ML20151H570
| ML20151H570 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/03/1983 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20151H531 | List: |
| References | |
| PROC-830303, NUDOCS 8305040655 | |
| Download: ML20151H570 (84) | |
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j REVISION LOG SHEET ij ~JA.4 .i Revision Date: PORC 2-4~-83 thru 2-14-83 (issued 3-3-83) ft . f( - - 9 i. This log sheet must be retained as the last page of the Browns Ferry ....g Implementing Procedures Document. .* - -{'h <-g G .A Inserted by: Date Inserted: h .j j Pages to be Removed New Pages to be Inserted dfy. 7 Part Pane Number Revision Part Pane Number Revision s .i ~ ~ Table of Table of /i l Contents 1 of 1 10/19/82 Contents 1 of 1 2/8/83 7 5 l j IP-2 1 of 3 12/21/82 IP-2 1 of 3 2/4/83 ff l 2 of 3 12/21/82 2 of 3 2/4/83 3 3 of 3 12/21/82 3 of 3 2/4/83 ^ IP-3 1 of 2 12/21/82 IP-3 1 of 2 2/4/83 2 of,2 12/21/82 2 of 2 2/4/83 IP-4 1 of 2 12/21/82 IP-4 1 of 2 2/4/83 2 of 2 12/21/82 2 of 2 2/4/83 IP-5 1 of 2 12/21/82 IP-5 1 of 2 2/4/83 2 of 2 12/21/82 2 of 2 2/4/83 IP-6 IP-6 1 of 4 12/21/82 1 of 4 2/14/83 2 of 4 12/21/82 2 of 4 2/14/83 3 of 4 12/21/82 3 of 4 2/14/83 4 of 4 12/21/82 4 of 4 2/14/83 IP-10 2 of 6 4/22/82 IP-10 2 of 6 2/8/83 (Continued next page) t O 8305040655 830426 PDR ADOCK 05000259 F PDR ---e mm .----m..-----a----.- -,,.--eeieem y,,,,, ,wy,,9-m.-----e.-.w%g .vy-,----ry. 7-y-,, y-y-y ce- &y - -we,.,,.yww9,-----.=
2 7 24 wg Y .i r .?} q REVISION LOG SHEET (Continued) Revision Date: PORC 2-4-83 thru' 2-14-83 (issued 3-3-83)
- 2 This log sheet must be retained as the last. page of the Browns Ferry
~f Implementing Procedures Document. 1 Paaes to be Removed New Paaes to be Inserted .fj Part Paac Number Revision Part Page Number Revision ~ IP-12 1 of 1 4/22/82 IP-12 Cover Page 2/8/83 ~' 1 of 1 2/8/83 IP-23 ~~ IP-23 Attachment E 1 of 1 12/21/82 Attachment E 1 of 1 2/8/83 List of List of Effective Effective Pages 1 of 10 2/4/83 Pages 1 of 10 3/3/83 2 of 10 2/4/83 2 of 10 3/3/83 3 of 10 2/4/83 3 of 10 3/3/83 9 of 10 2/4/83 9 of 10 3/3/83 N
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~ NAf BFN-IPD u. List of Effcetiva Pcg w (1 Page 1 of 10' ...Q 03/03/83 ( TENNESSEE VALLEY AUTHORITY m . _. g BROWNS FERRY NUCLEAR PLANT IMPLEMENTING PROCEDURES DOCUMENT q .i .] LIST OF EFFECTIVE PAGES - ;j This List of Effective Pages must be retained with the Browns Ferry Nuclear _{ Plant Implementing Procedures Documents. Procedure Page A Part Number Subdivision Number Date/Rev. No. 'j 3 BFN List of Effective h Pages 1 of 10 03/03/83 1 2 of 10 03/03/83 -1 3 of 10 03/03/83 .] 4 of 10 11/01/82 mit 5 of 10 11/01/82 - 6 of 10 11/01/82 .f 7 of 10 11/01/82
