added Att I 2.3.3.f NOTE to include only Iodine cartridge results when using Air Sample calculations (EPATS 1423).

Adds Attachment V - Wind Shift Example, to address CR-GGN-2002-0236.

Title:

Radiological NO. : 10-S-01-12 Revision: 30 Emergency Assessment And Protective Action Plan Recommendations Evaluation 10CFR50.54 (9) SCREENING

1. DOCUMENT INFORMATION Procedure/Document Number: 10-5-01-12 I Proc./Doc. Revision: 30 Document

Title:

Radiological Assessment And Protective Action Recommendations Brief Description of Proposed Revision:

0 Clarifies use of "Protected Area Fence" and Site Boundary.

0 Grammatical changes.

0 Reorders Sections 2, 3, and 5 alphabetically.

0 Added references to 10-S-01-1 and EPA-400.

0 Added definitions of PAR and PAR change.

0 Revises 6.1.7 for clarity and to more clearly meet commitments.

Adds Section 6.2.2 to discuss ad-hoc PARS for >lo miles 0 Adds Section 6.2.4 to more clearly define when each PAR is required 0 Added Attachment I, 2.1 Note to clarify RX Shutdown date/time to be determined by the Emergency Director/Offsite Emergency Coordinator (CR-GGN-2002-0238CA3).

0 Added Att I 2 . 3 . 3 . f NOTE to include only Iodine cartridge results when using Air Sample calculations (EPATS 1423) .

0 Adds Attachment V - Wind Shift Example, to address CR-GGN-2002-0236.

2. SCREENING l -

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

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

- Yes No I If the answer to either question is YES, then a 50.54(q) evaluation must be Derformed.

3. APPROVAL Screening Completed By: 7/.r/. 2 Si$na ture .Date Screening Reviewed By:

J:\ADM-SRVS\TECH~PuB\REVISION\lO\lOSOll2.DOC

Title:

Radiological Assessment No.: 10-5-01-12 Revision: 30 Page: 1 and Protective Action Recommendations 1.0 PURPOSE AND DISCUSSION 1.1 PURPOSE 1.1.1 To provide guidance for performing Radiological Assessment during emergencies.

1.1.2 Guidance is provided for:

a. Assessment of radiological release conditions.

b. Use of radiological data from effluent monitors (ERFIS),

Containment ARMS, and Radiological Monitoring Teams in the estimates of offsite doses.

c. Use of actual, and estimation of, meteorological conditions and their application to the estimates of offsite doses.

d. Application of projected dose to Protective Action Guides and subsequent Protective Action Recommendations.

e. Recognizing radiological conditions that require notification of the State Radiological Assessment Officer 1.1.3 To provide instructions for performing offsite dose projections with the DOSECALC Dose Projection Model.

1.2 DISCUSSION

-NOTE Dose projections are performed in the TSC until the EOF is operational, then the projections are performed in the EOF. If the EOF cannot perform the projections, the projections may be performed in the TSC, Backup EOF, Clean Chemistry Lab, Admin Building Chemistry Area, or in the Control Room. (DOSECALC PDS workstations are available at each of these locations) 2.0 RESPONSIBILITIES 2.1 Emergency Director (ED)/Offsite Emerqency Coordinator (OEC)- Is responsible I for implementing this procedure.

2.2 Radiation Emergency Manager (REM) - Is responsible for Radiological I Assessment, after the EOF is operational.

2.3 Radiation Protection Manaqer (RPM) - Is responsible for Radiological I Assessment, after the TSC is operational.

2.4 Radioloqical Assessment Coordinator (RAC) - Coordinating Offsite Dose I Calculations and Radiological data acquisition, in the EOF.

2.5 Radiological Assessment Dose Calculator - Perform offsite dose calculations using this procedure.

Title:

Radiological Assessment No.: 10-S-01-12 Revision: 30 Page: 2 and Protective Action Recommendations

3.0 REFERENCES

3.1 01-S-08-11, Radioactive Discharge Controls 3.2 06-CH-SG17-0-0045, Radwaste Release Post-Release Calculations I 3.3 06-CH-SP41-0-0036, Standby Service Water Post-Release Calculations 3.4 08-S-04-218, Radiological Effluent Tracking and Dose Assessment User's Guide 3.5 08-S-04-220, Ventilation Exhaust Gaseous Monitoring Systems' Operation 3.6 10-5-01-1, Activation of the Emergency Plan 3.7 DOSECALC Users Manual 3.8 EPA 400, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 3.9 GGNS Emergency Plan 4.0 ATTACHMENTS 4.1 Attachment I - DOSECALC Instructions and Information 4.2 Attachment I1 - SRAO Trigger Points 4.3 Attachment I11 - Met Instrument Determination 4.4 Attachment IV - Stability Class Determination 4.5 Attachment V - Wind Shift Examples 5.0 DEFINITIONS 5.1 &XJ - Eberline Accident Range Effluent Monitor 5.2 -

BOP - Balance of Plant Computer 5.3 -

AT - Delta temperature (use 33 ft and 162 ft MET tower temperature sensor data in Fo) 5.4 DOSECALC - A computer based mathematical model that predicts radiation doses at fixed points based on static weather conditions.

5.5 DOWNWIND - An area located beyond a fixed point in the same direction the wind is blowing. The area covers three sectors, the sector containing the plume centerline, and the two adjacent sectors. If the plume centerline is on a sector line, four sectors are used until the three-sector criteria can be identified.

5.6 EOF - Emergency Operations Facility 5.7 -

EPZ - Emergency Planning Zone 5.8 ERFIS - Emergency Response Facility Information System 5.9 -

GE - General Electric Normal Range Effluent Monitor

Title:

Radiological Assessment No.: 10-S-01-12 Revision: 30 Page: 3 and Protective Action Recommendations 5.10 MET - Meteorological 5.11 pAG - Protective Action Guide (EPA-400 Table 2.1) 5.12 pAR - Protective Action Recommendation 5.13 PAR chanae - any PAR after the PAR associated with the General Emergency declaration that recommends an action be implemented for a population that is different from any previously recommended action.

5.14 PDS - Plant Display System Computer 5.15 Q - Source material release rate in Ci/sec 5.16 Radioloaical release - a release of uncontained gaseous or liquid radiological material to the environment outside of the Site Boundary where:

a. an offsite dose projection exceeds the gaseous radiological material SRAO Trigger Point (21 mRem TEDE or Thyroid CDE), or

b. liquid samples performed per Chemistry procedure 06-CH-SG17-0-0045 or 06-CH-SP41-0-0036 indicate release of radioactive material above the Abnormal Effluent, LIQUID, EALs o f 10-S-01-1 5.17 E M - Radiation Emergency Manager 5.18 fQ&J - Radiation Protection Manager 5.19 - Standard deviation of wind direction in angular degrees 5.20 - Site Boundary - For emergency dose calculations, the site boundary is fixed at 696m (.43 miles) from the center of the reactor.

5.21 SPDS - Safety Parameter Display System 5.22 SPING - Eberline Normal Range Effluent Monitor 5.23 SRAO - State Radiological Assessment Officer 5.24 TSC - Technical Support Center 5.25 UFSAR - Updated Final Safety Analysis Report 5.26 USEPA - United States Environmental Protection Agency 5.27 X - Airborne activity concentration in Ci/m3 or pCi/cm3 or pCi/ml 5.28 &Q - Atmospheric dispersion factor in sec/m3

Title:

Radiological Assessment No.: 10-S-01-12 Revision: 30 Page: 4 and Protective Action Recommendations 6.0 DETAILS 6.1 Radiological Assessment Process CAUTION THIS PROCEDURE MAKES THE ASSUMPTION THAT ALL CALCULATIONS ARE PERFORMED USING ACTUAL RADIOLOGICAL DATA.

CONTINUOUS ASSESSMENT OF PLANT CONDITIONS SHALL BE PERFORMED TO ASCERTAIN IF A RELEASE IS IN PROGRESS.

NOTE DOSECALC decays all isotopes from time of shutdown to time of release, then decays the isotopes from time of release to time of arrival at the projection distances - SB, 2mi, 5mi, lomi, 15mi, and 20 mi.

DOSECALC assumes iodine removal of 99.825% for material released from a SBGT vent or filtered releases.

DOSECALC uses 696m (.43 miles) for the Site Boundary in all directions.

If DOSECALC is not receiving data from the PDS computer, a DOSECALC Data Sheet (EPP 12-03) should be used for data collection to aid performing a dose calculation.

Information required to complete EPP 12-03 may be obtained from PDS Workstations, Status Boards, Plant Staff or other sources as directed by the RPM/REM.

Unless the release duration is known, 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months should be used as the default release duration when estimating the projected exposure.

Although the use of a 2-hour release duration addresses only future or projected dose, integrated dose (dose already received plus dose projected) should be considered when making protective action recommendations. The addition of dose results at various times or the use of the "future dose1sfield of DOSECALC may be used to obtain these results. When using the "future dose" field of DOSECALC, care should be exhibited to ensure the release rates and meteorological conditions are representative of those conditions exhibited during the release duration period.

