ML20214T623

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Revised Emergency Plan Implementing Procedures,Including Rev 5 to EIP-2-007, Protective Action Recommendation Guidelines & Rev 4 to EIP-2-024, Offsite Dose Calculations Manual Method
ML20214T623
Person / Time
Site: River Bend Entergy icon.png
Issue date: 09/11/1986
From: Deddens J
GULF STATES UTILITIES CO.
To:
Shared Package
ML20214T619 List:
References
PROC-860911, NUDOCS 8609300358
Download: ML20214T623 (61)
v • d • e


Text

{{#Wiki_filter:I ENCLOSURE 1 REVISED EMERGENCY IMPLEMENTING PROCEDURES

  • REV.

REV. Title No. DATE EIP-2-002 Notification of Unusual Event 3 08/04/86 EIP-2-003 Alert 3 08/04/86 EIP-2-004 Site Area Emergency 3 08/04/86 EIP-2-005 General Emergency 3 08/04/86 EIP-2-006 Notifications 6 08/04/86 EIP-2-008 Search and Rescue 2 08/04/86 EIP-2-009 Medical Emergencies 2 08/04/86 EIP-2-010 Toxic Gas Emergencies 2 08/04/86 EIP-2-011 Fire Emergencies 2 08/04/86 EIP-2-012 Radiation Exposure Controls 3 08/04/86 EIP-2-013 Onsite Radiological Monitoring 2 08/04/86 EIP-2-014 Offsite Radiological Monitoring 4 08/04/86 EIP-2-015 Post-Accident Sampling 2 08/04/86 Operations 08/04/86 EIP-2-016 Operations Support Center - 2 Activation EIP-2-017 Operations Support Center - 3 08/04/86 Support Functions EIP-2-018 Technical Support Center - 3 08/04/86 Activation EIP-2-019 Technical Support Center - 3 08/04/86 Support Functions EIP-2-020 Emergency Operations 3 08/04/86 Facility - Activation EIP-2-021 Emergency Operations 3 .08/04/86 Facility - Support Functions EIP-2-022 Alternate EOF - Activation 3 08/04/96 and Transfer of Functions EIP-2-023 Joint Information Center 2 08/04/86 Staff Activation and Functions EIP-2-025 Offsite Dose Calculations - 2 08/04/86 Computer Method EIP-2-027 Personnel Accountability 2 08/04/86 EIP-2-028 Recovery 2 08/04/86 EIP-2-100 Procedure Review, Revision, 4 08/04/86 and Approval EIP-2-104 Maintenance of Emergency 2 08/04/86 Telephone Numbers EIP-2-105 Control of Radiological 1 08/04/86 Monitoring Vehicles

  • Copies provided under RBG-24267 dated August 29, 1986.

l h8 fD DO F l

F ENCLOSURE 2 REVISED EMERGENCY IMPLEMENTING PROCEDURES

  • Rev.

Rev. Title No. Date EIP-2-007 Protective Action 5 9/11/86 Recommendation Guidelines EIP-2-024 Offsite Dose Calculations - 4 8/26/86 Manual Method EIP-2-102 Training, Drills & Exercise 4 9/11/86 i i

  • Copies attached.

E 4 RIVER BEND STATION APPROVAL SHEET STATION SUPPORT MANUAL PROCEDURES Procedure No.: EIP-2-007 Procedure

Title:

PROTECTIVE ACTION RECOMMENDATION GUIDELINES Safety-Related Activity Involved? Yes @ No Approved by Total Reason * (Signature /Date) Rev. Pages for Plant Manager Concurrence Effective No. Issued Revision (Signature /Date) Date 0 18 New Procedure N/A Exercise Critique J. C. Deddens 01 /11 / R ; 1 13 Comments N/A 2' 13 NRC Commitments N/A J. c Deddens 12 / n fi / R 5 3 14 ACRS Commitments 12/09/85 N/A Drill / Exercise J. C. Deddonn 02/24/86 4 14 Corrective Action ,N/A 02/24/86 n ( M D L Wa/e 5 15 Annual Review g-09/11/86 N/A l l l

  • Be specific (e.g., QAFR No., Regulatory Guide No., commitment, etc.)
    • Procedure effective at 0001 hours on date the Operating License is received for River Bend Station - Unit 1.

I

RIVER BEND STATION PROCEDURE REVIEW EMERGENCY PLAN IMPLEMENTING PROCEDURES TITLE: PROTECTIVE ACTION RECOMMENDATION GUIDELINES PROCEDURE NO.: EIP-2-007 REV.: 5 Reconunended for Approval: DATE b-kb ~ hb Sup p gisor - Emergency Planning / Ab-/7 C Y29h

  • FRC Cha~irman Meeting No.

Reviewed and Approved. Forward to Vice President - RBNG for Final Approval: Yb Manager - Administration 0l n]>c 9/2Afd Plant Manager

  • Signature indicates 10 CFR 50.54q Review complete on all changes.

i l l l l i f 1

r PROTECTIVE ACTION RECOMMENDATION GUIDELINES TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE 2

2.0 REFERENCES

2 3.0 GENERAL INFORMATION 2 4.0 PROCEDURE 4 5.0 ATTACHMENTS 6 5.1 (Protective Action Worksheet) 8 5.2 (Protective Action Recommendation 9 Flowchart) 5.3 (Affected Sectors and Protective 10 Action Sections Based on Wind Direction) 5.4 (Populations Within the Protective 11 Action Sections) 5.5 (Special Facilities) 12 5.6 (Evacuation Time Estimate Summary) 14 PROCEDURE NO.: EIP-2-007 REVISION NO.: 5 PAGE 1 OF 15

1.0 PURPOSE This procedure provides guidelines for determining protective actions for the general public to be recommended to the appropriate authorities in the event of a radiological emergency.

2.0 REFERENCES

l 2.1 River Bend Station Emergency Plan 2.2 Station Support Manual (SSM) Emergency Implementing Procedure (EIP)-2-025, "Offsite Dose Calculations - Computer Method" 2.3 SSM Procedure EIP-2-024, "Offsite Dose Calculations - Manual Method" 2.4 SSM Procedure EIP-2-014, "Offsite Radiological Monitoring" 2.5 SSM Procedure EIP-2-006, " Notifications" 3.0 GENERAL INFORMATION 3.1 A protective action is an action taken to avoid or reduce the effects of a nuclear emergency when the benefits derived from such an action are sufficient to offset any undesirable features or results of the protective action (i.e., constraints). The Protective Action Guideline (PAG) is the level at which the projected dose to individuals in the population or the potential dose from a rapidly escalating emergency warrants taking protective action. A PAG level under no circumstances implies an acceptable dose; it is used only to minimize the risk from an event which is occurring, may occur, or has already occurred. 3.2 This procedure is a guide for determining recommended protective actions to be recommended to local authorities during an emergency. Since it is impossible to cover all potential situatione, the judgement of the person responsible for recommending protective actions shall take precedence over the requirements of this procedure. However, since the protection of the general public is the ultimate concern, l protective actions less stringent than those suggested by the procedure should be recommended only if constraints (i.e., time available, traffic congestion, weather hazards) make the required actions a greater hazard to public health. PROCEDURE NO.: EIP-2-007 REVISION NO.: 5 PAGE 2 0F 15

T-1.0 PURPOSE This procedure provides guidelines for determining protective actions for the general ~public to be recommended to the appropriate authorities in the event of a radiological emergency.

2.0 REFERENCES

2.1 -River Bend Station Emergency Plan 2.2 Station Support Manual (SSM) Emergency Implementing Procedure (EIP)-2-025, "Offsite Dose Calculations - Computer Method" 2.3 SSM Procedure EIP-2-024, "Offsite Dose Calculations - Manual Method" 2.4 SSM Procedure EIP-2-014, "Offsite Radiological Monitoring" 2.5 SSM Procedure EIP-2-006, " Notifications" 3.0 GENERAL INFORMATION 3.1 A protective action is an action taken to avoid or reduce the effects of a nuclear emergency when the benefits derived from such an action are sufficient to offset any undesirable features or results of the protective action (i.e., constraints). The Protective Action Guideline (PAG) is the level at which the projected dose to individuals in the population or the potential dose from a rapidly escalating emergency warrants taking protective action. A PAG level under no circumstances implies an acceptable dose; it is used only to minimize the risk from an event which is occurring, may occur, or has already occurred. 3.2 This procedure is a guide for determining recommended protective actions to be recommended to local authorities during an emergency. Since it is impossible to cover all potential situations, the judgement of the person responsible for recommending protective actions shall take precedence over the requirements of this procedure. However, since the protection of the general public is the ultimate concern, protective actions less stringent than those suggested by the procedure should be recommended only if constraints (i.e., time available, traffic congestion, weather hazards) make the required actions a greater hazard to public health. PROCEDURE NO.: EIP-2-007 REVISION NO.: 5 PAGE 2 0F 15 o

T 3.3 The Environmental Protection Agency (EPA) Protective Action Guides have been used to develop this procedure. The following table is a guideline for specific Protective Action Recommendations (see Attachment 2): Whole Body Thyroid Protective Action to

  • Integrated Dose Integrated Dose Be Recommended

<1 Rem 4 5 Rem No specific actions for the general public > l to < 5 Rem Z 5 to< 25 Rem Minimum action is to shelter public > 5 Rem > 25 Rem Evacuate area unless constraints make evacu-ation impractical Integrated dose levels are based on the estimated duration of the release or a predetermined default value. 3.4 Field surveys should be conducted to confirm dose projections. If these surveys are available at the time that a recommendation is made, they should be considered together with the dose projection. However, a protective action recommendation should not be delayed until field survey results are reported. 3.5 The authority and responsibility for the selection and implementation of offsite response options rests fully with the appropriate state and local authorities. Gulf States Utilities Company has no authority with respect to im70 sing protective response options beyond the boundaries of the River Bend Site. l NOTE When the EOF is activated, LNED representatives l will review'and concur / revise the protective action recommedations prior to release to offsite authorities. 3.6 Protective action recommendations for the general public shall be provided directly to Parish government representatives by the Recovery Manager. The decision to notify and to make protective action recommendations to offsite authorities may not be delegated. 3.7 Initially, the Shift Supervisor (acting as Emergency Director / Recovery Manager) implements this procedure. When the TSC is operational, the Plant Manager (or alternate), acting as Emergency Director / Recovery Manager, has the responsibility for actions in this procedure. When the EOF is operational, the Senior Vice President - RBNG (or alternate) assumes the role of Recovery Manager and has the responsibility for recommending protective actions for the general public to offsite agencies. PROCEDURE NO.: EIP-2-007 REVISION No.: 5 PAGE 3 OF 15