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.. _ ~ ~ 8 of 10 02/04/83 9 of 10 03/03/83 i ~' 10 of 10 11/01/82 i Table of Contents 1 of 1 02/08/83 IP-1 Coversheet 10/19/82 ~.2 Preface 1 of 1 10/19/82 j IP-1 1 of 11 10/19/82 ] 2 of 11 10/19/82 3 of 11 10/19/82 4 of 11 10/19/82 I 5 of 11 10/19/82 6 of 11 10/19/82 7 of 11 10/19/82 i 8 of 11 10/19/82 9 of 11 10/19/82 10 of 11 12/06/82 11 of 11 10/19/82 4 IP-2 Coversheet 06/15/82 1 of 3 02/04/83 - 2 of 3 02/04/83 3 of 3 02/04/83 I -+ t
~ ~ kDij} BFN-IPD 4 List cf Effsetiva Prges '.;j Page 2 of 10 f; 03/03/83 qi LIST OF EFFECTIVE PAGES (Con't) k = Procedure Page j Part Number Subdivision Number Date/Rev. No. 2 -J BFN IP-3 Coversheet 06/29/82 s ' I of 2 02/04/83 1 2 of 2 02/04/83 j Table i 1 of 1 10/19/82 -9 Table 2 1 of 1 10/19/82 s IP-4 Coversheet 10/19/82 k4 1 of 2 02/04/83 d 2 of 2 02/04/83 d Table 1 1 of 1 10/19/82 Table 2 1 of 1 10/19/82 't 9 IP-5 Coversheet 06/29/82 .3 1 of 2 02/04/83 1 ~~ 2 of 2 02/04/83 } Table 1 1 o f l' 10/19/82 -i s Table 2 1 of 1 10/19/82 1 4 IP-6 Coversheet 06/29/82 l 1 of 1 04/22/82 i 1 of 4 02/14/83 I 2 of 4. 02/14/83 3 of 4 02/14/83 4 of 4 02/14/83 ~, IP-7 Coversheet 06/29/82 b 1 of 1 12/21/81 1 of 2 12/21/82 2 of 2 12/21/82 IP-8 Coversheet 06/15/82 1 of 5 12/21/82 .o 2 of 5 12/21/82-3 of 5 12/21/82 j 4 of 5 12/21/82 5 of 5 12/21/82 1 of 1 12/21/81 IP-9 Coversheet 06/15/82 1 of 1 12/21/82 t s --._m- __y_ m.
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.s BFN-IPD List of Effective Pages 'y Page 3 of 10 3 03/03/83 'j f] LIST OF EFFECTIVE PAGES (Con't) O Procedure Page 'j Part Number Subdivision Number Date/Rev. No. _q ~
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's Coversheet 06/29/82 1 of 6 06/30/81 2 of.6 02/08/83 '? 3 of 6 04/22/82 3a of 6 04/22/82 4 of 6 06/30/81 j 5 of 6 12/21/81 1/ 6 of 6 06/30/81 J g 1 of 2 06/29/82 2 of 2 06/29/82 j A 1 of 1 06/30/81 B 1 of 1 Rev. O ~ 1 of 1 Rev. 0 ~ 'I of 1 Rev. O 1 of 1 04/22/82 1 of 1 Rev. 0 1 of 2 06/30/81 2 of 2. 06/30/81 Atta'chment 8 1 of 2 06/30/81 2 of 2 06/30/81 IP-11 Coversheet 06/15/82 1 of 2 ~12/21/82 2 of 2 10/06/81 IP-12 Coversheet 02/08/83 1 of 1 '02/08/83 IP-13 1 of 2 06/16/81 2 of 2 06/16/81 IP-14 Coversheet 06/29/82 1 of 6 10/19/82 2 of 6 10/19/82 3 of 6 10/19/62 4 of 6 10/19/82 j l 5 of 6 10/19/82 l 6 of 6 10/19/82 1 m - ,r,.. .-.__p.- _,----.,,--...,.-___,----.,.7_
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- Lk Lict of Effcetiva'Pcg;c j@j Page 9 of 10
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.4 -h /s' LIST OF EFFECTIVE PAGES (Con't) ~ d sc Procedure Page Part Number Subdivision Number Date/Rev. No. li[' BFN IP-20 s (Cont'd) Attachment C ' 1 of 1 06/29/82 1 Attachment D 1 of 1 10/19/82
- ) i Figure 1 1 of 1 12/21/82
[ . Figure 2 1 of 1 12/21/82 f 3 IP-21 Coversheet 06/15/82 1 of 1 12/21/82 3