Radiological Assessment Guides - RA-1 and RA-lB (EPP 1 2 - 0 2 ) are normally provided via color flow charts as an aid to follow this procedure. The procedure text takes precedence over the guides in all cases where inconsistencies in interpretations may arise.

J:\ADM-SRVS\TECH~PvB\REVISION\lO\lOSOll2.DOC

Title:

Radiological Assessment No.: 10-S-01-12 Revision: 30 Page: 5 and Protective Action

- Recommendations 6.1 (Cont.)

USING the Radiological Assessment Flowchart RA-1 and RA-1B (EPP 12-02) as a guide, perform the following:

6.1.1 Determine the correct ISOTOPIC mixture.

6.1.2 Determine when (if) the Rx was (is) shutdown.

6.1.3 Get appropriate current MET DATA.(see section 6.3 for details) 6.1.4 Monitor Release Pathways as follows:

a. Using PDS data or Eberline data, monitor the following gaseous release pathways (check for flow and radiation levels) :

I CAUTION Do not select any effluent monitor that contains negative numbers. Negative numbers dilute the estimated release rate.

(1) Containment Vent (2) Fuel Handling Area Vent (3) Turbine Building Vent (4) Radwaste Building Vent (5) Standby Gas Treatment A & B Vent (6) Any other release path such as major doors, holes, piping, roof hatches and blow out panels. (Ask an SRO or Engineer in the facility).

AND

b. Monitor radiation levels in containment.

(1) Containment Data - ERFIS OP Guide or Control Room Display or Inplant teams.

AND IF CONDITIONS WARRANT C. Monitor radiation levels within the Protected Area.

(1) Within Protected Area - onsite or offsite monitoring teams. (Contact Control Room ED if TSC/EOF/OSC not operational, TSC-RPM or EOF-RAC if TSC/EOF/OSC are operational) .

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE

Title:

Radiological Assessment I No.: 10-S-01-12I Revision: 30 ]Page: 6 I and Protective Action Recommendations 6.1.4 (Cont.)

d. Monitor radiation levels outside the Protected Area.

(1) Offsite monitoring team data. (Contact Control Room ED if TSC/EOF/OSC not operational, TSC-RPM or EOF-RAC if TSC/EOF/OSC are operational).

6.1.5 Determine the expected release duration.

6.1.6 Input the data into the DOSECALC program.

P;IOTE If a gaseous/particulate radiological release is in progress, input the DATE/TIME OF RELEASE START. (DATE/TIME OF RELEASE is left blank for liquid releases) 6.1.7 Evaluate DOSECALC results NOTE Emergency Notification Form is Form EPP 06-01.

SRAO Phone Numbers are in the Emergency Telephone Book.

If the SRAO Trigger Point of gaseous radiological release 21 mR at Site Boundary is exceeded DATE/TIME OF RELEASE START is not included, enter DATE/TIME OF RELEASE START and re-perform assessment.

I I

a. The TSC RPM or EOF REM will verbally contact the SRAO at least hourly to assure a common understanding and knowledge of radiological and plant conditions so that appropriate protective actions may be recommended and implemented.

b. IF no SRAO Trigger Points(Attachment 11) are met, THEN go to 6.1.8.

c. IF any SRAO Trigger Point (Attachment 11) is met AND a new PAR or PAR change is not indicated as outlined in 6 . 2 , THEN:

(1) Inform the Emergency Director/Offsite Emergency Coordinator, and (2) contact the SRAO sooner than hourly, and (3) include the SRAO Trigger Point information on the next Emergency Notification Form.

Title:

Radiological Assessment No.: 10-S-01-12 Revision: 30 Page: 7 and Protective Action Recommendations 6.1.7 (Cont'd)

d. IF any SRAO Trigger Point(s) (Attachment 11) is met AND a new PAR or PAR change indicated as outlined in 6.2, THEN:

Inform the Emergency Director/Offsite Emergency Coordinator, and Develop the 10 mile EPZ PAR within 15 minutes of the data becoming available, and PAR development based on plant parameters should not be delayed awaiting confirmatory field surveys.

Initiate an Emergency Notification Form to include the indicated Protective Action Recommendation for the 10 mile EPZ, and If applicable, expeditiously develop the ad-hoc PAR for areas outside the 10 mile EPZ. and If applicable, initiate an Emergency Notification Form to include the indicated Protective Action Recommendation for areas outside the 10 mile EPZ, and Development of 10 mile EPZ PARs should not be delayed to develop the ad-hoc PAR for areas outside the 10 mile EPZ. Ad-hoc PARs may be included on the 10 mile EPZ Emergency Notification or may be issued subsequently.

Contact the SRAO within 3 0 minutes of issuing the PAR Notification to ensure mutual understanding of the basis for the PAR and ascertain status of the PAR implementation.

6.1.8 Go back to 6.1.1 and continue assessment.

Title:

Radiological Assessment No.: 10-5-01-12 Revision: 30 Page: 8 and Protective Action Recommendations 6.2 Protective Actions 6.2.1 Protective actions within the 10 mile EPZ shall be recommended as follows: I Condition Protective Action Recommendation j_-____ {STANDARD PAR)

EVACUATE: 2 Miles All Sectors and EVACUATE: 5 Miles in Downwind Sectors and

~

SHELTER: Remainder of 10 Mile Emergency Planning Zone (EPZ)

(EXTENDED PAR)

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

and at 2 5 miles corresponds to SHELTER: Remainder of 10 Mile Emergency 1000 mRem TEDE Planning Zone (EPZ)

II or 5000 mRem Thyroid CDE

Title:

Radiological Assessment No.: 10-5-01-12 Revision: 30 Page: 9 and Protective Action Recommendations 6.2.2 Protective Action Recommendations for areas outside the 10 mile EPZ :

a. Predetermined Protective Action Recommendations for areas outside the lO-mile Emergency Planning Zone (EPZ) have not been established.

b. IF

___ dose projections or field measurements correspond to

>lo00 mRem TEDE or ~ 5 0 0 0mRem Thyroid CDE at 310 miles, THEN ad-hoc Protective Action Recommendations for affected areas outside of the 10 mile EPZ shall be developed and recommended.

C. Ad-hoe PARs will encompass at least the Extended PAR of 6.2.1.

(1) The Extended PAR portion of the ad-hoc PAR will be developed and communicated within the standard 15 minute criterias for PAR development and Emergency Notifications.

(2) PARs for areas outside of the 10 mile EPZ may be developed and communicated in conjunction with or after developing and communicating the Extended PAR for the 10 mile EPZ.

(3) Ad-hoc PARs should be developed expeditiously, however the 15 minute criteria does not apply to developing PARs for areas outside the 10 mile EPZ.

d. Ad-hoc PARs extend to appropriate distances outside the 10 mile EPZ and encompass appropriate areas as determined by the Lead Radiological Assessment staff.

e. Dose assessment software may provide technical grounds for development of ad-hoc PARs.

f. State agency representatives in the EOF should be consulted for development of the ad-hoc PARs at the discretion of the Lead Radiological Assessment staff.

6.2.3 Revising Protective Action Recommendations

a. Dose projections are to be reviewed frequently and updated based on changing conditions such as:

(1) Site meteorological parameters and stability class (2) Source terms (3) Radiological field monitoring team data (41 Expected Release Duration

Title:

Radiological Assessment No.: 10-5-01-12 Revision: 30 Page: 10 and Protective Action Recommendations 6.2.4 Indicated PARs, Sectors, and Distances

a. The Extended PAR of 6.2.1 are indicated AND the ad-hoc PARs of 6.2.2 are indicated IF:

(1) dose projections correspond to ~ 1 0 0 0mRem TEDE at 210 miles, OR (2) field measurements correspond to 21000 mRem TEDE at 510 miles, OR (3) dose projections correspond to 25000 mRem CDE Thyroid at

>lo

- miles, OR (41 field measurements correspond to 25000 mRem CDE Thyroid at 2x0 miles

b. The Extended PAR of 6.2.1 is indicated IF:

(1) 6.2.4.a above does g apply, AND (a) dose projections correspond to 21000 mRem TEDE at

>5 miles, (b) field measurements correspond to 21000 mRem TEDE at 2 5 miles, OR (c) dose projections correspond to 2 5 0 0 0 mRem CDE Thyroid at 2 5 miles, (d) field measurements correspond to 25000 mRem CDE Thyroid at 2 5 miles C. The Standard PAR of 6.2.1 is indicated IF :

(1) 6.2.4.b above does NOT apply, (a) dose projections correspond to 21000 mRem TEDE at the Site Boundary (696 meters), - OR (b) field measurements correspond to ~ 1 0 0 0mRem TEDE at the Site Boundary (696 meters),

(c) dose projections correspond to 25000 mRem CDE Thyroid at the Site Boundary (696 meters), OR (d) field measurements correspond to ~ 5 0 0 0mRem CDE Thyroid at the Site Boundary (696 meters)

d. -

IF a previous PAR recommended evacuating a Sector to a prescibed distance, THEN subsequent PARs do not recommend lesser evacuation distances for the Sector. The previous PAR is indicated.

e. -

IF the PAR indicated in 6.2.4.a-d above has previously been issued for the Sectors under consideration, a PAR change is not indicated.