3.8 is a worksheet for recording protective action recommendations based on Attachments 2 through 6. l 3.9 The Protective Action Recommendation Flow Chart in Attachment 2 will be used to determine the appropriate protective actions. The notes on Attachment 2 are guidelines and questions to be answered to assist in making protective action recommendations. 3.10 Attachment 3 will be used to determine the sectors of the 10-mile emergency planning zone (EPZ) that will be affected based on wind direction. Protective Action Sections (PAS) are identified in Attachment 3 to aid in determining the affected Protective Action Sections based on wind direction. 3.11 Attachment 4 displays populations in each of.the PASS established by the Louisiana Nuclear Energy Division (LNED). 3.12 Attachment 5 lists the special facilities (schools, hospitals, nursing homes, and prisons) within the 10-mile EPZ with the corresponding direction and distance form the station, the PAS, the population, and seasons used. Evacuation time estimates for these facilities are included in the estimates in except as noted. 3.13 The summary of evacuation time. estimates in Attachment 6 shows the evacuation areas by true direction, radius of the 10-mile EPZ and the affected PASS. The population and number-of vehicles in the 10-mile EPZ are listed for each of the areas. Evacuation times for nighttime and daytime and for normal adverse weather conditions'are shown. also delineates the difference in evacuation times between peak season and off-peak season. 4.0 PROCEDURE 4.1 The Radiological Assessment Coordinator shall: 4.1.1 Continually assess potential and actual releases of radioactive materials and review dose calculations performed by the Assistant Radiological Assessment Coordinator and data available from offsite monitoring teams. 4.1.2 Following each offsite dose calculation, complete the Protective Action Worksheet (Attachment 1) and provide the results immediately to the Radiation Protection Advisor or the Radiation Protection Coordinator as indicated. 4.1.3 Direct the offsite Radiological Monitoring Team (s) to take surveys of the plume during an actual release and provide this information to the Radiation Protection Advisor. If a release has not yet begun, direct the team (s) to an offsite l ation consistent with early detection of any releases from the plant. l PROCEDURE NO.: EIP-2-007 REVISION NO.: 5 PAGE 4 OF 15 l

^ 4.2 The Assistant Radiological Assessment Coordinator shall: 4.2.1 Calculate offsite integrated whole body and thyroid doses using EIP-2-025, "Offsite Dose Calculations-Computer Method (Reference 2.2). If'the computer method is unavailable, use EIP-2-024, "Offsite Dose Calculations-Manual Method" (Reference 2.3). 4.2.2 Provide dose calculation results to the Radiological Assessment Coordinator. 4.2.3 Document and keep accurate records of all dose' calculations performed and all field team results reported. 4.3 The Radiation Protection Advisor (or Radiation Protection Coordinator) shall: 4.3.1 Review dose projection calculations completed by the Assistant Radiological Assessment Coordinator and any l offsite radiological monitoring data available. 4.3.2 Approve Attachment 1 and complete lines 8 through 13 of the Notification Message Form (Attachment 1 of EIP-2-006 (Reference 2.5]), and discuss protective actions to be recommended with state representatives, and the Nuclear Regulatory Commission (NRC) if available, including the basis and reasoning used to arrive at the particular set of recommendations stated. through 6 should be used as an aid in such decisions. 4.3.3 Forward the completed Sections of the Notification Form (Attachment 1 of EIP-2-006 [ Reference 2.5]) and Attachment 1 to the Recovery Manager without delay. 4.3.4 Provide a copy of radiological information to the Status Boards Coordinator for status update. 4.3.5 Continue to assess offsite conditions and update protective action recommendations anytime the situation warrants. 4.4 The Recovery Manager or Emergency Director shall: NOTE If state representatives have not yet arrived at the EOF, recommendations to the parishes should not be delayed: however, every effort should be made to include state representatives in the protective action recommendation process. 4.4.1 Review and discuss with the State LNED Representative and the Radiation Protection Advisor, if necessary, the protective actions to be recommended for the general public indicated on Attachment 1. PROCEDURE NO.: EIP-2-007 REVISION NO.: 5 PAGE 5 OF 15

4.4.2 Make public protective action recommendations directly to the parish governments as soon as practical following events requiring such recommendations. 4.4.3 Continue frequent contacts with state and parish officials, providing information on escalating, deescalating or unchanged recommendations. 4.4.4 For the situation where the potential exists for venting the containment, the following items should be considered but are not all inclusive: 4.4.4.1 Status of Emergency Plan Implementation 1) Review level of emergency plan classification and impact of escalation 2) Review meteorological conditions 3) Review emergency response team / facility status 4) Assess offsite dose assessment capability 5) Review status of notifications to offsite agencies 6) Review status of current protective action recommendations. 4.4.4.2 Statuslof Plant 1) Post accident sampling system samples and analysis results 2) Containment radioactivity levels 3) Status of decay heat removal equipment (i.e., condenser, containment unit coolers, residual heat removal) NOTE Containment yield point is 53 psig. 4.4.5 other Anticipated Events 1) Consider rate of pressurization 2) Review near term equipment availability 3) Review restoration of decay / containment heat removal ability. PROCEDURE NO.: EIP-2-007 REVISION NO.: 5 PAGE 6 OF 15

5:0 ATTACHMENTS j 5.1 (Protective Action Worksheet) 5.2 (Protective Action Recommendation Flowchart) 5.3 (Affected Sectors and Protective Action Sections Based on Wind Direction) 5.4 (Populations Within the Protective Action Sections) 5.5 (Special Facilities) 5.6 (Evacuation Time Estimate Summary) l l PROCEDURE NO.: EIP-2-007 REVISION NO.: 5 PAGE 7 OF 15

PROTECTIVE ACTION WORKSHEET cete TME POLLOWIN G PROT E CTIV E ACTION RE COMM EN D ATIONS ARE SASED ON: ( ) C ore / Cen t ainme n t Status ( ) Does Proleetlen Calculatten. Calculated UsinS Release Rate At (Ti m e ) Based on Duration of Release (hours) ( ) Pleid Team Results RECOMMENDED PR OT E CTIV E ACTIONS: ( ) None ( ) Shelter miles radius around the Site ( ) gvacuate miles radius steund Site AND ( ) Shelter _ miles downwind in Sec tore ( ) Evaeuste mile s downwind in Sec t or s ( ) Other l l 1 Prepared by: (Time) Radiological Assessment Coordinator Approved by: l Radiation Protection Advisor (Time) i I D8 I LirID Representative (Time) PROCEDURE NO.: EIP-2-007 REVISION NO.: 5 PAGE 8 0F 15

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Proteellee AellenSeelleno 'if Affected C-.. a "" ;le 11ree Affected Seeters Degrees from Degrees to Sectors e 2 udies 5 miles le miles O 168.74 - 191.15 344.76 - 11.25 AR8 1 2,3 4,7 893.26 - 213.75 11.26 - 33.75 BAC 1 2,3 6,7,10 2 .O 913.76 - 2M.25 33.76 - 52.25 C I'l D 1 3 7,10,11 2M.26 - 258.75 56.16 - 76.75 DCE 1 3,8 7,89,11 l% 258.76 - 281.25 78.76 - 101.25 EDP 1 3,4,8,9 7,80.11,11,13 g

7 201.26 - 303.75 191.26 - 123.75 PEG 1

3,4,0,9 11,12,13 gy-i 7 303.76 - 326.25 123.76 - 148.15 0PH 1 4,9 12,13,84 yQ o 326.24 - 348.75 148.28 - 168.75 HGJ t 4,9 12,13,14,15,17 d$ 344.76 - 11.25 168.76 - 191.25 JHR 1 4,9,16 14,15,17 Ocn tn tn i1.24 - 33.75 191.26 - 213.75 RJL ,1 4,14 15,17,18 g 33.76 - 56.25 213.76 - 2M.25 LRM i 16 17,18 gg 58.26 - 78.75 2M.26 - 258.75 IILM I le 5,80 gm g g 2 78.76 - 191.25 258.76 - 281.25 MMP 1 2,16 5,10 o$

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191.28 - 123,75 201.26 - 393.75 PMQ t 2 5,6 CN

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5 salle Radius PAS = 2,3,4,0,9.16 H 19 mile Radius PAS = 5,6,7,10,11,12,13,14,15,17,10 yg 'if ZH tg PROTECTIVE AC710M SEC710M PER PARISH: H 2 miles 5 miles le miles 13,14 O w East Beton Roege 8,9 10,11,12 O Best Pelleiena 16 17,18 Point Coopee 15 Q West Beton Rouge 1 2,3,4 5,6,7 Went Pelielane

l POPULATIONS WITHIN THE PROTECTIVE ACTION SECTIONS I899/44, West Feliciona y 10 s.:se/4,iie 2 3 J33/1,734 l II 5 3 733/037 344/173 120A00 i Celt Felicient g,$ ' '88 1 0/0

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/12 373 4 j ses/ise a / is is j ..../..., .., 1. := =.. e.,,....,... 2.088/100 g-13 p sees /ars 841/419 14 15 ,,r,,,,,,,7,,,,,,,,, west satan to.,e Permanent and Transient Populations projected f om 1980 census data PROCEDURE NO.: EIP-2-007 REVISION No.: 5 PAGE 11 OF 15

l l *ti ! 30 R lII l' Beforence Direction / Numtier of Users /Staf f l eso. (21 Wile PAS Name of racility D Night seasons of Use S g taset Feliciana Parish i.O Schools l ** 1 IINN/6 2 Bains Elementary 026/70 Fall, winter, soring i ggg 2 sums /6 2 teest Feliciana Nigh 745/00 Fall, winter, spring ) ogg Itoopitals and Nursines Nomes j k 3 ans/ 3 2 00est Feliciana Parish 15/25 15/5 Year-round l! O Nospital e i o 4 seNE/6 7 Idlewood Nursing Mome 122/25 122/10 Year-round lN i prisons m 5 tsNes/4 2 toest Feliciana Parish 2e/2 2e/2 Year-round mh Jail

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6 Seent/9 .6 Dept. of corrections 35/6 Year-rosend 00 > rt Meat Packing Plant m td m O East Feliciana Parish 6* g schools O c) m E mH i!,o 7 NE/lO 10 Jackson Elementary 874/5e Fall, winter, spring td rt I tJ H Fall, winter, spring vH u j O ME/lO 10 Jackson Nigh School 600/47 H l 9 NE/10 10 Folkes vocational 150/19 150/9 Fall, winter, spring tr3 Technical M 4 ItoopitaIe and Nuraing Momes I 10 NE/9 10 East Louisiana State 500/690, 500/227 Year-round q i Hospital (ELSHI j tut Prisons 11 ENE/9 le Dixon correctional 010/134 ele /62 Year-round p N Institute i 12 NE/9 le Jackson Special 45/15 45/s Year-round j g geospital 13 seE/9 le Feliciana Forensic 30/46 en/21 Year-round ij g Facility at ELSN