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2 of 2 12/21/82 i -? Figure 1 1 of 1 12/21/82 3 -s Figure 2 1 of 1 04/22/82 4 ~ IP-22 Coversheet 06/15/82 1 of 2 12/21/82 2 of 2 12/21/82 j 06/29/82 IP-23 Coversheet 1.of 5 12/21/82 1 2 of 5 10/19/82 i 3 of 5 12/21/82 4 of 5 10/28/82 5 of 5 12/21/82 12/21/81 ' Attachment A 1 of 1 i ~ Attachment B 1 of 1 12/21/82 Attachment C 1 of 1 06/29/82 Attachment D 1 of 1 12/21/82 Attachment E -1 of 1 02/08/83 e 6 h e b y __-r.--
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- BFN, FEB 081Mnts
'1" Table of Co l <a -) RROWNS FERRY NUf't F AR Pf. ANT ~ ~ 0 RADIOLOGICAL EMERf1RMCY PROCEDURRM - :l 9 IP-1 Emergency Plan Classification Logio gg .IP-2 Notifiction of Unusual' Event - i3 A l IP Alert
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IP-4 Site Area Emergency IP-5 General Emergency y') .id IP-6 Activation of the Technical Support Center O. IP-7 Activation of the Operations Support Center j 1 IP-8 Personnel. Accountability and Evac'uation .j IP-9 Evacuation of Construction Services Personnel IP-10 Medical Emergency Eroc,edures IP-11 Security and Access Control 'IP-12 Local Recovery Center 1 IP-13 Deleted IP-14 Health Physics Procedures IP-15 Emergency Exposure IP-16 Recovery Procedure 1 IP-17 Emergency Equipment and Supplies l IP-18 Potential' Release Eval'Ution' Proce' dure . 2 es. ~ IP-19 Operation of the Emergency Data Information System IP-20 Technical Support Center (TSC) Operation IP-21 Operations Support Center (OSC) Operation 'IP-22 Long Term Operation IP-23 Communication System IP-24 Earthquake Emergency Plan e Revision A s e-wee e. . ee ^ --.7- .w--
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'~4'j BFN, IP-2 e,- FEB 041983 ~ NOTIFICATION OF UNUSUAL EVENT - 1.0 PURPO9E 1.1 Provide for timely notification of apprcpriate j individuals and organizations of a NOTIFICATION OF '5 j UNUSUAL EVENT. ~' -i 1.2 Provide for periodic reanalysis to determine whethe.' the NOTIFICATION OF DNUSUAL EVENT should be cancelled, continued or upgraded to a more serious classification. 2.0 INSTRUCTIONS (3 Initinta nag ..a 2.1 Shift Engineer notify Operations Duty Specialist (40- 200, 50-0200,or 51-0200) within 5 minutes of declaration of j NOTIFICATION OF UNUSUAL EVENT. .j Give the following: j i a. Ycur name. b. drowns Ferry Nuclear Plant. l c. NOTIFICATION OF UNUSUAL EVENT. d. Time of incident.- I e. Brief description of incident. [ f. Plant condition (whether stable or deteriorating). g. Unusual release of, radioactivity (yes or no). h. Direction wind is coming from (degrees) and speed (meters /second). (Use 300 ft. info. if available). 2.2 Operations Duty Specialist will return call to verify I authenticity. 23 Shif t Engineer will notify the following of the event: eRevision A i 4 4 ee a 1 = y y,-,, .~ __yg e.w-n a--' M m -- = -
s 3 ..'.) ~ ~. _y g 3 Page 2 of 3' ? - r. BFN-IPD BFN, IP-2 3 t m i (Initials) (Time) . FEB 041983
- a. Other Shif t Engineer. (When assigned) b.