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE

Title:

Radiological Assessment No.: 10-S-01-12 Revision: 30 Page: 11 and Protective Action Recommendations 6.2.4 (Cont. I

f. Indicated PARS should include:

(1) currently affected sectors, AND (2) any sectors the plume has affected since the last Emergency Notification but for which the indicated PAR has not previously been issued NOTE When completing the Emergency Notification Form, each form should represent the current and/or projected radiological, meteorological and plant conditions.

During periods of rapid changes in wind direction, as might be experienced along the leading edge of a weather front, it is important to capture all sectors through which the wind has passed.

In such instances, Section S.B.(Recommended Protective Actions, if applicable) of the Emergency Notification Form should include 6.2.4.f(1) and 6.2.4.f (2) above.

see Attachment V for examples Section 8.B.(Meteorological Data - Sectors Affected) is normally used to annotate only those sectors affected by the current wind direction.

Section 6(Comments) of the Emergency Notification form may be used to explain the reason for the additional sectors or to explain the additional affected sectors if protective action recommendations have not been made.

6.2.5 The RPM/REM must report the results of dose calculations/rad assessment immediately to the Emergency Director/Offsite Emergency Coordinator.

6.3 Meteoroloqical Data 6.3.1 DOSECALC automatically determines appropriate MET DATA based on available instruments and parameters as outlined in Attachment 111.

6.3.2 The parameter used to calculate Stability Class (Delta-Tor Sigma-Theta) and its instrument computer point are indicated in the MET DATA area. The parameter not used for Stability Class displays a question mark ( ? I . In the event both parameters are unavailable (as indicated by question marks in both Delta-T and Sigma-Theta) use Attachment IV to determine Stability Class.

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE

Title:

Radiological Assessment No.: 10-5-01-12 Revision: 30 Page: 12 and Protective Action Recommendations 6.4 Liquid Releases 6.4.1 If a liquid release exceeds EAL 6.1 or 6.2 of 10-S-01-1 (Abnormal Effluents, Liquid), the radiological information from the RETDAS printout or hand calculation is included in Section 6 of the Emergency Notification Form (Incident Description, Update, Comments) .

I NOTE Prior to the declaration of the Emergency, the information that resulted in the declaration is normally supplied by Chemistry to the Shift Manager.

6.4.2 Section 11 and 12 of the Emergency Notification Form are left blank, as they relate to gaseous effluents and do not apply to liquid releases.

6.4.3 To print an Emergency Notification Form, leave the DATEITIME OF RELEASE field in Dosecalc blank. This leaves Sections 9, 10, 11 and 12 of the Emergency Notification Form blank when printing from Dosecalc.

6.4.4 Complete Sections 9 and 10 manually.

6.5 Securing from a Release 6.5.1 After a release is secured, delete the entries in the DATEITIME OF RELEASE field.

6.5.2 Reperform calculations.

6.5.3 Print mergency Notification Form.

6.5.4 Complete Section 9.c manually.

6.5.5 Leave Sections 10, 11, and 12 blank.

6.6 Records and Information 6.6.1 Forms and paperwork generated by this procedure during emergencies are to be retained for information and event reconstruction and submitted to the Manager, Emergency Preparedness to be filed as a Quality Assurance record.

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE 10-s-01-12 Revision: 30 Attachment I Page 1 of 7 DOSECALC INSTRUCTIONS AND INFORMATION In this Instruction Manual, the term %creenl' is meant to convey the window that fills the monitor. The Term ltfunctionalarea" or ltareall is meant to convey an area on a window dedicated to be a specific type of data (e.g. "RELEASE DATA").

1.0 STARTUP When the User approaches the workstation, the screen may be dark due to the screen saver feature.

a. Click anywhere on the screen to bring up the login screen,

b. Enter the login and password displayed on the front of the workstation.

Allow 2-3 minutes f o r PDS to load. PDS is required to be displayed or the workstation to receive plant data.

C After PDS menu is displayed, click in the black screen to access the Root menu.

d On the Root menu, scroll down to DOSECALC to bring up the Dose Calculation program. The Main Screen on the DOSECALC program appears.

2.0 MAIN SCREJ3N The Main screen contains the DOSECALC Data windows. This is the beginning point of DOSECALC and the program returns to this screen after data is entered on data screens. If a data screen is on the monitor, click on the DONE button and it returns to the MAIN screen.

DOSECALC requires specific information to perform a dose calculation. The information is as follows: Wind Speed, Accident Type, Source Term, and when performing a dose calculation based on a field monitoring team reading, Distance and Angle. Written warnings delineating each of the above requirements are at the bottom of the screen. They disappear as each of the required data is entered.

User definable fields have a White background and are for data entry. In user definable fields, the text is either Red or Black. Red text indicates that the user has entered/modified the value displayed. Black text indicates that the program supplies the value displayed. Yellow fields are not user definable and display information for the User's benefit. All text displayed in Yellow fields is Black.

2.1 ACCIDENT DATA AREA This area is in the upper left-hand corner of the MAIN screen. A HELP button is available to the User or an explanation of the area. Click on ISOTOPIC MIX to select the Isotopic Mix desired.

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE 10-5-01-12 DOSECALC INSTRUCTIONS AND INFOF%IATION 2.1 ACCIDENT DATA AREA (Cont. )

NOTE The isotopic mixture defaults to steam cycle mixture.

A window with isotopic fractions comes up and the User is required to select one prior to performing a projection. Determining the appropriate mix may require input from Operations personnel.

For entry of an effluent spectrum (e.g. from an effluent sample) choose the USER DEFINED accident type and a window appears for entry of data.

The entered spectrum is used in the conversion of effluent monitor readings to release rates.

Click on the RX SHUTDOWN DATE/TIME field and enter the date in the following format: mm/dd/yy. Enter the time in the following format:

hh:mm. The DOSECALC Computer normally updates the RX SHUTDOWN and DATEJTIME field automatically for all conditions except during an ATWS.

During an ATWS, a manual entry or deletion of RX Status and shutdown times may be required. Concurrence of the shutdown reactor following an ATWS Condition normally comes from the Emergency Director or Shift Supervisor.

When this is done, move to the MET DATA area.

NOTE When deleting DATE/TIME OF SHUTDOWN data, ensure all characters are deleted (including spaces). Failure to delete all characters results in the ENF "RELEASE IS OCCURRING" checkbox to be checked and ENF Section 12 dose fields to be completed.

RX SHUTDOWN DATE/TIME are automatic inputs from P D S . PDS uses an algorithm to determine if the reactor is shutdown. If the MODE SWITCH is in SHUTDOWN and reactor power i s < 4 % , PDS determines that the reactor is shutdown. The time of shutdown may be different than determined by PDS, especially during an ATWS. The Emergency Director/Offsite Emergency Coordinator may direct that times other than the PDS shutdown time be used. In all cases, the time of shutdown determined by the ED/OEC should be used.

GFSND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE 10-5-01-12 Revision: 30 1

Attachment I Page 3 of 7 DOSECALC INSTRUCTIONS AND INE'ORMATION 2.2 MET DATA AREA A HELP button is available to the User for an explanation of the area.

The area is set to default to the Primary Met tower 10 meter instrumentation. In the event this instrumentation is unavailable, DOSECALC automatically selects appropriate instrumentation based on the flowchart in Attachment 111. The HELP screens and Attachment IV outline the backup method for stability class determination if the MET towers are unavailable.

The HELP button lists the ERFIS computer points for obtaining MET data in the event PDS is not automatically updating DOSECALC.

To enter Met data, click on the fields for wind speed and wind direction.

DOSECALC selects a stability class based on this data. Alternately, a stability class may also be entered manually. However, if the entered stability class differs from the calculated stability class, a warning comes up on the area notifying the User o f the conflict.

NOTE When performing a dose calculation, if there is a change in wind speed, direction, or stability class, an alarm sounds. To acknowledge alarm, click on silence. To remove alarm box from screen, press OK.

After using User Defined data, a return to PDS data can be performed by clicking on the PDS Data button in the Process Monitor Data area. This returns both Process Monitor Data and Met Data to PDS.

After completing this area, move the cursor to the RELEASE DATA area.

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE 10-s-01-12 DOSECALC INSTRUCTIONS ANI) INPORMATION 2.3 RELEASE DATA/MONITOR DATA SCREEN OR WINDOWS A HELP button is available for the User for an explanation of the area.

The release duration field defaults to two hours but may be changed by the User by clicking on the field. The User may select Release to present, future release, or user defined for release duration. If RLS TO PRESENT is selected, the program automatically calculates the Release to present based upon release start time. The User is required to enter numbers for the Future Release and the User Defined.