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i l l l l J8 III Reference Direction Number of Users / Staff I we.12) set te PAS wame of racility pay nigh Seasons of Use East Baton Rouge Parish - 1. ,2 Fall, winter, spring O 14 SE/0 13' Port Nedeon Child 87/13 Imarning Center Noepitale and tearsing %ees - wa== f% Prisome - teone ,7 int. Co se Parish

e,o cois j g 15 sw/s le roydras 45e/51 ralt, winter, spring l N 36 usw/0 le posenwald 955/11 Fall, winter, spring 17 Sw/0 IS Catholic Elementary 466/41 Fall, winter, spring U) 10 Sw/S 10 Catholle Junior High 225/15 Fall, winter, spring mm H

19 Sw/S IS Catholic nigh 291/22 Fall, winter, spriseg [O n 20 wsw/9 le False River Academy 610/11 Fall, winter, spring $h O { E 21 usw/10 IB 90emorial Area 130/18 20/2 ral1, winter, spring 9y k l> Vocational 1 oa e ( 3 Fall, winter, sering ms

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!,o 22 Ssw/le le sougon Nigh school 400/40 mn a i .os,itais and w.reing.omes 23 usw/le le Pointe Coupee General 26/Se 26/25 Year-round

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j Hospital 120/12 Year-round U U) 24 WSw/19 19 Lakeview Manor pursing 120/25 un-. 25 wSw/10 18 Pointe Coupee Nursing 120/40 120/15 Year-round lecee (uj Prisons g t.d 26 Sw/8 IS Pointe Coupee Parish 42/2 42/1 Year-round Jail O tenet Baton Rouge Parleh j ; .c.oois - none j Inoopitale and leursing geomes - teone Prisons - stone (1) Data collected as of psovember 1982 I 1

i l 1 i ' 4 30 o 4 et. 1 xo c.eneral Pubtle Appres1 mate evacuatton Times thoure/minuteel(2) Swacuation Population vehicles NIqhttime Weather Dertime teenther j Area (PAS) Nighttime Daytime NIqhttime Daytime Normal Adverse teormal Adverse N roll e-2 mile til 933 116e 325 420 1/32 1/42 2/35 3/s 4 m lh morthwest e-5 utlett,23 4446 7137 153e 217e I/52 2/3 i/51 3/23 y ii n 'o northeast e-5 nilett,33 13e6 1573 421 53e I/3e 1/42 7/36 3/1 g ] Soetheast e-5 Mile (1,4, 1421 1982 579 009 1/37 1/47 2/42 3/9 d e,. i g _g <3 seetheseet e-5 M11 ell,163 1255 1658 439 711 1/32 1/42 ,2/35 3/o Ea n i

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  • Peak Season a s September through May o

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l l 1 30 t3 orr-PEAR SEASON 2 4l,o GeneralPeblic i.. APPresimate Evacuation Times thours/minutee (2) i Evacuation Population vehicles Nighttime tocather Daytime Weather Arealll (PAS) niiElet time Daytime Nighttime Daytime Uormal Adverse 90ermal

Adverse, g

1 Ftskl 4-2 mile (Il 1303 1632 445 544 1/38 1/44 2/36 3/7 i g< Y. Iterttawest e-5 Mile (1,28 4779 5771 1599 1981 1/52 2/4 2/Ses 3/21 g C Itertineast 4-5 Ninet t,3 3 1756 2020 541 655 I/3e 1/58 2/39 3/7 y 1 H soottisest e-5 Mlle II,4, 1971 2424 699 1883 1/3e 1/47 2/42 3/9 .1 e,93 mz m l H seethuset e-5 M11ett,165 1705 213e 559 e35 1/3e 3/44 2/36 3/7 ,S 8 Q m g mZ m y Nortteuest e-le Mile 524e 7299 2015 2441 1/56 2/19 '2/54 3/29 M o( i 2 (1,2,5,6 ) N g O U3 (D stortheast e-10 Mile 6325 7258 1903 2507 1/3e t/51 2/38 3/6 Hi H. :s II,3,7,10,111 H g v m soottisest e-le Mile 5135 613e 1827 2526 1/40 1/47 2/42 3/9 H u (8,4,e,9,12,13,14,15) M III soottiveet e-le Mile 12739 13551 4250 4641 1/5t 2/23 2/38 3/21 ( 4,16,17,1 e ) M Full EPS (1 through le) 26298 29350 e60s 10563 2/11 2/54 3/10 4/17 1 i M N (3) See Attachment 4 for PAS tocations. (2) All times are roended to nearest minute. (36 special facility evacuation time for Pointe coupee Nursing Name is 2 hours 19 minutes M i M I I s

t s RIVER BEND STATION APPROVAL SHEET STATION SUPPORT MANUAL PROCEDURES Procedure No.: EIP-2-024 Procedure

Title:

OFFSITE DOSE CALCULATIONS - MANUAL METHOD Safety-Related Activity Involved? Yes No Approved by Total Reason * (Signature /Date) Rev. Pages for Plant Manager Concurrence Effective No. Issued Revision (Signature /Date). Date 0 29 New Procedure ^ ^ N/A 1 21' NRC Commitments N/A Corrections /FRC J. C. Deddens 08/09/85 2 21 Review Comments N/A Drill / Exercise J. C. Deddens 02/24/86 3 24 02/24/86 Corrective Action g, j gfg ( [s W h rleb 08/26/86 4 25 Annual Review N/A l l l l l l Be specific (e.g., QAFR No., Regulatory Guide No., commitment, etc.)

    • Procedure effective at 0001 hours on date the Operating License is received for

( River Bend Station - Unit 1.

RIVER BEND STATION PROCEDURE REVIEW EMERGENCY PLAN IMPLEMENTING PROCEDURES TITLE: OFFSITE DOSE CALCULATIONS - MANUAL METHOD PROCEDURE NO.: EIP-2-024 REV.: 4 Reconunended for Approval: DATE %L.%. M L ,-n -8s Supgvisor-EmergencyFlanning Wt h CtN4VM Pl-l45 T!d!$0

  • FRC Ch'Kirman fleeting No.

Reviewed and Approved. Forward to Vice President - RBNG for Final Approval: m _A YlV Manager - Administratio'h Wf V'/4N16 Plant ' Manager f

  • Signature indicates 10 CFR 50.54q Review complete on all changes.

i OFFSITE DOSE CALCULATIONS - MANUAL METHOD TABLE OF CONTENTS ] SECTION PAGE H 1.0 PURPOSE 2

2.0 REFERENCES

2 3.0 GENERAL INFORMATION 2 4.0 PROCEDURE 3 4.1 Dose Projection for Gaseous Airborne Release 3 (Calculator-Manual Method) 4.2 Dose Projection for Gaseous Airborne Release 8 (Manual-Manual Method) 4.3 Dose Projection for Gaseous Airborne Release 10 (Isopleth-Overlay Method) 5.0 ATTACHMENTS 11 5.1 (Dose Projection Worksheet A, 13 Meteorology and Release Conditions) 5.2 (Dose Projection Worksheet B, Off-15 site Dose Calculations) 5.3 (Table 1, Atmospheric Dispersion 17 Factors 5.4 (Table 1-A, Atmospheric Dispersion 18 Factors) 5.5 (Dose Projection Worksheet C, 19 Isopleth Dose Calculations) 5.6 (Release Rate Determination Based 20 on Effluent Sample) 5.7 (Alternate Methods of Determining 21 Stability Class) 5.8 (Figure 1, Net Radiation Index 25 [NRADI]) 1 PROCEDURE NO.: EIP-2-024 REV. No.: 4 PAGE 1 OF 25

1.0 PURPOSE This procedure provides the methodology for predicting offsite radiation exposure rates from an actual or potential release of radioactive materials from the plant.

2.0 REFERENCES

2.1 River Bend Station Emergency Plan 2.2 Station Operating Manual (SOM) Procedure COP-1003, " Post Accident Sampling of Gaseous Effluents" 2.3 Station Support Manual (SSM) Emergency Implementing Procedure (EIP)-2-006, " Notifications" 2.4 SSM Procedure EIP-2-007, " Protective Action Recemmendation Guidelines" 2.5 SSM Procedure EIP-2-025, "Offsite Dose Calculations - Computer Method" 3.0 GENERAL INFORMATION 3.1 Initial and follow-up calculations using this method shall be completed by the Control Operations Foreman or the Assistant Radiological Assessment Coordinator. 3.2 This procedure shall be used by the Assistant Radiological i Assessment Coordinator when the RM-21 Module of the Digital i Radiation Monitoring System (DRMS), dose assessment mode, is inoperable. 3.3 Offsite dose calculations shall be initiated anytime a Site Area Emergency or General Emergency is declared due to a radiological accident, or any other time the Emergency Director or Recovery Manager deem necessary. 3.4 Offsite radiation doses, calculated using this procedure shall be used to recommend protective actions for the general public in accordance with Reference 2.4 (SSM Procedure EIP-2-007, " Protective Action Recommendation Guidelines"). 3.5 When the Emergency Operations Facility (EOF) is operational, the Assistant Radiological Assessment Coordinator shall brief } the Chemistry / Core Damage Assessment Coordinator in the Technical Support Center (TSC) on dose assessment activities. The Chemistry / Core Damage Assessment Coordinator shall perform dose assessment activities while the Assistant Radiological Assessment Coordinator is relocating from the TSC to the EOF. 3.6 Assessment of offsite radiation exposure rates and projected integrated doses shall be completed initially within approximately 15 minutes of the declaration of a Site Area PROCEDURE NO.: EIP-2-024 REV. NO.: 4 PAGE 2 0F 25