STA (PA i Operations Section Su'p'ervisor R. Hunkapillar c. Decatur ~ DR Operations Supervisor Tommy Jordan Muscle Shoals DR Operations Supervisor A. Burnette Florence d. Plant Superintendent ' G. T. Jones Decatur 4.. Assistant Plant Superintendent J. E. Swindell ( Decatur DR Assistant Plant Superintendent J. R. Pittman e. Public Information Officer R. C. Boyer 2. 18 Shif t Engineer will notify the NRC of NOTIFICATION OF UNUSUAL EVENT by red phone. Give a brief description. Maintain an open line until released by NRC. cRevision eV L h l
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1,., E 041983 1 2.5 At least every two hours, or more frecuentiv. if on tions y Marrant, the Shift Engineer will reevaluate the event using 'm The Shif t Engineer on the unaffected unit (s) will (if * ~J IP-1. assigned) handle additional communications. d e a.- If the situation no longer exist, inform the personnel y notified in step 2.1 thru 2.4. j -3 b. If the condition warrants' upgrading to a higher 't classification, initiate the appropriate procedure. .M -Q g '. 3
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.d s- . q y;g ' ~ . f" ' i ' CPnga 1 ef 2 BFN - IFD ): EFN, IP-3 .] FEB 041983 ~~ cI O ALERT .1. 0 Purcose. '~ 1.1 Provide for timely notification of appropriate individuals and organizations of an ALERT. ~ 1.2 Provide for periodic reanalysis to determine whether the ALERT TI should be cancelled, continu'ed, or upgraded to a more serious 1.! classification, j. jl N 2.0 INSTRUCTIONS . A [ Initials Ii 1
- l 2.1 Shif t Enstineer notify Operations Duty Specialist t
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4 , within 5 minutes of declaration of ALERT. !;f ' Give the following: .M ~':. a. Your name + b. Browns Ferry Nuclear Plant j c. ALERT ~ d. Tit.a of incident j e. Brief description of incident j i f. Plant condition (whether stable or deteriorating) l g. Unusual release of radioactivity (yes or no). If yes, calculat'e release rate (s) in /ZC1/sec from Table 1 and 2. Rolease rate ' /lCi/sec. / / h. Direction wind is coming from (degrehs) and speed = (meters /second). (Use 300 ft. info if available). 2.2 Operations Duty Specialist will return call to verify authenticity. 5 23 Shirt Engineer will evaluate conditions. If required, initiate area (by public address) or total plant (by siren) evac':ation. Refer to IP-8. eRevision l
I ~ _...j.,; .'d ' (,l ePeso 2 cf 2 } 4 . w.. BFN - IPD .. 'T '.' ~ c: BFN, IP-3 '~ ,n FEB 041983 Initiah Tima t ~ 2.4 Shift Engineer's Clerk will: '.l By a.' !!otify other Shift Engineer (when assigned) of ALERT. .j ci b, Notify-STA (PAX -of the ALERT. "3 1 ' U! ~ c.
- Notify Chem, Lab Superviisor (pal of ALERT.