To select the effluent monitoring data for the release, click on the appropriate button. When the user presses the title button for an area, it turns blue to indicate the values and User selections in that area are to be used during projection calculations.

2.3.1 PROCESS MONITOR DATA AREA This area offers selection of the GGNS effluent monitors as follows :

GE MON-LR SPING-LR CH5 SPING-MR CH7 AXM-HR CH3 AXM-MR cH4 These monitors apply for the GGNS release points which are as follows :

CNTMT VENT TURB BLDG VENT FUEL HNDLG VENT RW BLDG VENT STAND BY GAS A (except GE MON)

STAND BY GAS B (except GE MON)

The Help screen for this window has the complete list of ERFIS computer points of each of these monitor/release points.

The Flow Rate field for each release point may have either the default or PDS value set in the field, but this may be changed by User override.

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE 10-s-01-12 DOSECALC INSTRUCTIONS AND INFORKATION 2.3.1 PROCESS MONITOR DATA AREA (Cont.)

Click on the appropriate monitor button and it changes to red to indicate that the monitor is selected. Click on the field and enter a monitor reading, if necessary. Multiple release points may be selected, but multiple monitors on the same release point may not be selected. Click on the desired release point and the button turns red to indicate it has been selected.

Use of SBGT A or SBGT B monitor release point indicates that SBGT is operational/functional and that the effluent is filtered at 99.825% efficiency for Iodines.

Once these selections are made, click on DONE.

A trend of a selected channel may be reviewed by double-clicking on the right mouse button of the selected channel.

Containment monitors can also be used if process monitors are offscale or inoperable.

After using User Defined data, a return to PDS data can be performed by clicking on the PDS Data button. This returns both Process Monitor Data and Met Data to PDS.

2.3.2 CONTAI- DATA AREA A dose projection may be performed using the Containment Area Monitors. A HELP screen is available to the User. Click on the monitor to be used and then click on the field and enter the monitor reading. Design leakage is default entered in the CTMT LEAK RATE field. The User may select a leak rate by clicking on the Leak Rate Button. To calculate a leakage rate, the User is required to enter area and pressure for the release point. A YES or NO answer is required to be selected for MIX FILTERED (default is YES). A I1YES1lreduces the iodine fraction by 99.825%-. Once those selections are made, click on Done.

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE 10-s-01-12 DOSECALC INSTRUCTIONS AND INFORMATION 2.3.3 FIELD DATA AREA

a. This area is used for dose projections based on field monitoring team data. A HELP screen is available to the Users.

b. Click on the white FIELD DATA button in the RELEASE DATA area.

C. Click on FIELD MAP button.

d. After clicking the FIELD MAP button, an EPZ map appears. Use the scroll bars to move to location of sample. Click on the sample location with the left mouse button. A sample data box appears. The location of the sample is automatically entered.

e. A YES or NO answer is required to be selected for MIX FILTERED (default is YES). A 'lYES1' reduces the iodine fraction by 99.825%.

NOTE

'IYES1*is selected if the release point is through Standby Gas Treatment. If the release is from a release point other than Standby Gas Treatment, llNO1' is selected.

f. Click on the method to be used. If AIR SAMPLE RESULT is chosen by clicking on the button, the User may enter the results of a spectral analysis of a field monitoring team sample. Click twice on the AIR SAMPLE RESULT field and a screen for the air sample results in pCi/cc appears.

Alternately, a gross pCi/cc may entered.

NOTE If gross pCi/cc AIR SAMPLE RESULT is used, only the Iodine charcoal cartridge results are included.

g. After entering results, click OK. The sample results are displayed on the map in a red box.

h. Click on the right mouse button anywhere in the map to return to main screen.

i. Click on the FIELD DATA button to highlight the box (the box turns blue). Click on DONE when complete.

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE 10-s-01-12 DOSECALC INSTRUCTIONS ANI) INFORMATION 2.4 RELEASE DATA AREA (Additional Features)

An option to use the results of an effluent sample is also provided in this area. Click on the NUCLIDE MIX DATA field and a window appears for entry of the spectral data. A help screen is available in this window.

Click on DONE when completed.

The "TIME TO NEXT DOSE CALCULATION" feature is displayed in this area.

Dose calculations are performed every 60 seconds unless the User clicks on HOLD to delay the next dose calculation or on IMMEDIATE to begin the next dose calculation.

2.5 DOSE DATA, PLUME DATA, AND PATEWAY DATA AREA These areas provide the results of the DOSECALC calculation. There is no interaction with the User (the fields are yellow).

Doses are provided in terms of total projected dose from the time of the current projection through the estimated release duration.

When dose calculations are performed, if projections exceed SRAO trigger points or GE limits, an alarm sounds. To acknowledge alarm, click on silence. To remove alarm box from screen, click on OK.

2.6 PRINT/PREVIEW Click on the Preview ENF button, to preview the Emergency Notification Form. The following data is automatically entered:

DATE/ TIME REACTOR SHUTDOWN DATE/TIME MET DATA (except for precipitation)

RELEASE INFORMATION After the form has been reviewed, click on print in the menu bar. To exit ENF Preview, click on EXIT in the menu bar. To print the dose calculation data, click on the PRINT DATA button. The ENF and the raw data have corresponding serial numbers in the upper right corner of printouts.

NOTE The automatic calculation freezes during the ENF preview. To resume calculations, press the RESUME button.

To recall ENF or data sheets, click on the RECALL DATA button. The last ten calculations are stored. Click on the appropriate data to retrieve.

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE 10-5-01-12 1 Revision: 30 Attachment I1 Page 1 of 1 SRAO TRIGGER POINTS RPM/REM shall notify the State Radiological Assessment Officer (SRAO) when any of the following occurs:

Plant conditions exists that indicate possible, potential, or actual Gaseous Radiological release from GGNS 21 mR at Site Boundary (696 m). I Change in wind direction that would shift projected plume centerline into another sector Change of 2 5 mph in wind speed Any change of stability class Any change in emergency classification Change (increase or decrease) of source term/radiological release rate that would result in the following projected doses at the Site Boundary (696 m): 1 TEDE CDE Thyroid 1000 mRem 5000 mRem 2000 mRem 10000 mRem 3000 mRem 15000 mRem 4000 mRem 20000 mRem 5000 mRem 25000 mRem above these levels, change of k 20%

SRAO telephone numbers are in the EMERGENCY TELEPHONE BOOK

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE 10-5-01-12 MET INSTRUMENT DETERMINATION No No second)

No to determine stabirity class Q 10m windspeed and sigma theta available in any combination?

Ye!

Y Use delta-t to determine stability class sigma theta to determine stability class NO theta to determine stability class

(-)

Refer to Attachment IV to determine stability J:\ADM~SRVS\TECH~PUB\REVISION\lO\lOSOll2.DOC

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE 10-5-01-12 STABILITY CLASS DETERMINATION 0~-1 updated (Attlll)

Use ERFIS data to on ERFIS? calculations NO v

Use local data NO V

Call national Weather Service in obtain Wind Speed and Directlon NO Go outside and estimate Wind Speed and DlrecUon by visual observation Wind SDeed Sunliaht at 10m lmDh) Strona Moderate Sliaht

-z or = 4.5 A B B b > 4.56.7 B B C

> 6.7-1 1.2 B C C

> 11.2-13.4 C D D

> 13.4 C D D INPUT METDATA IN DOSECALC Wind So& Cloud Cover at 10m ImDh) >or =1/2 <1/2

<or=4.5 F F No b 4.5-6.7 E F

> 6.7-11.2 D E

> 11.2-13.4 D D

> 13.4 D D

GRKND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE 10-s-01-12 Attachment V Page 1 of 3 WIND SHIFT EXAMPLES NOTE- Examples assume that ad-hoc PARS greater than 10 miles are not indicated and dose calculations are constant.

EXAMPLE 1:

A General Emergency has just been declared and you are preparing the initial ENF for the GE (i.e.-no ENFs previously issued containing PARS). Wind affects only the current sectors (R,A,B).

Actions :

Notify ED/OEC.

Develbp new PAR within 15 minutes.

Issue new ENF within 15 minutes of developing new PAR.

Notify SRAO of Trigger Point.

Section 5b PAR Sectors:

Those sectors currently affected (R,A,B).

EXAMPLE 2:

Previous ENF issued with Sectors R,A,B listed in Section 5b.

Wind now shifts to affect Sectors C,D,E.

Actions :

Notify ED/OEC.

Develop new PAR within 15 minutes.

Issue new ENF within 15 minutes of developing new PAR.

Notify SRAO of Trigger Point.

Section 5b PAR Sectors:

R,A,B previously identified, so only those sectors currently affected (C,D,E).

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE 10-s-01-12 Attachment V Page 2 of 3 WIND SHIFT EXAMPLES EXAMPLE 3:

Previous ENFs issued identifying R,A,B,C,D, & E listed in Section 5b.

Wind now rapidly shifts to affect Sectors G,H,J.

Actions :

Notify ED/OEC.