Emergency or General Emergency, when these declarations are based-on a radiological emergency; follow-up calculations shall be completed approximately every 30 minutes following the initial projections, or sooner if release rates change significantly. 3.7 The minimum information required to use this procedure and the source of that information are: 3.7.1 Radioactivity concentrations being released, available from the Main Control Room or DRMS. 3.7.2. Flow rate of release pathway, effluent vent flow rate (s) as indicated in the Main Control Room. NOTE If instrumentation is inoperable or not available, flow rates may be estimated based on operations experience for the initial calculations, or default values may be used. 3.7.3 Meteorological conditions within the ten mile Emergency Planning Zone (EPZ) as indicated by the plant meteorological tower. Parameters needed include wind I direction, wind speed, and an indication of atmospheric stability, [e.g. temperature change with height above the ground (delta T)]. These parameters are indicated in the { Main Control Room and are available on the RM-21 Module of j the DRMS and the meteorological data printer. 3.8 The Isopleth Overlay Method in Section.4.3 may be used to calculate off-centerline doses to the edge of the plume. The overlay is also useful in graphically depicting the plume on the 1 7/8" = 1 mile scale map. The centerline Xu/Q values on the overlays are the same as those in Table 1; therefore, it is recommended that centerline doses be calculated using either the Calculator-Manual Method (Section 4.1) or the Manual-Manual Method (Section 4.2). 4.0 PROCEDURE 4.1 Dose Projection for Gaseous Airborne Release (Calculator-Manual Method) 4.1.1 Obtain a copy of the Dose Projection Worksheet A (Attachment 1) and record the data required. NOTE If for any reason the calculator will not function, go to Step 4.2 and use the Manual-Manual Method for dose calculation. PROCEDURE NO.: EIP-2-024 REV. NO.: 4 PAGE 3 0F 25

i 4.1.2 Set up the Printer for operation as follows: a. Turn on-off switch to "0N". b. Place Mode switch to " MAN". l c. Place the intensity switch to the mid position. NOTE Printer can be powered by either self contained battery (approximately 4 hours continuous use), or by the A/C power supply. Printer must be on for program to run. 4.1.3 Turn on calculator by depressing the "0N" button. Check the display, if the word (s) " ALPHA" or "PRGM" appear in display go to Step 4.1.4, otherwise proceed to Step 4.1.5. 4.1.4 The ALPHA and PRGM functions must be cleared prior to performing dose calculations. 1) To clear the ALPHA function,. depress the " ALPHA" Key. (ALPHA in the display should disappear.) 2) To clear the PRGM function, depress the "PRGM" Key. (PRGM in the display should disappear.) 4.1.5 Check the display for the word USER, if it appears in disp" lay proceed to Step 4.1.6. If not in display, depress the USER" Key until word appears. 4.1.6 Meteorology Subroutine 1) Depress the " MET" Key. (The "E+" Key on the H.P. Calculator) NOTE If meteorological tower information is unavailable either in Control Room or directly from the tower, refer to Attachment 7 of this procedure. This provides for correcting wind speed measured at Ryan Airport to wind speed at River Bend Station (RBS) in mph. 2) Key in the wind speed in miles per hour (mph) from the 30-foot (ft) sensori push the "R/S" Key. 3) Key in the wind direction in degrees, from the 30 ft sensori push the "R/S" Key. 4) The calculator now provides three options: (1) Delta T, (2) Sigma theta, (3) Estimate. The preferred method is Method #1. PROCEDURE NO.: EIP-2-024 REV. NO.: 4 PAGE 4 0F 25 i

5) Press numerical key 1, 2, or 3 to select desired option, then press the "R/S" Key. 6) Key in the app'ropriate values for options 1, 2, or 3; push the "R/S Key. NOTE The "CHS" Key is used to input negative values. Enter the numerical value then push the "CHS" Key. 7) For record purpose the calculator asks for Release Point, enter the appropriate number followed by the "R/S" Key. 1 1. Main Plan Vent = 2 2. Radwaste Building = 3 3. Fuel Building = 8) Key in the flow rate of the release point in cubic feet per minute (CFM), push the "R/S" Key. 9) The calculator prints out the Stability Class, and a Table of Xu/Q values for the Exclusion Area Boundary (EAB) and 1 to 10 miles.

10) " Press Key" should appear in the display.

4.1.7 Release Rate Subroutine 1) Press the "REL" Key ("1/X" Key on the H.P. Calculator). 2) The calculator provides for two options: (1) Release Rate based on vent monitor values, (2) Release Rate based on vent concentration (release pathway grab sample). 3) If using vent monitor, select Option f1 and continue, if using vent sample information select Option #2 and go to Step 6) 4) Enter the Noble as Release Rate in uCi/sec, push the "R/S" Key. 5) The calculator will now print the Noble Gas Release Rate in Ci/sec and the Iodine Release Rate in Ci/sec. " Press Key" should appear in the display. Skip steps 6), 7), 8), and 9). PROCEDURE NO.: EIP-2-024 REV. NO.: 4 PAGE 5 0F 25

NOTE The above method assumes a 1000:1 Noble Gas to Iodine ratio. Verification by Chemistry of the actual Iodine Release Rate should be done as soon as possible. Use the following method to adjust the release rate, based on Chemistry results. 6) Press the "1/X" Key and select option (2), press the "R/S" Key. 7) Enter the vent concentration of gross noble gases (CONC NG) from a grab sample analysis in uCi/cc, then press the "R/S" Key. 8) Enter vent concentration of gross radioiodine (CONC I) in uCi/cc, then press the "R/S" Key. NOTE To key' in the value of 1 x 10-6 you would key in "l, then the "EEX", then the "CHS" Key, then the "6". 9) " Press Key" should appear in the display. 4.1.8 Dose Rate Subroutine 1) Press the " DOSE" Key ("#T " Key on the H.P. Calculator). 2) Enter the time in hours since the Reactor has been shut down, push the "R/S" Key. 3) Enter the estimated duration of the release in hours (if unknown, enter the value of 8 hours), push the "R/S" Key. 4) The calculator now calculates the dose rate (mrem /hr) and projected dose (Rem) based on the data in the Meteorology and Release Rate subroutines, time since reactor shutdown and release duration estimate. 5) The values printed in the tables for Thyroid and Whole Body doses should be entered on the Notification Message Form (Attachment 1 of Reference 2.3 [SSM Procedure EIP-2-006, " Notification"]) and used to prepare recommendations for protective actions as described in Reference 2.4 (SSM Procedure EIP-2-007, " Protective Action Recommendation Guidelines"). PROCEDURE NO.: EIP-2-024 REV. NO.: 4 PAGE 6 OF 25

4.1.9 The projected doses are based on the information in all three subroutines. If data changes, enter the appropriate subroutine, key in the old and new data as appropriate and then enter the dose subroutine which will generate new tables based on the current information in the calculator. 4.1.10 Field Survey Subroutine NOTE This module determines release rate by back calcu-lating field readings to release point. It should not be used unless all other information concerning the release is not available. 1) Press the " Field Survey" Key (The " LOG" Key on the H.P. Calculator). 2) Enter field reading of Dose Rate Whole Body (D RATE WB) in mrem /hr, then press the "R/S" Key. 3) Convert field team estimated iodine concentration at the point of interest to dose by multiplying the iodine concentration in uCi/cc by the appropriate dose conversion factor from the following table: Time after Reactor Iodine Dose Conversion Shutdown hours Factor; mrem /uCi/cc (1 hour) 9 2.0 1.9 x 10 9 2.5 2.2 x 10 9 3.0 2.8 x 10 9 3.5 3.2 x 109 4.0 3.6 X 10 9 4.5 3.7 x 10 9 6.5 4.2 x 10 9 8.0 4.4 x 10 9 10.0 4.6 x 10 9 16.0 5.4 x 10 9 32.0 6.9 x 10 4) Key in radiciodine dose rate (D RATE THY) in mrem /hr, then press the "R/S" Key. 5) Enter the field team's distance from the plant in miles (DISTANCE), then press'the "R/S" Key. 6) Key in the time since reactor shutdown (TIME) in hours, then press the "R/S" Key. 7) Calculator will now print out the Noble Gas and Iodine release rate in Ci/sec based on dose rate readings in the field and MET data in memory. PROCEDURE NO.: EIP-2-024 REV. NO.: 4 PAGE 7 0F 25

8) Calculate the Noble Gas to Iodine ratio by dividing the Noble Gas release rate by the Iodine release rate. This yields a correction factor (CF) to multiply by calculated Iodine doses using Option #1 of the program: 1000 CF = Conc NG Conc I 2 9) Go back to Step 4.1.7 and calculate offsite doses using the release rates calculated in Step 7) above and Option fl. NOTE Option #1 of the Release Rate subroutine always assumes a 1/1000 Iodine to Noble Gas ratio. The resulting doses calculated for Iodine must be adjusted to account for the measured Noble Gas / Iodine ratio. 4.2 Dose Projection for Gaseous Airborne Release (Manual-Manual Method) 4.2.1 Obtain

a. copy of the Dose Projection Worksheet A (Attachment 1)

Record the date and time of release rate being used for the calculation. NOTE If meteorological information is not available either in Control Room or directly from the tower refer to Attachment 7 of this procedure. This provides for correcting wind speed measured at Ryan Airport to wind speed at RBS in aph. 1) Obtain wind speed for 30 ft. level from either the Control Room or local tower readouts. Convert the wind speed in miles per hour to meters per second. 2) Obtain the wind direction from the Control Room or local tower readouts. l 3) Obtain the 150-30 ft. temperature difference (Item 3a, Worksheet A) from the Control Room or local tower readout and determine the stability class. (If delta T is not available see Attachment 7.) NOTE For purposes of expediting calculations, if release rate is taken from DRMS or from RM-23 (Control Room), flow rate is not necessary. However, if grab samples from effluent pathways are taken, flow rates must be obtained. t PROCEDURE NO.: EIP-2-024 REV. No.: 4 PAGE 8 0F 25

4) Select the point of release and record the vent flow rate in cubic feet per minute. This information should be obtained from the Control Room. Use default value only if actual flow r'te cannot be determined. a 5) Enter'the release rate in Ci/sec for Noble Gas and for Iodine. Release rate is available from the DRMS output or from grab sample analyses. (Use Attachment 5 to calculate release rates from sample analyses.) NOTE Obtain isotopic analysis from vent sample as early as possible, in accordance with Reference 2.2 (SOM Procedure COP-1003, " Post Accident Sampling of Gaseous Effluents"), and calculate actual Noble Gas to Iodine ratio. 6) Enter the estimated duration of the release (EDR) in hours. Use defaalt value only if a reasonable estimate cannot be made. 4.2.2 Obtain a copy of Dose Projection Worksheet B (Attachment 2) and record the same date and time as on Worksheet A. 1) Record the selected Stability Class from Worksheet A (Attachment 1). 2) Record the appropriate Xu/Q value from Table 1 (Attachment 2) according to Stability Class selected. 3) Record the value for Mu(u - the average wind speed in meters per second) from Worksheet A (Attachment 1). 4) Calculate X/Q according to the form on Worksheet B. Item 2.c. 5) Calculate the Whole Body Dose Rate at the EAB using the form on Worksheet B, Item 2.d. (fg - factor noble gas found in Table at the bottom of Worksheet B). Value selected is dependent on hours after reactor shutdown. 6) Calculate the Child Thyroid Dose Rate at the EAB using the form on Worksheet B, Item 2.e. (fct - factor child thyroid - found in Table at bottom of Worksheet B). Value selected is dependent on time after reactor shutdown. 7) Record Whole Body Dose Rate at EAB (DR-WB-EAB) in l PROCEDURE NO.: EIP-2-024 REV. NO.: 4 PAGE 9 0F 25 l I L

appropriate blanks on lines 3.a., 3.b., and 3.c. respectively (this value from calculation on Worksheet B, Attachment 2). 8) Record Dispersion Factor (DF) values for appropriate stability class and radii from plant (2, 5, and 10 miles: DF at 2, DF at 5, and DF at 10 respectively) from Table 1-A (Attachment 4). 9) Calculate the integrated Doses in Rem for the Whole-Body (WB) and Child Thyroid (CT) by multiplying the WB and CT dose rates at the EAB, 2, 5, and 10 miles by the Estimated Duration of Release (EDR) (Item 7 of Worksheet A) and dividing the result by 1,000 to convert mrem to Rem. NOTE This method can be used for determining dose rate and integrated doses at any distance by using the relationship between the Xu/Q at the EAB and the Xu/Q at any desired distance. Xu/Q tables are provided at the TSC and EOF.