.' 1 d. Notify' HP Shif t Supervisor (PAX, of ALERT. Direct them,, 'f .,3 to activate IP-14. . A., e. Notify Public Safety Supervisor (PAX of ALERT. Direct' ~;! .,them to activate IP-11 (Coatrol. Rooms Only) and IP-7 m] Vg 2.5 Shif t Engineer's Clerk will: pt ') a. Initiate IP-6. ,..] 1 3 2.6 . Shif t Engineer will notify NRC of' ALERT by. red phone. Give'a' brief descripi, ion. Maintain an open line until released by NRC. a,l Note: NRC naI sendAresponse team to the site. 3- .3 - - - 2 7. . Time permitting, the Shif t Engineer will implement operation of ? t.he TSC (IP-20), to include activation of Dimension telephones and placing required desks in hall in front of TSC. ' li 2.8 At least every two hours, or more frecuentiv if conditions l 'l warrant. the Shift Engineer / Site Emergency Director will 3 reevalute the event using IP-1. s a. If the situation no longer exists or should be downgraded, inform all personnel previously notified. b. If the condition warrants upgrading to a higher classification, initiate the appropriate procedure. 29 Refer to Table 1 for a quick estimate of maximum offsite' do'se for a stack release. and Table 2 for a quick esticate of the site boundary do1e.for buildinc-release. 1 [ ' eRevision d \\ l 0 9 G -6 g M v-., c n
~ +- ,j, ... { CParo 1 cf 2' 1 53 4 BFH - IPD '4-A ~ ' BFN, IP !! a SITE AREA EMERGENCY FEB 041983 -i ~ 1.0 Purcose - d 1.1 Provide for timely notification of appropriate individuals ..i and orSanizations of a SITE AREA EMERGENCY, ,i 1.2 Provide for periodic reanalysis'or the situation to' ':l determine whether the SITE AREA EMERGENCY ahould be cancelled, continued, or upgraded to a more serious classification. N JJ .Y 2.0 INSTRUCTIONS f n ,1 Initials Time 2.1 Shift Engineer notify Operations Duty Specialist g 4lk 7.t
- iit.hin 5 minutes of declaration or
.1 SITE AREA EMERGENCY.
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- -y Give the following: ',i : a-a. Your name b. Browns Ferry NucIeat - Plant i a 2 / 7c. SITE AREA EMERGENC 7- ' ~ ' - - X '#-- i' d.- Time of' incident' .? m. .Brief description hf incident ~ u ~ ~ e. a f. Plant condition (whether stable or deteriorating) g. Unusual release of radioactivity (yes or no).' If yes, calculate release rate (s) in /4Ci/see from Table 1 and 2. Release rate! /4Cf/sec. ~ / h. Direction wind is co=ing from (degrees) and ~ speed (meters /second). (Use 300 ft. info. if available). 2.2 Operations Duty Specialist will return call to verify authenticity. s 23 Shift Engineer will evaluate conditions. If required, initiate area (by public address) or total plant (by ,i siren) evacuation. Refer to IP-8. s. Note: Precautionary site evacuation should be considered. ' Revision \\,s 1
A ,~ lj jf .f i... CP g2 2 cf 2 BFN -IPD Q ~ ' ~ BFN, IP-4 c' FEB 041983 ~ I Initials Time 2.4 Shift Engineer's Clerk will: f ~ I a. Notify other Shif t Engineer (when assigned) of SITE
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AREA EMERGENCY b. No'tify STA (PAX, , of J E AREA EMERGENC c. Notify Chem Lab Supervisor (PAX. of SITE AREA ~ EMERGENCY, d. Notify HP Shift Supervisor (PAX. of SITE AREA EMERGENCY. Direct them to activate IP-14. ,,;.l ..a-e. Notify Public Safety Supervisor'(PAX. of SITE AREA EMERGENCY. Direct them to activate IP-11 and IP-7 A ~.1 2.5 ' Shift Engineer's Clerk will: !2 i a. Initiate IP-6. .. h. 2.6 Shif t Engineer will notify NRC of SITE AREA EMERGENCY by red phorie'.' Give e brief description., Maintain an open line ,_._....until released by NRC. m. 4 , Note:. NRC will probably send a response team to the site. j 27 Time permitting, the Shif t Engineer will implement operation 1 of the TSC (IP-20), to include activation of Dimension j telephones and placing required desks in hall in front of 3 TSC. 2.8 At least every two hours, an more frecueDU2 if conditions _ arrant. the Shift Engineer / Site Emergency Director will w reevaluate the' event using IP-1. ~~ a. If the situation no longer exists or should be downgraded, inform all personnel'previously notified. b. If the condition warrants upgrading to a higher classification, initiate the appropriate procedure. 