Develop new PAR within 15 minutes.

Issue new ENF within 15 minutes of developing new PAR.

Notify SRAO of Trigger Point.

Section 5b PAR Sectors:

R,A,B,C,D, & E previously listed, but F was not.

Section 5b should contain those currentlv affected (G,H,J)ANI) those sectors NOT pGeviously identified (Sector F) .

5b should contain F,G,H,J EXAMPLE 4 :

Previous ENFs issued identifying R,A,B,C,D,E,F,G,H,Jlisted in Section 5b.

Wind now shifts back to affect A,B,C.

Actions :

Notify ED/OEC.

Notify SRAO of Trigger Point.

New PAR not required (by definition it is not a PAR change). Include sectors on next periodic update.

Section 5b PAR Sectors:

R,A,B,C,D,E,F,G,H,J previously listed.

Section 5b should contain only those currently affected (A,B,C).

GI?AND GULF NUCLEAR STATION 10-s-01-12 Revision: 30 Attachment V Page 3 of 3 W I N D SHIFT EXAMPLES EXAMPLE 5:

Previous ENFs issued identifying R,A,B,C,D,E,F,G,H,J listed in Section 5b.

Wind now shifts to the boundary line affecting A,B,C,D.

Actions :

Notify ED/OEC.

Notif; SRAO of Trigger Point.

New PAR not required (by definition it is not a PAR change). Include sectors on next periodic update.

Section 5b PAR Sectors:

R,A,B,C,D,E,F,G,H,J previously listed.

Section 5b should contain only those currently affected (A,B,C,D).

PLANT 0PE?IATIONS MABUAL volume 10 10-S-01-17 Section 01 Revision: 15 Date: 11/22/02 EMEZGENCY PLAN PROCEDURE SAFETY RELATED Prepared :

Reviewed :

Concurred:

Manager, Operadons Approved :

Fj2f+nt General Manager Manager, Emdjgency Preparedness List of Effective Pages:

Pages 1-10 Attachments 1-11 List of TCNs Incorporated:

Revision 2xE 0-14 None 15 None

EN-S NUCLEAR QUALITY RELATED LI-101 Revision 2 MANAGEMENT ADMINISTRATIVE

~~~~

MANUAL lNFORMATlONUSE ATTACHMENT 9.1 50.59 REVIEW FORM Page 1 of 6 I. OVERVIEW / SIGNATURES Facility: GGNS Document Reviewed: 10-S-01-17Emergency Personnel Exposure Control Change/Rev. 15 System Designator(s)/Description: N/A

EN-S NUCLEAR QUALITY RELATED Ll-101 Revision 2 MANAGEMENT ADMINISTRATIVE erg)l MANUAL INFORMATION USE ATTACHMENT 9.1 50.59 REVIEW FORM Page 2 of 6 Description of ProDosed Change

1. Reorders Sections 2,3,and 5 alphabeticallyand numerically.

2. Clarifies Section 2.0 responsibility of Emergency DirectorlOffsiteEmergency Coordinator for approving emergency exposure limits.

3. Adds R P M responsibility for ensuring NRC reports of overexposures are completed.

4. Adds reference to 014-06-5, Reportable Events or Conditions

5. Adds reference to Nuclear Management Manual Procedure RP-201, Dosimetry Administration

6. Adds reference to 10-S-01-26, Offsite Emergency Response

7. Adds Attachment 11-Risks Associated With Large Doses of Radiation

8. Removes definitions for CDE, CEDE, EDE, and TEDE which are contained in NMM RP-201,Dosimetry Administration

9. Removes definition for HP

10. Adds definition for RP

11. Adds definition for Offsite Emergency Assistance personnel

12. Revises definition of TLD

13. Adds definition of personal TLD

14. Allows the issuance of emergency TLDS to ERO members if their personnel TLDS are unavailable.

15. Grammatical changes to 6.0 NOTE.

16. Provides for immediate suspension of RP-201administrativelimits and extension approvals. Personnel are immediately administrativelyextended to the 10CFR20 limits upon declaration of an Alert, Site Area Emergency, or General Emergency.

17. -Adds reference to lens dose and organ dose limits.

18. Clarifies 6.1 to request exposure authorization through the E M or RPM as applicable.

19. Editorial changes to consolidate information already in the procedure into section 6.7 to make the procedure easier to use.

20. Clarifies in 6.1.9 that exposure extension authorizationsmay be entered into the log of the person granting the authorizationor their designee.

21. Removes reference to administrative limits in 6.2.1.

22. Section 6.3.7grammatical changes and editorial changes to consolidate information already in the procedure into section 6.7 to make the procedure easier to use.

23. Clarifies in 6.4.1 that EP Form 17-02,Emergency Dose Margin Form, is only used if the EAD system is inoperable.

24. Section 6.4grammatical and editorial changes to consolidate information already in the procedure into section 6.7to make the procedure easier to use.

25. Grammatical changes to Section 6.5.

26. Revises 6.6.1reference of EmergencyVehicle Dosimetry to Offsite Emergency personnel.

27. Adds 6.6.1.dfor the OSC H p Coordinator to ensure that 10-S-01-26 requirements are satisfied.

28. Clarifies 6.6.1.ethat TLDs continue to be worn by the Offsite Emergency personnel.

29. Editorial changes to consolidate information already in the procedure into section 6.7to make the procedure easier to use.

30. Editorial changes to Attachment I.

31. To promote standardization of EOI-SEP processes:

-Provides for immediate suspension of RP-201administrativelimits and extension approvals. Personnel are immediately administrativelyextended to the 10CFR20 limits upon declaration of an Alert, Site Area Emergency, or General Emergency.

-Adds reference to lens dose and organ dose limits.

-Adds NRC conference prior to extending personnel beyond 10CFR20 limits if practicable.

-Clarifies that Emergency Dose is considered to be part of the employeesoccupational dose.

-Adds Notifications and Reports required by 10CFR20.2202and 10CFR20.2203to be performed as outlined in 01-S-06-5.

-Adds Attachment 11- Risks Associated With Large Doses of Radiation

- Adds RPM responsibility for ensuring NRC reports of overexposures are completed.

EN-S NUCLEAR QUALITY RELATED LI-101 Revision 2 MANAGEMENT ADMINISTRATIVE

@??Y MANUAL lNFORMATIONUSE ATTACHMENT 9.1 50.59 REVIEW FORM Page 3 of 6 If the proposed activity, in its entirety, involves any one of the criteria below, check the appropriate box, provide a justification/basis in the Description above, and forward to a Reviewer. No further 50.59 Review is required. If none of the criteria is applicable, continue with the 50.59 Review.

0 The proposed activity is editorialltypographicalas defined in Section 5.2.2.1.

Cl The proposed activity represents an FSAR-onlychange as allowed in Section 5.2.2.2 . (Insert item # from Section 5.2.2.2).

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

El SCREENING Sections I, 11, and I11 required 50.59 EVALUATION EXEMPTION Sections I, 11,111,and IV required Cl 50.59 EVALUATION ( # Sections I, 11,111,and V required Preparer: Richard Sumrall/$ / EOI / EP / 7-22-2002 Name (print) l Signature l Company / Department / Date Name (print) / Signature l Company l Department / Date OSRC: N/A Chairmans Name (print) / Signature l Date

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

List of AssistingKontributhg Personnel:

Name: Scope of Assistance:

Billv Middleton Review of Securitv Plan

EN-S NUCLEAR QUALITY RELATED LI-101 Revision 2 MANAGEMENT ADMINISTRATIVE YY MANUAL iNFORMATlON USE ATTACHMENT 9.1 50.59 REVIEW FORM Page 4 of 6 II. SCREENING A. Licensina Basis Document Review

1. Does the proposed activity impact the facility or a procedure as described in any of the following Licensing Basis Documents? (Check /A for those documents that are not applicable to the facility.)

Operating License YES NO N/A CHANGE # and/or SECTIONS IMPACTED Operating License o m TS u m NRC Orders D E l O LBDs controlled under 50.59 YES NO N/A CHANGE # (ifapplicabie) a d o r SECTIONS IMPACTED FSAR o m TS Bases u m Technical Requirements Manual o m Core Operating Limits Report u m Offsite Dose Calculations Manual D m NRC Safety Evaluation Reports o m perform an Exemption Review per Section IV perform a 50.59 Evaluation per Section V.

LBDs controlled under other redations 1 YES I 1 I NO NIA CHANGE # (if applicable) a d o r SECTIONS IMPACTED Quality Assurance Program Manual2 u m Emergency Plan u m security plan2. 3 o m Fire Protection program4 o m 0 (includes the Fire Hazards Analysis)

If YES, see Section 5.1.5.

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

%he Security Plan is classified as safeguards and can only be reviewed by personnel with the appropriate security clearance. The Preparer should notify the secure department of potential changes to the Security Plan.

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

EN-S NUCLEAR QUALITY RELATED LI-101 Revision 2 MA~AGEMENT ADMINISTRATIVE fer7,3y MANUAL INFORMATION USE ATTACHMENT 9.1 50.59 REVIEW FORM Page 5 of 6 B. -

Bask (Provide a clear, concise basis for the answers given in the applicable sections above. 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.)

An electronic search was conducted on the following Licensing Basis Documents: Technical Specifications, FSAR, COLR, FHA, and Emergency Plan. The search was conducted using the keywords TLD, Dosimetry, Dosimeter, Exposure, OMT, Offsite Monitoring Team, emergency support personnel, exposure extension, exposure, administrative limit, and overexposure. lOCIrR20.2202, lOCIrR20.2203, and 10CFR20.1502 were also reviewed.

Searches revealed that there are requirements to monitor individuals,but nowhere does it say that an emergency TLD or a personal TLD is used, only that a TLD is used (UFSAR 12.5.2.2.3, Emergency Plan 6.7.1).

Emergency Plan 6.7.1 limits Emergency Support Personnel to the GGNS administrative limits, but does not specify what the administrative limit is. Therefore setting the administrative limit equal to the Federal Limit does not represent a change to the Emergency Plan.

This change does not affect when emergency personnel are monitored or what type of monitoring devices are used. This change allows the use of one TLD in place of another, since using a personal TLD will expedite logging in to the EAD system.

Security personnel have verified that these changes will not affect the Security Plan.

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-IOIJ LBDs/Documents Reviewed: Keywords:

FSAR. Technical Specifications. GGNS Emergency TLD. Dosimetrv. Dosimeter, Exposure, OMT. Offsite Plan. 10CFR20.2202, 10CFR20.2203, Monitoring Team. emergency support personnel, lOC~20.1502 exvosure extension, exposure, administrative limit, and overexoosure D. Is the validity of this Review dependent on any other change? Yes (See Section 5.3.4 of the EOI IOCFR50.59 Program Review Guidelines.) No If Yes, list the required changes.

EN-S NUCLEAR QUALITYRELATED LI-101 Revision 2 MANAGEMENT ADMINISTRATIVE