10) Record the resulting integrated doses on the Fotification Form (Attachment 1 of Reference 2.3 (SSM Procedure EIP-2-006, " Notifications"]).
11) Complete the Meteorology and Dose Rate sections of the Notification Form and forward the form to the Radiation Protection Advisor.
12) Initial and file completed Worksheets A and B to provide a permanent record of dose calculations.

4.3 Dose Projection for Gaseous Airborne Releases (Isopleth-Overlay Method). NOTE This method is not recommended for calculating centerline dose values. If centerline doses are desired use the methods in Section 4.1 or 4.2 above. 4.3.1 Complete centerline dose calculations using the Calculator-Manual or Manual-Manual Methods. 4.3.2 Obtain a set of Isopleth Overlays from the emergency supply locker in the Main Control Room, TSC, or EOF. 4.3.3 Select an overlay from the packet making sure that the Isopleth Overlay selected has the same stability class designation as that recorded in Item 3.b of Worksheet A. PROCEDURE NO.: EIP-2-024 REV. NO.: 4 PAGE 10 0F 25

4.3.4 Secure the overlay to the center post of the 10 mile EPZ map (1 7/8" = 1 mile scale). Align the Isopleth centerline with the current wind direction. 4.3.5 Using the Isopleth Dose Calculation Worksheet, (Dose Projection Worksheet C, Attachment 5) calculate off-centerline doses for the points of interest as follows: 1) Visually determine which of the isopleth lines, lettered A-L, is of interest. (For example, field team measurement or location of special facility.) 2) Determine the isopleth value for the line selected (table in lower right corner of the overlay labeled "ISOPLETHS".) Enter this value on Worksheet C (Attachment 5). 3) Enter the release rate for Noble Gases and for radioiodines from Worksheet A, Items 5a and Sb, or 5a and Sc. 4) Multiply the release rate by the isopleth value selected, and calculate dose rates along the isopleth line by multiplying the release rates of Noble Gas and Iodines by "the isopleth value and the appropriate dose factors "fg or "fct" from Worksheet B. 5) Calculate Integrated doses by multiplying the dose rates by the estimated release duration (EDR) from Item 7 on Worksheet A. 6) Repeat the calculations for each isopleth line of interest as directed by the Radiation Protection Advisor, the Emergency Director, or the Recovery Manager. I 4.3.6 Ensure that the originals of all attachments to this procedure are provided to the EOF Manager (or TSC Manager if applicable) for further transmittal to the Supervisor - Emergency Planning. 5.0 ATTACHMENTS 5.1 (Dose Projection Worksheet A, Meteorology and Release Conditions) 5.2 (Dose Projection Worksheet B, Offsite Dose Calculations) 5.3 (Table 1, Atmospheric Dispersion Factors) PROCEDURE NO.: EIP-2-024 REV. NO.: 4 PAGE 11 0F 25

5.4 (Table 1 , Atmospheric-Dispersion Factors) 5.5 (Dose Projection Worksheet C, Isopleth Dose Calculations) 5.6 (Release Rate Determination Based on Effluent Sample) 5.7 (Alternate Methods of Determining Stability Class) 5.8 (Figure 1, Net Radiation Index [NRADI]) PROCEDURE NO.: EIP-2-024 REV. NO.: 4 PAGE 12 0F 25

DOSE PROJECTION WORKSHEET A METEOROLOGY AND RELEASE CONDITIONS (Page 1 of 2) Date: Time: 1. Wind Speed: (30 ft. level) x 0.447 = m/Sec mph u 2. Wind Direction: (30 ft. level) from degrees 3. Atmospheric Stability: (See Attachment 7 if delta T is not l available) a. Delta Temperature (150-30 ft.) degrees F. b. Stability Class: Delta T Delta T Range (*F) Stability Class (*F) A T & - 1. 3 A (dT,k-1.3) >-1.3 6 Ti - 1.1 B GdT,-1.2,-1.1) 1 d T = - 1.0 C ( ALT = -1.0) i ) -1. 0 A T i- 0. 4 D 06T,-0.9 to -0.4) ) -0.4 4LT6 + 0.9 E (dT,-0.3 to +0.9) > +0.9 A T S + 2. 6 F (AT,+1.0 to +2.6) AT )+ 2.6 G 06T,)2.6) 4.0 Release Point: Flow Rate Default Flow Rate a. Main Stack Exhaust CFM 123,000 CFM b. Rad Waste Bldg. Vent CFM 4,000 CFM c. Fuel Bldg. Vent CFM 10,000 CFM Use actual flow rate from Control Room if available. PROCEDURE NO.: EIP-2-024 REV. NO.: 4 PAGE 13 0F 25

C DOSE PROJECTION WORKSHEET A METEOROLOGY AND RELEASE CONDITIONS (Page 2 of 2) 5.0 Release Rate: (Use "a" and "c" if vent sample analysis is available.) a. Noble Gas: Ci/Sec (DRMS or calculated on ) b. Iodine: Ci/Sec 4 1000 = Ci/Sec Noble Gas c. Iodine: Ci/Sec calculated on Attachment 6 (If data available) 6.0 Time Elapsed since Reactor shutdown hours 7.0 Estimated Release Duration (EDR) hours (Default value = 8 hours.) i 1 PROCEDURE NO.: EIP-2-024 REV. NO.: 4 PAGE 14 OF 25

DOSE PROJECTION WORKSHEET B 0FFSITE DOSE CALCULATIONS (PAGE 1 OF 2) 1. Stability Class selected (from Worksheet A): (A through G) 2. X/Q calculation and Whole Body - Child Thyroid Dose Rates at EAB: a. Xu/Q at EAB (0.6 mile) from Table 1: 1/m2 b. G from Worksheet A in meters /sec: m/s U C. = XG/Q G X/Q d. Dose Rate - Whole Body at EAB (DR - WB - EAB): mrem / hour x x = Ci/Sec Noble Gce X/Q fg (DR-WB-EAB) ~ at eff, pathway (from Item (Table below (DRMS) 2c.above) based on time after reactor shutcc er.) e. Dose Rate Child Thyroid EAB (DR-CT-EAB? mrem /hr* x x Ci/Sec lodine X/Q fct (DR-CI-EAE) from Worksheet A (from Iter (Table below 2c.s.bove) based on time after reacter shutdown) Time After Reactor Shutdewn fe fet x10l 1.4x10l 0 3.3 0.5 5.2 x 10 1.5 x 10 5 9 1.0 4.9 x 10 1.6 x 10 5 9 1.5 4.5 x 10 1.7 x 10 5 9 2.0 3.87 x 10 1.9 x 10 3 9 2.5 3.00 x 10, 2.2 x 10 9 3.0 2.50x10j 2.8 x 10 9 3.5 2.20 x 10 3.2 x 10 5 9 4.0 1.83 x 10 3.6 x 10 9 4.5 1.70 x 10 3.? x 10 5 9 6.5 1.40 x 10 4.2 x 10 5 9 8.0 1.04 x 10, 4.4 x 10 10.0 9.40x10{ 4.6x10l 16.0 5.09 x 10 5.4 x 10 3 9 32.0 3.70 x 10 6.9 x 10 Dose Commitment for one hour inhalation. PROCEDURE NO.: EIP-2-024 REV. NO.: 4 PAGE 15 0F 25

DOSE PROJECTION WORKSHEET B OFFSITE DOSE CALCULATIONS (PAGE 2 0F 2) 3. Whole Body Dose Rates at 2, 5 and 10 miles: Dispersion Factor (DF) table for 2, 5, and 10 miles (Table 1-A, Attachment 4) mrem / hour at 2 miles a. x = DR-WB-EAB DF at 2 DR-WB at 2 mrem / hour at 5 miles b. x = DR-WB-EAB .DF at 5 DR-WB at 5 mrem / hour at 10 miles c. x = DR-WB-EAB DF at 10 DR-WB at 10 4. Dose Commitment for Estimated Release Duration (EDR-Worksheet A) a. x 4 1000 = Rem, Whole Body DR-WB-EAB EDR Dose at EAB b. x + 1000 = Rem, Thyroid Dose DR-CT-EAB EDR at EAB c. x + 1000 = Rem, Whole Body DR-WB-2 EDR Dose at 2 miles d. x x + 1000 = Rem, Thyroid Dose DR-CT-EAB DF-2 EDR at 2 miles e. x 1000 = Rem, Whole Body DR-WB-5 EDR Dose at 5 miles f. x x 1000 = Rem, Thyroid Dose DR-CT-EAB DF-5 EDR at 5 miles g. x + 1000 = Rem, Whole Body DR-WB-10 EDR Dose at 10 miles h. x x + 1000 = Rem, Thyroid Dose DR-CT-EAB DF-10 EDR at 10 miles 5. Enter Whole Body Dose Rates for EAB 2, 5 and 10 miles, and Whole Body and Thyroid Dose Commitments for EAB 2, 5 and 10 miles (Item 13 'B, C, and D) on the Notification Message Form (Attachment 1, EIP-2-006). PROCEDURE NO.: EIP-2-024 REV. NO.: 4 PAGE 16 OF 25

TABLE 1 ATMOSPHERIC DISPERSION FACTORS

  • EAB, 2, 5, AND 10 MILES CENTERLINE Xu/Q VALUES DOWNWIND DISTANCE (MILES)