29 Refer to Table 1 for a quick estimate cf g ximum Offsite ~ dose for a stack release, and Table 2 for a quick estimate of site boundary dose for buildine release. 8 Revision - 1 / b g
'3 7:-F _ ).f : GPega 1.cf 2 BFN-IPD --) I. ',4 ~ BFN, IP-5 3 FEB 041983 s m GENERAt EMEncENCr 1.0 Puroose 1.1 Provide for timely notification of appropriate individuals and-organizations of a GENERAL EMERGENCY. ,3 1 1.2 Provide for periodic reanalysis of the situation to determine j ythether the GENERAL EMERGENCY should be cancelled or .. l cent,inued. ,'j ~ y 2.0 INSTRUCTIONS f 1 - !'j 1 Tnitials Time rG 2.1 Shift Engineer notify Operations Duty Specialist g. . *k'.. f,] .ithin 5 minutes of declaration of .y _ GENERAL EMERGENCY. "'c Give the following: ..( i
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'.,i a. Your name b. Browns Ferry Nuclear Plant i ~ ....' ic.,'CENERAL EMERGENCY C _. x _ t A. d._. Time of.incid.ent.. }' ~. e.p. Brief description of incident '
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'5 4 f. Plant condition (whether stable or deteriorating) g., Unusual release of radioactivity (yes or no). If yes, calculate release rate (s) in />Ai/see fr'on Table 1 and 2. Release rate pCi/sec. h. Direction wind is cooing from (degrees) and speed (Heters/second). (Use 300 ft. info. if available).
- i. Recocmended initial protective a'ctions for the public:
(Activate warning systes and advise public to take shelter, tune radio or TV to a local station,. and avait further instructions). 2.2 Operations Duty Specialist will return call to verify authenticity. 23 Shif t Engineer will evaluate conditions. If required, initiate area (by public address) for total plant (by siren) evacuation. Refer to IP-8. Note: Site evacuation is probable under these conditions. eRevision /tk ~ 'I
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.s o y,.. 'IQ _ ' ('i 'Page 2 of 2 bf BFN - IPD BFN, IP-5 B33 Initials Time 2.4 Shif t Engineer's Clerk will: ) ' a., Notify other Shif t Engineer (when assigned) of GENERAL EMERGENCY q b. . Notify STA (PAX ')*of GENERAL EMERGENC1 c. Notify Chem Lab Supervisor (P 1 of CENERAL EMERGENCY. +i* FA d. Notify HP Shift Supervisor (PAX, of GENERAL EMERGENCY. 'l Direct them to a'ctivate IP 14. 'I cii e. Notify Public' Safety Supervisor (PAX of GENERAL 7 EMERGENCY. Direct them to activate IP-11 and IP-7. ~3 2.5 Shif t Engineer's Clerk will:. a. Initiate IP-6 ~ 2.6 Shif t Engineer will notify NRC of CENERAL EMERGENCY by red ~ r' phone. Give a brief description. Maintain an open line until s released by NRC. 1 Note: 'NRC will probably send a response team to the site. I 1 27 Time pe mitting, the Shif t Engineer will imple=ent operation of the TSC (IP-20), to include activation of Dimension telephones and placing required desks in hall in front of TSO. ~ 2.8 At least every two hours, or more frecuentiv'if conditions warrant. the Shift Engineer / Site Emcrgency Director will reevaluate the event using IP-1. a. If the situation no longer exista or should be downgraded, inform all personnel previously notified. 2.9 Refer to Table 1 for a quick estimate of maximum offsite do;;. for a stack release. and Table 2 for a quick estimate of the i site boundary dose for building release.