~~~~

MANUAL INFORMATION USE ATTACHMENT 9.1 50.59 REVIEW FORM Page 6 of 6 111. ENVIRONMENTAL SCREENING 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.

Will the proposed

. . Change being evaluated:

No El 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)?

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

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

El Increase t h e amount of thermal heat being discharged to the river or lake?

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

El Discharge any chemicals new or different from that previously discharged?

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

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

El 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?

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

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

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

El Involve the use or storage of oils or chemicals?

El Involve burial or placement of any solid wastes in the site area that may effect runoff, surface water, or groundwater?

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

Title:

Emergency Personnel NO.: 10-S-01-17 Revision: 15 Emergency Plan

Title:

Emergency Personnel NO.: 10-S-01-17 Revision: 15 Emergency Plan Exposure Control Evaluation A.) Does the proposed revision require a change to the Emergency Plan?

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

Y e s -....& No If the answer to either question is YES, then a 5 0 . 5 4 ( q ) evaluation =st be performed.

3. APPROVAL Screening Completed By:

Signature Date Screening Reviewed By:

Signature Date

Title:

Emergency Personnel No.: 10-S-01-17 Revision: 15 Page: i Exposure Control RPTS FORM 10CFRJ0.59 Review Required? I @)Yes I If Yes, attach 50.59 Review Form I ON0 1 Not required per LI-101 Cross-Disciplinereview required? I (X) Yes I (Note affected Departments Below)

I Requirement Implemented by Directive Directive Paragraph Number Name Paragraph Number That Implements Requirement GGNS Emergency Plan 6.7.1.S4.b.sl 6.0 Table 1 GGNS Emergency Plan 6.7.1.54.a 6.8.2 I

Covered by directive as a whole or 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 a

only Yes El N/A CDBCR #

Title:

Emergency Personnel No.: 10-S-01-17 Revision: 15 Page: ii Current Revision Statement Revision 15:

1. Reorders Sections 2,3, and 5 alphabetically and numerically.

2. Clarifies Section 2.0 responsibility of Emergency DirectorlOffsite Emergency Coordinator for approving emergency exposure limits.

3. Adds RPM responsibility for ensuring NRC reports of overexposures are completed.

4. Adds reference to 01-S-06-5,Reportable Events or Conditions

5. Adds reference to Nuclear Management Manual Procedure RP-20 1, Dosimetry Administration

6. Adds reference to 10-S-01-26, Offsite Emergency Response

7. Adds Attachment 11- Risks Associated With Large Doses of Radiation

8. Removes definitions for CDE, CEDE, EDE, and TEDE which are contained in NMM RP-201, Dosimetry Administration

9. Removes definition for HP

10. Adds definition for RP

11. Adds definition for Offsite Emergency Assistance personnel

12. Revises definition of TLD

13. Adds definition of personal TLD

14. Allows the issuance of emergency TLDS to ERO members if their personnel TLDS are unavailable.

15. Grammatical changes to 6.0 NOTE.

16. Provides for immediate suspension of RP-20 1 administrative limits and extension approvals. Personnel are immediately administratively extended to the 1OCFX20limits upon declaration of an Alert, Site Area Emergency, or General Emergency.

17. -Adds reference to lens dose and organ dose limits.

18. Clarifies 6.1 to request exposure authorization through the REM or RPM as applicable.

19. Editorial changes to consolidate information already in the procedure into section 6.7 to make the procedure easier to use.

20. Clarifies in 6.1.9 that exposure extension authorizations may be entered into the log of the person granting the authorization or their designee.

21. Removes reference to administrative limits in 6.2.1.

22. Section 6.3.7 grammatical changes and editorial changes to consolidate information already in the procedure into section 6.7 to make the procedure easier to use.

23. Clarifies in 6.4.1 that EP Form 17-02,Emergency Dose Margin Form, is only used if the EAD system is inoperable.

24. Section 6.4 grammatical and editorial changes to consolidate information already in the procedure into section 6.7 to make the procedure easier to use.

25. Grammatical changes to Section 6.5.

26. Revises 6.6.1 reference of Emergency Vehicle Dosimetry to Offsite Emergency personnel.

27. Adds 6.6.1.d for the OSC HP Coordinator to ensure that 10-S-01-26requirements are satisfied.

28. Clarifies 6.6.1 .e that TLDs continue to be worn by the Offsite Emergency personnel.

29. Editorial changes to consolidate information already in the procedure into section 6.7 to make the procedure easier to use.

30. Editorial changes to Attachment I.

3 1. To promote standardization of EOI-S EP processes:

-Provides for immediate suspension of RP-201 administrative limits and extension approvals. Personnel are immediately administratively extended to the 10CFR20 limits upon declaration of an Alert, Site Area Emergency, or General Emergency.

-Adds reference to lens dose and organ dose limits.

-Adds NRC conference prior to extending personnel beyond 10CFR20 limits if practicable.

-Clarifies that Emergency Dose is considered to be part of the employees occupational dose.

-Adds Notifications and Reports required by 10CFR20.2202 and 10CFR20.2203to be performed as outlined in 01-S-06-5.

-Adds Attachment 11- Risks Associated With Large Doses of Radiation

- Adds RPM responsibility for ensuring NRC reports of overexposures are completed.

Title:

Emergency Personnel No.: 10-5-01-17 Revision: 15 Page: 1 Exposure Control 1.0 PURPOSE AND DISCUSSION 1.1 This procedure provides guidelines for emergency exposure authorization, issuing dosimetry, and RWP access during emergencies.

2.0 RESPONSIBILITIES 2.1 Emeraency Director/Emeraencv ResDonse Facility Coordinator - Ensure that they and personnel under their direction are monitored per this procedure.

I 2.2 Emeraencv Director. Offsite Emeraencv Coordinator - responsible for approving personnel exposures exceeding the limits of 10CFR20.

2.3 GGNS Radiation Protection section - Is responsible for updating the exposure margins for all appropriate GGNS ERO personnel.

2.4 Manaaer. Emeraencv PreDarednesg - Is responsible for ensuring that EOF dosimetry is processed as soon as possible and that the results of the processing are hand-delivered to the GGNS Radiation Protections section.

2.5 Radiation Emeraencv Manacrer - Is responsible for collecting all EOF dosimetry, ensuring that all EOF dosimetry is delivered to the Manager, Emergency Preparedness; and notifying the Radiation Protection Dosimetry section of which (if any) EOF personnel (including OMT personnel) may have received occupational radiation exposure.

2.6 Radiation Protection Manaaer - Is responsible for tracking the dose history for those personnel authorized to receive exposures in excess of 10CFR20 and notifying the NRC of any overexposures. Is responsible for ensuring NRC Notifications and Reports of overexposures are completed as outlined in Ref. 3.2.