STABILITY 0.6 (EAB)' 2.0 5.0 10.0 CLASS A 2.22E - 06 5.196E - 07' 2.432E - 07 1.410E - 07 B 1.149E - 05 8.304E - 07 3.197E - 07 1.833E - 07 C 3.479E - 05 5.054E - 06 1.353E - 06 4.009E - 07 D 9.015E - 05 1.830E - 05 5.020E - 06 2.040E - 06 E 1.566E - 04 3.620E - 05 1.111E - 05 5.237E --06 F 2.731E - 04 8.628E - 05 2.946E - 05 1.426E - 05 G 3.958E - 04 1.527E - 04 6.287E - 05 3.265E - 05 i For Xu/Q values for distances other than 2, 5 and 10 miles, see Isopleth for the appropriate stability class. 4 i PROCEDURE NO.: EIP-2-024 REV. NO.: 4 PAGE 17 OF 25

TABLE 1-A ATMOSPHERIC DISPERSION FACTORS EAB - 2, 5, and 10 Miles STABILITY EAB DF DF DF-CLASS Xu/Q Value at 2 Miles at 5 Miles at 10 Miles A 2.220E-06 .2340 .1096 .0635 B 1.149E-05 .0723 .0278 .0160 C -3.479E-05 .1452 .0331 .0115 D 9.015E-05 .2030 .0557 .0226 E 1.566E-04 .2312 .0709 .0334 F 2.731E-04 .3159 .1078 .0522 C 3.958E-04 .3858 .1588 .0825 1 PROCEDURE NO.: EIP-2-024 REV. NO.: 4 PAGE 18 OF 25

DOSE PROJECTION WORKSHEET C ISOPLETH DOSE CALCULATIONS 1. Complete Worksheet A. 2. Ensure Overlay Stability Class agrees with Item 3.b of Worksheet A. 3. Select Isopleth of Interest from Overlay and 10 mile EPZ MAP. Isopleth Selected Isopleth Value Wind Speed (from Worksheet A) m/s 4. Calculate Isopleth Dose Rate: mrem / hour k a. x x = Noble Gas Isopleth Ig DR-NG Release Rate Value/ Wind Speed mrem / hour

  • b.

x x = Iodine Release Isopleth fct DR-I Rate Value/ Wind Speed NOTE These dose rates are valid at any point on the isopleth line selected regardless of distance from the plant site. 5. Calculate integrated doses for the isopleth line: x 1000 = Rem DR-NG EDR Noble Gas Dose x + 1000 = Rem DR-I EDR Iodine Dose j 6. Repeat Steps 3, 4 and 5 for as many isopleth lines as desired. Total Dose Commitment for 1 hour inhalation. i l PROCEDURE NO.: EIP-2-024 REV. NO.: 4 PAGE 19 OF 25

RELEASE RATE DETERMINATION BASED ON EFFLUENT SAMPLE 1. Effluent Sample Concentrations (from Sample Analysis data): uCi/cc Total Noble Gds Concentration (NG CONC) uCi/cc Total Iodine. Concentration (I CONC) 2. Release Point: Default Flow Rate

  • Flow Rate a.

Main Stack Exhaust CFM 123,000 CFM b. Rad. Waste Bldg. Vent CFM 4,000 CFM c. Fuel Bldg. Vent CFM 10,000 CFM Use actual flow rate from Control Room if available. 3. Release Rate Determination: a. uCi/cc x CFM x 4.72 x 10-4 Ci/Sec = NG CONC Flow Rate NG Release Rate b. uCi/cc x CFM x 4.72 x 10-4 = Ci/Sec I CONC Flow Rate I Release Rate Enter "a" and "b" on Attachment 1 Worksheet A, Item 5.a and 5.c. c. 4. Calculate Noble Gas to Iodine Ratio: a. + = NG CONC I CONC NG/I RATIO b. When using DRMS values for Noble Gas Release Rate in Subsequent Calculations, calculate Iodine Release Rate by: Ci/Sec Ci/Sec 4 NG Rate (DRMS) NG/I Ratio Iodine Release c. Enter "b" in Block 5.c of Worksheet A. PROCEDURE NO.: EIP-2-024 REV. No.: 4 PAGE 20 OF 25

ALTERNATE METHODS OF DETERMINING STABILITY CLASS (PAGE 1 OF 4) 1. Stability Class based on Sigma Theta [ standard deviation of wind direction (SWD)] a. Obtain Sigma Theta (e0) value', indicated as "SWD" (30 ft), from meteorological printout in Control Room, Environmental Lab or the base of meteorological tower, b. Select the stability class from the following table: SWD (e0) Range SWD (o0) in degrees (*) Stability Class in degrees ( ) > 22.5 A (SWD > 22.5) <22.5 > 17.5 -B (SWD 22.4 to 17.5) < 17. 5 3 12. 5 C (SWD 17.4 to 12.5) < l2. 5 > 7.5 D (SWD 12.4 to 7.5) <7.5 3 3.8 E (SWD 7.4 to 3.8) < 3. 8 3 2.1 F (SWD 3.7 to 2.1) 4.2.1 G (SWD 4.2.1) l l c. Enter the Letter Stability Class on Worksheet A, Item 3.b, Note method used on worksheet. 2. If no meteorological tower information is available, estimate stability class from current weather conditions as follows: a. Call the National Weather Service at Ryan Airport, telephone number 357-9743, 389-0646, or 389-0308 (after hours) and obtain the following: (1) Wind Direction Degrees (From) (2) Wind Speed MPH (3) Cloud Cover 10ths (4) Cloud ceiling-Feet (5) Front between RBS and Ryan Airport? Yes No (If Yes see 'f.' Attachment 7) PROCEDURE NO.: EIP-2-024 REV. NO.: 4 PAGE 21 OF 25

ALTERNATE METHODS OF DETERMINING STABILITY CLASS (Page 2 0F 4) b. Modify Ryan Airport (NWS) Wind Speed in MPH to local RBS meteorology by multiplying by the appropriate correction factor below: Transfer calculated local RBS wind speed in mph to Worksheet A, line 1. (30 ft level) m Use conversion factor on Worksheet A to convert to meters /ph. sec. TABLE 2 Ryan Airport Correction Local RBS Month Wind Speed (MPH) factor Wind Speed (MPH) JAN. x 0.576 = FEB. x 0.586 = MAR. x 0.557 = APR. x 0.476 = MAY x 0.446 = JUNE x 0.435 = JULY x 0.481 = AUG. x 0.474 = SEP. x 0.467 = OCT. x 0.475 = NOV. x 0.563 = DEC. x 0.554 = NOTE If nighttime, skip Step 'c.' and go directly to Step 'd.'. Enter as wind speed (mph) on line 1 of Worksheet A, (Attachment 1). Also, this calculated windspeed is partial basis for determination of i Stability Class on Attachment 7 (Page 4 of 4). I l PROCEDURE NO.: EIP-2-024 REV. NO.: 4 PAGE 22 OF 25 l

ALTERNATE METHODS OF DETERMINING STABILITY CLASS (PAGE 3 0F 4) c. Determine the Insolation Class Number (ICLNo) from the following table (Table 3): TABLE 3 Insolation Class Number for Time of Year and Time of Day (ICLNo)' Hour of Day-(24 hour clock) Time of Year (1-6) 7 8 9 10 11 12 13 14 15 16 17 (18-24) Jan. 5-Jan. 22 1 1 1 2 2 3 3 3 2 2 1 1 1 Jan. 23-Feb. 6 1 1 2 2 2 3 3 3 2 2 2 1 1 Feb. 7-Feb. 21 1 1 2 2 3 3 3 3 3 2 2 1 1 Feb. 22-Mar. 8 1 1 2 2 3 3 3 3 3 2 2 1 1 Mar. 9-Mar. 23 1 1 2 3 3 3 3 3 3 3 2 1 1 Mar. 24-Apr. 7 1 2 2 3 3 3 4 3 3 3 2 2 1 Apr. 8-Apr. 22 1 2 2 3 3 4 4 4 3 3 2 2 1 Apr. 23-May 7 1 2 2 3 3 4 ~4 4 3 3 2 2 1 May 8 - May 22 1 2 3 3 4 4 4-4 4 3 3 2 1 May 23-June 6 1 2 3 3 4 4 4 4 4 3 3 2 1 June 7-June 21 1 2 3 3 4 4 4 4 4 3 3 2 1 June 22-July 6 1 2 3 3 4 4 4 4 4 3 3 2 1 July 7-July 21 1 2 3 3 4 4 4 4 4 3 3 2 1 July 22-Aug. 5 1 2 3 3 '4 4 4 4 4 3 3 2 1 Aug. 6-Aug. 20 1 2 2 3 3 4 4 4 3 3 2 2 1 Aug. 21-Sep. 4 1 2 2 3 3 4 4 4 3 3 2 2 1 Sep. 5-Sep. 19 1 2 2 3 3 3 4 3 3 3 2 2 1 Sep. 20-Oct. 4 1 1 2 3 3 3 3 3 3 3 2 1 1 Oct. 5-Oct. 19 1 1 2 2 3 3 3 3 3 2 2 1 1 Oct. 20-Nov. 3 1 1 2 2 3 3 3 3 3 2 2 1 1 Nov. 4-Nov. 18 1 1 1 2 2 3 3 3 2 2 1 1 1 Nov. 19-Dec. 3 1 1 1 2 2 3 3 3 2 2 1 1 1 Dec. 4-Dec. 18 1 1 1 2 2 2 3 2 2 2 1 1 1 Dec. 19-Jan. 4 1 1 1 2 2 2 3 2 2 2 1 1 1 ICLNO = d. For daytime, determine the Net Radiation Index (NRADI) using the ICLNo determined in 'c.' above, information concerning cloud cover and cloud ceiling from 'a.' above, and Figure 1. For nighttime, cloud cover in tenths is the only parameter needed to determine NRADI from Figure 1. Daytime is defined as 1 hour after sunrise to 1 hour before sunset. NRADI = PROCEDURE NO.: EIP-2-024 REV. NO.: 4 PAGE 23 OF 25

ATTACHMENT 7 ALTERNATE METHODS OF DETERMINING STABILITY CLASS (PAGE 4 0F 4) Determine the Stability Class using the modified wind speed from e. 'b.' and the NRADI from 'd.' above. TABLE 4 Modified NRADI wind speed in mph from Attach-ment 7, Item b. 4 3 2 1 0 -1 -2 0-1 A A B C D F G 2-3 A B B C D F G 4-5 A B C D D E F 6 B B C D D E F 7 B B C D D D E 8-9 B C C D D D E 10 C C D D D D E 11 C C D D D D D 12 C D D D D D D Stability Class (Enter on Worksheet A, Item 3.b) f. If a front exists between RBS and Ryan Airport, request that the NWS Meteorologist recommend the "best estimate" wind speed and direction to be used for RBS meteorological conditions, and the approximate time that this condition will exist. Enter estimated Wind Speed and direction on Worksheet A and in a.(1) and (2) above. Note method of deriving these parameters on Worksheet A. Continue to estimate atmospheric stability using the method provided in Steps 'b.' through 'e.'. For windspeed not' included in ranges given, round to the nearest whole number. PROCEDURE NO.: EIP-2-024 REV. NO.: 4 PAGE 24 OF 25

FIGURE 1 NET RADIATION INDEX (NRADI) DAYTIME NIGHTTIME CLOUD CEILING CLCVR 7000 ft 7000 to 1500 ft-15000 ft 0/10 1/10 ICLNO NRADI = -2 2/10 NRADI = 3/10 4/10 5/10 6/10 7/10 NRADI = ICLNO-2* NRADI = ICLNO-1 8/10 9/10 10/10 NRADI = 0

  • If less than 1, set NRADI = 1.

} PROCEDURE NO.: EIP-2-024 REV. NO.: 4 PAGE 25 0F 25

I ,;e. ^4 WFORNrUNg..y ~ 4 RIVER BEND STATION . p, APPROVAL SHEET I STATION SUPPORT MANUAL PROCEDURES Procedure No.: EIP-2-102 Procedure

Title:

TRAINING, DRILLS, AND EXERCISES Safety-Related Activity Involved? C Yes @ No Approved by Total Reason * (Signature /Date) Rev. Pages for Plant Manager Concurrence Effective No. Issued Revision (Signature /Date) Date J. C. Deddens 10/02/84 0 12 New Procedure N/A Change Effective J. C. Deddens 12/12/84 1 12 Date yfg 2 12 NRC Commitments 05/22/85 N/A Drill / Exercise J. C. Deddens 02/24/86 02/24/86 3 13 Corrective Action N/A o, !/ M //Ib d t 4 13 Annual Review p 09/11/86 N/A v I i

  • Be specific (e.g., QAFR No., Regulatory Guide No., commitment, etc.)
    • Procedure effective at 0001 hours on date the Operating License is received for River Bend Station - Lhit 1.

RIVER BEND STATION PROCEDURE REVIEW EMERGENCY PLAN IMPLEMENTING PROCEDURES TITLE: TRAINING, DRILLS AND EXEICISES PROCEDURE NO. ' EIP-2-102 REV.: 4 Recommended for Approval: DATE h"28 ' hb Sup(rvisor - Emergency Planning h b.u% / b ' /I D

  • FRC Chairman Meeting No.

Reviewed and Approved. Forward to Vice President - RBNG for Final Approval: AS A Manafer - Administrhtion W (t.t 4 9/2/,VA Plant Manager

  • Signature indicates 10 CFR 50.54q Review complete on all changes.

l i t

i o TRAINING, DRILLS, AND EXERCISES TABLE OF' CONTENTS SECTION PAGE 1.0 PURPOSE 2 -2. 0 REFERENCES 2 3.0 GENERAL INFORMATION 2 4.0 PROCEDURE 3 5.0 ATTACHMENT 11 (Training Requirements Matrix) 12 4 i PROCEDURE NO.: EIP-2-102 REV. NO.: 4 PAGE 1 OF 13

~1. 0 PURPOSE This procedure establishes the basic training requirements for personnel who perform emergency functions and describes the program for planning and conducting drills and. exercises.

2.0 REFERENCES

2.1 River Bend Station Emergency Plan 2.2 10CFR50, Domestic Licensing, Part 50.47 b and Appendix E 2.3 NRC Regulatory Guide 1.101 1 2.4 TAP-5-007 (Training Records and Documentation) 3.0 GENERAL'INFORMATION 3.1 Applicability This procedure will be used by personnel who are assigned to develop, plan, schedule, conduct and evaluate emergency preparedness training, drills and exercises. 3.2 Definitions i 3.2.1 Drill - A Drill is a supervised event aimed at evaluating, developing,--and maintaining skills in a particular l operation. S 3.2.2 Exercise - An Exercise is an event.which tests the overall functions and capabilities of organizations involved in responding to an emergency situation. An exercise shall simulate an emergency that results in offsite radiological releases which require response by offsite authorities. 3.2.3 Controller - A Controller is a member of a drill or l exercise control group. Each controller may be assigned to one or more activities or functions for the purposes of keeping the action going according to a scenario, resolving differences (acting as an umpire), supervising, and otherwise assisting as needed. 3.2.4 Evaluator - An Evaluator is a member of a drill or exercise evaluation group. He or she may also serve in a dual capacity as both a Controller and Evaluator. Each Evaluator may be assigned to one or more activities or functions for the aurposes of evaluating, recording, critiquing, and mating recommendations for improvement. 3.2.5 RBS-Emergency Plan Working Group - The RBS Emergency Plan Working Group is comprised of personnel who are assigned to develop, plan, schedule, conduct and. evaluate emergency preparedness training, drills and exercises, s PROCEDURE NO.: EIP-2-102 REV. NO.: 4 PAGE 2 OF 13 l l L

3.2.6 Refresher Training-Periodic training to maintain proficiency in the River Bend Station Emergency Plan. 3.3 Precautions 3.3.1 When contacting any organization during a drill or exercise, the individual making the contact will emphasize that.a drill or exercise is in progress and that an actual emergency condition does not exist. 3.3.2 All announcements on the radio or Plant Page/Gadtronics k System during a drill or exercise shall be prefaced and ended with the words: "This is a drill (or exercise)." 3.3.3 The Emergency Implementing Procedures (EIPs) and Emergency Operating Procedures (EOPs) require protective and corrective actions which involve the operation of plant equipment, such as air dampers or valves. Drill or exercise controllers should be informed that such steps 5 will not be performed but should be simulated by the appropriate personnel. To the extent possible, such simulation should include all actions up to actually performing the equipment operations. For some drills or exercises, the Supervisor - Emergency Planning may position controllers at certain equipment locations to ensure that equipment is not inadvertently operated. 4.0 PROCEDURE 4.1 Training 4.1.1 All personnel, onsite and offsite, who are responsible for performing emergency functions required by the Emergency Plan and EIPs shall have appropriate training as described in this procedure. I 1 4.1.2 The training program will consist of required readings, classroom instruction, facility drills, and practical drills to provide individuals an opportunity to demonstrate the ability to perform assigned emergency functions in a simulated emergency situation. Documentation of training for all GSU emergency personnel shall be maintained in accordance with TAP-5-007, " Training Records and i i Documentation" (Reference 2.4). 4.1.3 The Supervisor - Emergency Planning shall: l 1. Coordinate'with the Nuclear Training Coordinator - Technical in the preparation, planning and scheduling of training for all GSU personnel, i l i I PROCEDURE NO.: EIP-2-102 REV. NO.: 4 PAGE 3 0F 13

2. Coordinate emergency training for offsite emergency response and support organization personnel, such as law enforcement, medical and fire department personnel. 3. . Annually review the General Employee Training (GET) program to ensure that Emergency Planning aspects are adequately covered and to verify that changes to the Emergency Preparedness program have been incorporated in the training program. 4. Annually review the News Media Training program presented by the GSU Public Affairs Division to ensure that training is being conducted and that changes to the RBS Emergency Preparedness program have been incorporated in the training program. 5. Annually review the Offsite Agency Training program to ensure that all agencies which arovide direct support to RBS during an emergency are icing provided training-on an annual basis and to verify that changes to the Emergency Preparedness program have been incorporated into the offsite agency training program. Training shall be provided annually to local support agencies listed in Section 13.3.4.3.2 of the Emergency Plan. 4.1.4 The Nuclear Training Coordinator - Technical shall: 1. Ensure that individuals receive the appropriate emergency training and refresher training annually. 2. Coordinate the planning and scheduling of training sessions with the Supervisor - Emergency Planning and GSU Department Heads /Section Supervisors. 3. Issue notices of training schedules to all employees. Notices should indicate which individuals should plan to attend specific courses in order to comply with the 'nitial qualification and annual refresher training i requirements. 4. Assist, if requested, with the preparation and implementation of the training program for offsite emergency response and support organization personnel. 5. -Maintain training records for all GSU emergency response personnel in accordance with TAP-5-007, " Training Records and Documentation" (Reference 2.4). 4.1.5 All River Bend Station employees are indoctrinated on the Emergency Plan and EIPs through the General Employee Training Program. The training provided through this program with regard to emergency planning is conducted on an annual basis with provisions for prompt indoctrination of new employees. The objectives of this training are: PROCEDURE NO.: EIP-2-102 REV. NO.: 4 PAGE 4 OF 13

1. Familiarize personnel with the scope, applicability, and implementation of the Emergency Plan and Procedures. 2. Instruct all station personnel in their responsibilities during an emergency. 3. Keep personnel informed of any changes in the Emergency Plan and Procedures. 4.1.6 Personnel receive, as a minimum, the following instruction concerning Emergency Planning: 1. General content of the Emergency Plan and EIPs. 2. Individual employee responsibilities with regard to familiarization with station alarms and response to alarms and use of communications systems during an l emergency. 3. Procedures and requirements associated with personnel evacuation, accountability, and contamination control criteria. 4.1.7 Personnel assigned to the emergency response organization receive specialized training for their respective assignments, as identified in the Training Matrix (Attachment 1). 4.1.8 Offsite support agencies having agreements and understandings with GSU to provide direct support to RBS during an emergency are offered training on an annual basis. The Offsite Support Agency training program shall include as a minimum: 1. Orientation with respect to the physical layout of RBS. 2. Indoctrination in their expected roles during an emergency at RBS. 3. Procedures for notification and points of contact. 4. Basic radiation protection. Training for offsite agency personnel may be combined with one or more of the required drills and exercises listed in Section 4.2. PROCEDURE NO.: EIP-2-102 REV. NO.: 4 PAGE 5 OF 13

4.1.9 On an annual basis a seminar type training program is offered to the News Media. This training will include orientation to RBS, points of contact within GSU, how information will be distributed during an emergency at RBS, and facilities provided by GSU to accommodate News Media representatives during exercises and emergencies. This training is presented by the GSU Public. Affairs Division. l 4.2 Drills and Exercises 4.2.1 Periodic drills and exercises will be conducted to verify the emergency preparedness of participating organizations and agencies. 4.2.2 The Supervisor - Emergency Planning shall: 1. Ensure accomplishment of the minimum number of drills required by the Emergency Plan. 2. Coordinate with the Nuclear Training Coordinator - Technical, GSU Department Heads and offsite agencies in planning and scheduling drills and exercises. 3. Ensure that communications tests are performed as described in Section 4.2.6,1.,b and review -documentation associated with the tests. 4. Direct development of drill and exercise scenarios and necessary support material. 5. Review drill and exercise scenarios and forward copies of scenarios to the RBS Emergency Plan Working Group l for their review. 6. Forward necessary drill / exercise advance materials to state / local / federal government agencies. 7. Assign personnel to control and evaluate drills / exercises. 8. Conduct a pre-drill / exercise conference with controllers, evaluators, representatives of participating offsite organizations and other drill / exercise staff personnel to discuss the scenario, conduct of the drill / exercise, necessary precautions and to distribute evaluation forms. L 9. Manage the conduct of the drill or exercise according to the scenario. l l l PROCEDURE NO.: EIP-2-102 REV. NO.: 4 PAGE 6 OF 13

10. Conduct a post drill / exercise critic ue, collect evaluation forms and document all itentified deficiencies and recommended corrective actions.
11. Based on critique comments, complete a written evaluation of the drill or exercise, describing the results of the critique, recommended corrective actions and a schedule for completion of corrective actions.