3.0 REFERENCES

3.1 01-5-06-5, Reportable Events or Conditions 3 . 2 01-S-08-2, Exposure and Contamination Control 3 . 3 10-S-01-26,Offsite ECmergency Response 3.4 Nuclear Management Manual Procedure RP-201, Dosimetry Administration 3.5 Nuclear Management Manual Procedure TQ-110, Emergency Preparedness Training Program 4.0 ATTACHMENTS 4.1 Attachment I - EOF TLD Locations 4.2 Attachment I1 - Risks Associated with Large Doses of Radiation I

Title:

Emergency Personnel No.: 10-5-01-17 Revision: 15 Page: 2 Exposure Control 5.0 DEFINITIONS 5.1 Accident Ranae Dosimeter - 2 100R 5.2 - Electronic Alarming Dosimeter 5.3 Electronic Dosimeter Svstem - Computer system consisting of electronic dosimeters and dosimeter readers that is used for exposure monitoring at GGNS .

5.4 Emeraencv TLD - A TLD issued to an Emergency Response Organization me&er during a drill or emergency. Usually issued if their personal TLD is unavailable.

5.5 Emeraencv Dosimetrv - TLD and High Range and Accident Range Dosimeters, or TLD and Electronic Alarming Dosimeter 5.6 Emeraencv Personnel - Emergency Response Personnel and Emergency Support Personnel 5.7 Emergencv ResDonse Personnel - GGNS and contractor personnel who are required to respond to an emergency and meet the necessary qualification requirements.

5.8 Emeraencv S u mort Personnel, - GGNS and contractor personnel who are required to respond to support Emergency Response Personnel and their actions during an emergency and have completed the minimum training requirements as per reference 3.5.

5.9 rn - Emergency Operations Facility 5.10 Hiah Ranae Dosimeter - > 1R but < 100R 5.11 HIS Health Physics Information System Computer 5.12 Qffsite Emeraencv Dersonnel - personnel responding to assist emergency efforts that may require training and briefings as outlined in Ref. 3.3. I 5.13 4sc - Operations Support Center 5.14 Personal TLD - TLD's issued to personnel on a permanent basis. I 5.15 m- Radiation Protection technician I 5.16 - Radiation Work Permit 5.17 TLD - Thermoluminescent Dosimetry. For the purposes of this procedure two types of TLD are discussed: Emergency TLD's and Personal TLD's.

5.18 - Technical Support Center

Title:

Emergency Personnel No.: 10-S-01-17 Revision: 15 Page: 3 Exposure Control 6.0 DETAILS NOTE EMERGEXKY DOSE MARGIN TRACKING FORMS (EPP 17-02) are used during emergencies. The forms are completed by the individuals issuing dosimetry only if the Electronic Dosimeter System is not in service, not available, or being used in the power on - power off modes.

Initial Dose Margins for individuals designated as emergency workers must be obtained from Radiation Protection personnel located in the OSC. Maintaining dose margins current is the responsibility of each emergency facility issuing dosimetry.

Normally only those persons in each emergency facility who are leaving the facility and are expected to receive a whole body exposure are issued emergency dosimetry. Surveys or installed area radiation monitors in each facility normally provide adequate radiological controls for all persons remaining in that facility.

Self-Reading dosimeters are read at the frequency specified in the Emergency RWP or at a frequency specified (if appropriate) by the:

Radiation Protection Manager - TSC Radiation Emergency Manager - EOF OSC HP Coordinator - OSC 6.1 Emercrencv Emosure Authorization TABLE 1 POSE LIMITS FOR EMERGENCY WORKERS The following table represents those extensions of administrative exposure limits for which authorization, by the Emergency Director (ED) or Offsite Emergency Coordinator (OEC), shall be obtained prior to the exposure being received:

DOSE LIMITS (TEDE) ACTIVITY CONDITIONS

>5 up to 10 Rem Protecting Valuable Lower dose not Property practicable Life saving or Lower dose not Protection of Large practicable Populations Life saving or Only on a voluntary Protection of Large basis to persons fully Populations aware of the risks involved

Title:

Emergency Personnel No.: 10-S-01-17 Revision: 15 Page: 4 Exposure Control 6.1.1 Workers performing services during emergencies should limit dose to the lens of the eye to three times the listed value and doses to any other organ (including skin and body extremities) to times the listed value.

6.1.2 The administrative limits and extension process of Reference 3.4 are automatically suspended at the declaration of an Alert, Site Area Emergency, or General Emergency.

6.1.3 Emergency Response personnel are administratively extended to the Federal Limits of 10CFR20 at the declaration of an Alert, Site Area Emergency, or General Emergency. Efforts are made to maintain personnel exposures within the limits established by 10CFR20 .

HIS-20 margins are not automatically extended. Manual. reset of exposure margins in HIS-20 or manually resetting EAD setpoints is required by Radiation Protection Personnel.

6.1.4 Each situation in which an individual may receive exposure in excess of Federal Limits must be evaluated with regard to the risk to the individual, protection of valuable property, or protection of other persons.

6.1.5 Those individuals requesting authorization should do so through the appropriate Lead Radiation Protection personnel (REM or RPM),

if possible.

6.1.6 The Lead Radiation Protection personnel present the authorization request to the ED or the OEC.

6.1.7 The ED or OEC considers each request on a case by case basis.

"Blanket" authorizations are not to be considered.

6.1.8 The ED or OEC may either grant authorization or deny authorization (by verbal, facsimile, or written comunication).

6.1.9 All authorization requests, approvals, and denials must be entered into the log of the person requesting the authorization and the person granting the authorization (or designee). Log entry should include the appropriate information to support the authorization decision.

6.2 CONTROL ROOM ENVELOPE EXPOSURE CONTROL (Control Room, TSC, Central Alarm Station, Operator Work Area) I 6.2.1 The Shift Supervisor/Manager/Emergency Director is to ensure that personnel who are leaving the Control Room Envelope and are expected to receive a whole body exposure meet the requirements of section 6.7 of this procedure.

Title:

Emergency Personnel No.: 10-S-01-17 Revision: 15 Page: 5 Exposure Control 6.2.2 The area radiation monitors or habitability surveys in the Control Room Envelope provide monitoring that may be used to determine habitability. Individual issue of emergency dosimetry is not required unless :

a. As specified in Step 6.2.1.

b. Radiation levels exceed ARM setpoint.

6.3 OPERATIONS SUPPORT CENTER EXPOSURE CONTROL 6.3.1 The OSC Coordinator ensures that personnel leaving the OSC and are expected to receive a whole body exposure meet the requirements of section 6.7 of this procedure. The OSC Health Physics (HP) Coordinator assumes the responsibility upon arrival.

NOTE The Daily Dose Margin Report should be in the OSC. This printout is generated by the RP section daily. The age of the data contained on the printout should not exceed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months plus 25%.

6.3.2 Area surveys of the OSC are taken to document radiological conditions in the OSC. A Senior RP must evaluate the results of the surveys to determine habitability and the need for issuing Emergency Dosimetry to all OSC personnel.

6.3.3 Upon activation of the OSC, the on-shift Radiation Protection Supervision ensures that a sufficient number of Electronic Alarming Dosimeters (FADS) are taken from the RP Lab to the OSC.

(A guideline for a sufficient number is approximately 40 EADs.)

6.3.4 Each person assigned to an emergency response team is issued a TLD and an EAD, or a TLD and dosimeters (High Range and Accident Range) .

6.3.5 Personnel leaving the OSC are logged into the Emergency RWP in accordance with section 6.7 of this procedure. I

Title:

Emergency Personnel No.: 10-5-01-17 Revision: 15 Page: 6 6.3.6 Activation of the Electronic Dosimeter System (EDS) is as follows:

NOTE The normal use of the electronic dosimeter system requires the HIS-20 computer system to be operational and in communication I with the EAD reader being used.

a. EAD readers should be "on" and operating at all times.

b. If the EAD readers are not operating in normal mode, use the ED Power program to manually set dose and dose rate alarm setpoints. Setpoints should be set to the RWP setpoints unless determined otherwise by Radiation Protection personnel.

NOTE WHEN USING THE EAD READER TO "POWER ON" OR "POWER" OFF" AN EAD:

The cumulative dose alarm setpoint and the exposure rate setpoint may be set to values that are different than the corresponding setpoints in the Emergency RWP .

6.4 OFFSITE MONITORING TEAM (OMT) EXPOSURE CONTROL The OSC HP Coordinator/EOF Plume Tracker / Senior RP ensures that appropriate emergency dosimetry is issued to each OMT member and verifies that each member meets the requirements of section 6 . 7 of this procedure.

OMT members may bring their personal TLD with them when responding to the EOF.

6.4.1 Obtain dose margin for OMT members by contacting the OSC HP Coordinator or using HIS-20 (if available) and record on Emergency Dose Margin Form (EP Form EPP 17-02). Emergency Dose Margin Tracking Forms are used only if the Electronic Dosimeter System is not in service, or is not available, or is being used in the power on - power off modes. A separate form is filled out for each OMT member.

6.4.2 Obtain dosimetry. In the EOF the dosimetry is normally located at the Habitability Specialist Desk. Issue dosimetry in accordance with section 6.7 of this procedure.

Title:

Emergency Personnel No.: 10-S-01-17 Revision: 15 Page: 7 Exposure Control 6.5 EMERGENCY OPERATIONS FACILITY EXPOSURE CONTROL

&?.cZ!x Occupational exposure monitoring in the EOF is accomplished using posted TLDs distributed throughout the EOF, habitability surveys, and if necessary, individually issued pocket ion chamber dosimetry devices.

At the termination of the Emergency or discretion of the Radiation Emergency Manager (REM), the REM must ensure that EOF posted TLDs, EOF Personnel Monitoring Logs (EOF), Emergency Dose Margin Forms and EOF Habitability Surveys are delivered directly to the Manager, Emergency Preparedness for processing as soon as possible. (EOF posted TLD locations are in Attachment I of this procedure.)

I I 6.5.1 Upon reporting to the EOF and passing through Security, personnel find (or record) their name and Social Security Nwnber on the EOF Personnel Monitoring Log that is posted on the wall near the main entrance to the EOF.

6.5.2 Personnel verify that their SSN is correct and record the date and time of reporting for duty at the EOF under the IN column.

6.5.3 When leaving the EOF, personnel record the date and time of leaving under the OUT column.

6.5.4 The Offsite Emergency Coordinator ensures personnel leaving the EOF and are expected to receive whole body exposure meet the requirements of section 6.7 of this procedure.

Title:

Emergency Personnel No.: 10-S-01-17 Revision: 15 Page: 8 Exposure Control 6.6 OFFSITE EMERGENCY PERSONNEL MONITORING (Entry into the Protected Area) 6.6.1 The following guidelines must be followed for issuance of dosimetry to Offsite Emergency personnel during declared emergencies:

a. Visitor Key Cards with a TLD attached is issued by Security Island personnel. The Visitor Key Cards are issued to personnel responding inside the Protected Area only.

b. The Security Island personnel must notify the OSC Coordinator (if manned) that Offsite Emergency personnel are to enter the Protected Area.

c. The OSC Coordinator, through the Health Physics Coordinator, assigns an EAD to all offsite personnel responding (if necessary) using the ED Power program and the Emergency Dose Margin Tracking Form (EPP Form EPP 17-02). Pocket ion chambers may be issued if determined appropriate by the OSC Health Physics Coordinator.

d. The OSC HP Coordinator ensures requirements of Ref. 3.3 are satisfied. I

e. When the Offsite Emergency personnel leave the Protected Area, the TLDs attached to the issued key cards are removed from the cards and continue to be worn by the Offsite Emergency personnel throughout the emergency.

f. After the incident is terminated, the RP escorting the personnel must collect the dosimetry worn, collect all issuance paperwork, and turn in the paperwork to the OSC HP Coordinator or the Radiation Protection Shift Supervisor.

I 6.7 EXPOSURE CONTROL FOR PERSONNEL LEAVING EMERGENCY FACILITIES 6.7.1 Dose Marains

a. The facility lead, or his designee, ensures that each person leaving the facility and expecting to receive a whole body exposure has a sufficient exposure margin to complete the expected task. This may be done using the HIS-20 terminal or the Daily Dose Margin Report, both of which are available in the OSC.

b. If the person's dose limit is likely to be exceeded, obtain an Exposure Extension Authorization in accordance with section 6.1 of this procedure.

c. EMERGENCY DOSE MARGIN TRACKING FORMS (EPP 17-02) are used during emergencies. The forms are completed by the individuals issuing dosimetry only if the Electronic Dosimeter System is not in service, not available, or being used in the power on - power off modes.

d. Record the dose margin on Emergency Dose Margin Form (EP Form EPP 17-02). A separate form is filled out for each person.

Title:

Emergency Personnel No.: 10-S-01-17 Revision: 15 Page: 9 Exposure Control 6.7.2 Emerqencv RWP

a. The Emergency RWP uses the Response Team Pre-Dispatch Requirements as a Pre-Job Brief for OSC Teams and the OMT Briefing Checklist for Offsite Monitoring Teams. Personnel leaving other facilities must be briefed by the facility lead (or designee) prior to leaving the facility. The details of the briefing, and personnel briefed, should be logged if no briefing form is used.

b. All personnel who report to emergency facilities and expect to be sent out into the field should log into the RWP upon arrival. Personnel who experience problems logging in report to Radiation Protection personnel to determine appropriate action to allow the person to log in.

c. The Emergency RWP is used for personnel who leave emergency response facilities during a declared emergency. Working copies of the Emergency RWP are posted at the Control Room, TSC, Back-up TSC, OSC, Back-up OSC, EOF, and the RP Lab.

(The master copy is in the RP Lab.)

6.7.3 Issuina Dosimetrv

a. Select and assign a TLD (if the personal TLD is unavailable) and EAD, (or pocket dosimeters) for each person. Record TLD and dosimeter numbers on the Emergency Dose Margin Form.

b. Rezero all dosimeters.

c. Record dosimeter readings in "dose in" block of the Emergency Dose Margin Form.

d. Record the date and time that the person actually left the facility.

6.7.4 Personnel should read their dosimetry at the frequency required by the Emergency RWP. Readings should be reported to the emergency facility so the person's exposure margin may be updated. Report all dosimeter readings to the facility lead, or his designee, if requested.

a. TLD and dosimeter numbers need not be recorded for each entry except when there is a change of dosimetry or continuing data on a new Emergency Dose Margin Form.

b. Return the emergency dosimetry to the facility it was issued from, if possible.

Title:

Emergency Personnel No.: 10-5-01-17 Revision: 15 Page: 10 Exposure Control 6.8 EMERGENCY SUPPORT PERSONNEL EXPOSURE 6.8.1 Emergency Support personnel are administratively extended to the Federal Limits of 10CFR20 at the declaration of an Alert, Site Area Emergency, or General Emergency.

6.8.2 Support personnel are furnished appropriate dosimetry. In situations when it appears that administrative dose limits may be exceeded, these individuals are relieved of duties involving additional exposure to radiation.

6.9 RECORDS AND INFORMATION 6.9.1 Forms and paperwork generated during actual emergencies are retained for information, legal records of exposure, event reconstruction, and are submitted to the Manager, Emergency Preparedness to be filed as a Quality Assurance Record.

6.9.2 Ensure dose received during an emergency is recorded on the individual's dose history file. All occupational doses, including emergency doses, are required to be included as part of the individual's accumulated dose history and can affect the individual's allowable exposure during the current and subsequent years.

6.10 NOTIFICATIONS AND REPORTS 6.10.1 Ensure oral and written reports of overexposure are conveyed to the NRC as outlined in Ref. 3.1.

GRAND GULF NUCLEAR STATION 10-S-01-17 Revision: 15 Attachment I Page 1 of 2 EMERGENCY OPERATIONS FACILITY TLD LOCATIONS I (LOWER LEVEL) / lecommunications Num=TLD Location f2 I

' fi I

PUBLIC INFO 1 E NRC ELEC.

EQUIP ECURITY Engineering nu ~

1

\

ro/

I I I

GRAND GULF NUCLEAR STATION EMERGENCY PLAN PROCEDURE 10-5-01-17 Revision: 15 Attachment I Page 2 of 2 EMERGENCY OPERATIONS FACILITY TLD LOCATIONS (UPPER LEVEL)

STAIRS Num = TLD Location EXIT 5

L CONFERENCE AREA EXIT

GRAND GULF NUCLEAR STATION 10-S-01-17 Revision: 15 Attachment I1 Page 1 of 1 RISKS ASSOCIATED WITH LARGE DOSES OF RADIATION EPA-400-R-92-001, Table 2-3 Health Effects Associated With Whole-Body Absorbed Doses Received Within A Few Hoursa:

Whole Body Early Whole Body Prodromal Absorbed Dose Fatalitiesb Absorbed Dose Effects' (rad) (percent) (rad) (percent affected) 140 5 50 2 200 15 100 15 300 50 150 50 400 85 200 85 460 95 250 98 a

Risks will be lower for protracted exposure periods.

Supportivemedical treatment may increase the dose at which these frequenciesOCCUT by approximately50 percent.

C Forewarning symptoms of more serious health effects associated with large doses of radiation.

EPA-400-R-92-001, Table 2-4 Approximate cancer risk to average individuals from 25 Rem Effective Dose Equivalent delivered promptly:

Age at exposure Approximate risk of Average years of Life (years) premature death lost if premature (death per 1,000 death occurs persons exposed) (years) 20 to 30 9.1 24 30 to 40 7.2 19 40 to 50 5.3 15 50 to 60 3.5

GNRO-2002/00097, Changes to Emergency Plan Implementing Procedures - December 2002

Contents

Text

Subject:

Title:

Title:

Title:

Title:

Title:

3.0 REFERENCES

Title:

Title:

Title:

Title:

Title:

Title:

Title:

Title:

Title:

Title:

Title:

Title:

Title:

Title:

Title:

3.0 REFERENCES

Title:

Title:

Title:

Title:

Title:

Title:

Title:

Title:

Title:

Navigation menu