Forward a copy of the evaluation to the Manager - Administration and the Plant Manager.

12. Direct follow up and corrective actions resultfhg from drills / exercises, such as the need for additional training, revision of procedures or procurement of equipment and document completion of corrective actions.
13. Maintain documentation concerning the participation of personnel in drills and exercises in accordance with applicable Training Department procedures.
14. Maintain drill and exercise records on file for a minimum period of five years.
15. Ensure implemention of communications tests described in Section 4.2.6.1, b and verify that tests are completed as assigned.

4.2.3 The Nuclear Training Coordinator - Technical shall coordinate with the Supervisor - Emergency Planning and GSU department heads in planning and scheduling drills and exercises. 4.2.4 The RBS Emergency Plan Working Group shall review drill / exercise scenarios. An alternate member shall be assigned if the primary member is participating in the subject drill / exercise scenario. 4.2.5 The Shift Supervisor shall: ) 1. Assign a communicator to conduct communication tests from the Control Room, as described in Section 4.2.6.1, b. 2. Ensure documentation of communications tests conducted from Controi Room. 4.2.6 Drills 1. Types and Frequency a. Communications Drills PROCEDURE NO.: EIP-2-102 REV. NO.: 4 PAGE 7 OF 13

(1) Communications between the River Bend Station emergency response facilities (Control Room, TSC and EOF), the State of Louisiana and Mississippi, local EOCs and station field assessment teams shall be tested annually. (2) Communications drills shall test both the applicable circuits and ability of communicators to understand the content of messages passed. b. Communication Tests NOTE The emergency hotline will be tested monthly, except that every third month, the alternate radio system will be tested, and each initial notification point will be called by telephone in order to verify I commercial telephone notification numbers. (1) Communications links with the State of Louisiana and local Parishes, used for initial notifications of an emergency, within the plume exposure pathway EPZ shall be tested monthly. (2) Communications from the Control Room, TSC and EOF to the NRC Headquarters shall be tested monthly. c. Fire Drills Fire Drills will be conducted in accordance with River Bend Station Fire Protection Procedures, d. Medical Emergency Drills (1) Medical emergency drills, which involve a simulated contaminated individual and which provide for participation by local support agencies such as ambulance and hospital services, shall be conducted annually. (2) Offsite portions may be performed as part of l the required annual exercise, l e. Radiological Monitoring Drills Radiological monitoring drills shall be conducted annually, and will include the collection and analysis of sample media such as water, grass, soil, and air from the owner-controlled nearby offsite areas. PROCEDURE NO.: EIP-2-102 REV. NO.: 4 PAGE 8 0F 13

f. Radiation Protection Drills (1) Radiation protection drills, which involve response to and analysis of simulated elevated airborne and' liquid samples, as well as direct radiation measurements in the plant environment, shall be conducted semi-annually. (2) Analysis of in-plant liquid-samples with simulated, elevated radiation levels including use of the-post-accident sampling system are included in radiation protection drills. g. Evacuation and Site Accountability Drills, (1) An evacuation drill is conducted annually, so that personnel are aware of proper routes and assembly points. (2) An accountability drill is held simultaneously to ensure that all personnel have either been evacuated or accounted for onsite. (3) Evacuation and accountability drills may be performed as part of the required annual exercise. h. Facility drills may be conducted either independently or as onsite integrated drills with all facilities participating. i. Any of the above indicated drills may be accomplished in conjunction with the onsite facility drills. j. Additional drills may be scheduled by the \\ Supervisor - Emergency Planning, as necessary, to provide adequate training of personnel, provide emphasis on weak areas, and to ensure an adequate level of emergency preparedness. 2. Scenario Requirements a. As a minimum, drill scenarios shall contain provisions for the following: (1) Basic objective (s) of the drill and appropriate evaluation criteria. (2) Time period, place (s) of the drill and participating individuals. (3) Narrative summary which describes the conduct of the drill. PROCEDURE NO.: EIP-2-102 REV. NO.: 4 PAGE 9 OF 13

0 (4) Assignments for drill controllers and evaluators. 4.2.7 Exercise Description 1. Frequency An exercise which simulates a General Emergency will be conducted annually. 2. Scenario Requirements a. As a minimum, exercise scenarios shall contain provisions for the following: (1) Basic objective (s) of the exercise and appropriate evaluation criteria. (2) Time period, place (s) of the exercise, and the participating organizations. (3) Simulated events. (4) Time schedule of real and simulated initiating events. (5) Nar.ative summary which describes the conduct of the exercise and includes such items as simulated casualties, offsite fire department assistance, rescue of personnel, use of protective clothing, deployment of radiological emergency teams, and public information activities. (6) Assignments for controllers and evaluators. (7) Messages and evaluation forms for use by exercise staff personnel. (8) Observers from federal, state, and local government agencies, as agreed upon between GSU and the observing agency. b. In addition to the requirements listed in Section 4.2.7,2.a, the following additional requirements are pertinent for exercise scenarios: (1) Scenarios shall simulate an emergency that results in offsite radiological releases which require responses by oftsite authorities. PROCEDURE NO.: EIP-2-102 REV. NO.: 4 PAGE 10 0F 13

i (2) Scenarios will be varied from year to year so that over a five year period all major portions of the Emergency Plan and emergency response organization are tested. (3) Once every six years, the annual exercise will be init'iated between 6:00 p.m. and midnight and once between midnight and 6:00 a.m. (4) Exercise scenarios will allow for free play and decision-making by participants. This may require optional flowpaths to be written into the scenario. (5) Annual exercise scenarios will provide for the mobilization of state and local agencies to verify their capability to respond to an accident involving an offsite radiological release. Periodic participation by federal response organizations will be invited. c. Exercise scenarios shall be provided to the Nuclear Regulatory Commission and Federal Emergency Management Agency on the following schedule. (1) The narrative summary and sequence of events g is due 75 days prior to the scheduled exercise I date. (2) The complete scenario package including operational data and controller / evaluator information is due 45 days prior to the i scheduled exercise date. (3) Minor changes to scenario data and a schedule i L for meetings, briefings and critiques are due one week prior to the scheduled exercise date. L 5.0 ATTACHMENTS (Training Requirements Matrix) ~ i l l l PROCEDURE NO.: EIP-2-102 REV. NO : 4 PAGE 11 OF 13 l

e ATTACWENT 1 TRAINING REQUIREMENTS MATRIX (PAGE 1 0F 2) I l T s 8 i 3 h 3,,, 5.* X = 1 E.1 g 5 g. 6 3 x 3 1 I i s l'{i. E i s 3 t g e r (3# 5 E5 5 E I i i h 'l. ?- 3:l ! IE U o s a ! ~ g-in se,,: 3 I gr 4 4 e -s

3 63 45 ej 68 65 4 6&

6 2.. 55 55 5 5 37 z g.j sj RBS Emergency Plan .{.5 33 *. 3 23 3 3 3 sg g li15 lE l! la il la 1. I $5lll'l'ilili Shift Supervisors / Control Ops Foreman

  • X X

X X X X Nuclear Control Operators X X X Nuclear Equipment Operators ** X X X Shift Clerks X X Emergency Director X X -X X X T5C Manager X X X X X Core Technical / Core Physics Coordinator X X X Chemistry / Core Damage Assessment Coord. X X X X X X Engineering Coord. X X X I (Elec. & Mechanical) Operations Support Coordinator X X X X Maintenance Support Coordinator X X Radiation Protection Coordinator X X X X X X A&nin. Coordinator X X Data Facility Coord. X X T5C Clerical /Adnin. Support Personnel X X Copenunicators X X X 5tatus Boards Coord. X X X (1) (1) Security Supervisor / X X l Security Coordinator X Security 5taff (1) either or both

  • See Paragraph 9.4 of EPP-2-202
    • NEO Participation in Fire Brigade Drills and Consnunication test / drills fulfills the requirement for participation in facility drills PROCEDURE NO.:

EIP-2-102 REV. NO.: 4 PAGE 12 0F 13

A ATTACHMENT 1 TRAINING REQUIREMENTS MATRIX (PAGE 2 0F 2) e l i ]T s 6 5 2 3 lj. I.= 3 8 I' 5 8 -8 W, W gt s oK E J K g [ 8 I g = x a p-g I IE gg E '. 5 &E 2 2 E2 {

1. {,:

h 3v

E t
- g i s em 8:

3 5 1 ga a s = s. = - 4 a4 t a- -s -: -: -s 1.;5 4;5 ;;5 G) s$ 4: E 5 UE 55 5 i5E e eD Ej 35 3 3_ st 3" s tja t g 3j RBS Emergency Plan 33 35 33 3. Training Matrix {s, g g (( g,p g g j g (( g g (( 05C Coordinator X X x Radiation Protection Foreman X X Chemistry Advisor X X X X X Maint. Personnel X X Nuclear Chemistry X X X Technicians Radiation Protection Technicians X X X X Recovery Manager X X X X X EOF Manager X X X X X Radiological Assessment Coord. X X X X X X X Asst. Raoiological Assessment Coord. X X X X X X Offsite Team Coord. X X X X X Radiation Protection Advisor X X X X X Operations Advisor X X X Technical Advisor X X X Administrative / Logistics Advisor X X EOF / Clerical Admin Support X X Prompt Motif. X System Opert. X j Events Info. Team X X X 5 tate / Parish Liaisons X X X X G5U 5pokespersons X X X Joint Infantation Center Director X X X Joint Information Cen.ar Staff X X Asst. JIC I I I I I ~ l I Director i X X X i _-i I PROCEDURE NO.: EIP-?40: REV. NO.: 4 PAGE 13 0F 11 _ - _ _ _}}

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