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.h 3 ~i ^ CPeg2 1 ef 4 / BFN - IPD BFN - IP-6 ,[ At tachment 1 FEB 141983 ATTACEMcNT'1 Contact one or more AS NOTED. MESSAGE: "We have a/an (ALERT) (SITE EMERGENCY) (GENERAL EMERGENCY) condition existing at the plant. This is no_t. a drill. Please report to the Technical Support Center [ immediately as the (Job Title)." SITE EMERGENCY DIRECTOR (CONTACT 1) INITIAL TIME CONTACTED ELL h HOME George Jones Decatur Jim Swindell Decatur John Pittman Decatur Ray Hunkapillar Decatur OPERATIONS MANAGER (CONTACT 1) Ray Hunkapillar Decatur Muscle Shoala , Tommy Jordan-n_ _.. _.; 3.,_. _.3 z .g_ .. ~. ~ u- ,g -= ,,~ ~A. L. Burnette i Florence TECHNICAL ASSESSMENT MANAGER (CONTACT 11 J. E. Swindell Decatur W. C. Thonison Decatur Dwight Mims Decatur MAINTENANCE MANAGER (CONTACT 11 John Pittman Decatur John Hiller Decatur Tom Cosby Florence REP COMMUNICATOR (CONTACT 1) l Terry Chinn Athens Bill Roberts Athens l Carroll Rozear De catur eRevisien d 1 - i 1
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- ii ECRETARY (CONTACT 9)
~ INITIALS TIME CONTACTED 2AX Mli HOME d Glenda Harrison Athens Betty Riley N Athens Cathy McChristian Athens Jane Page Lecatur Brenda Owens Athens Jacque Garner , Florence TSC COMMUNICATOR (CONTACT 1) Bob Metke ' Athens Dwight Mims Decatu. ...~- - ,, Roger McPherson Decatur NRC COMMUNICATOR (CONTACT 1) Bill Roberts Athens Terry China A' thens 4 ' Carroll Rozear 'Decatur OPERATIONS SPECIALIST (CONTACT 1) S. Burnette Florence Tocmy Jordan Muscle Roy Smallwood Killen
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.e. ~~ CPag2 3 cf 4 -., '.l. J ~ ..J' BFN - IPD 'l f ' BFN, IP-6 ~ ~j ttachment 1 3 EB 141983 ~j: HEALTH PHYSICS (CONTACT 2) INITTAL TIME CONTACTED f.AX dei HOME ~.: Allen Sorrell i Florence-i Ed Cargill l Athens i Wayne Simpkins Athens Herman Crowson Florence RADIOCHEMICAL ENGINEER (CONTACT 1) Bill Thonison j Decatur i Ausie Clement Athens. Weaver Burton Decatur i' i REACTOR ENGINEER (CONTACT 1) ( Hhntsville Earl Nave \\
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Mike Wingo ] Decatur f~ (,'- Bill Williamson ' Killen SYSTEMS & TEST ENGINEER (CONTACT 1) Dwight Mims Decatur R. McPherson Decatur, Paul Romine Florence MECHANICAL ENGINEER (CONTACT 1) Tink Haney = Athens Charlie Wages
- Sheffield Jim Walker Athens l
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'.1 1' ,] CPaga 4 ef (*,. J J* BFN - IPD BFN, IP-6 ~I u-FEB 14'1983 c (?d. FLFCTRICAL ENGINEER (CONTACT 1) INITTALS TIME CONTACTED ,, PAX DIM HCHE '4 4 Tom Cosby Florence Dwight Thompson Athen s Stan Solley Rogersville Howard Vail Huntsville INSTRUMENT & CONTROLS ENGINEER (CONTACT 1) Ron Burns 'Decatur Bob Irby Athens PSO ' ENGINEER (CONTACT 1) , Leonard Bynum Huntsville A Lee Haygood Killen * =T, Lu PUBLIC SAFETY SERVICE SUPERVISON'(CONTACT 1) --. Ralph Jackson Killen James Brazel Athens Glenn Lard Florecce. COMPUTER' SPECIALIST (CONTACT 1) Larry Johnson Athens Russ McNutt Athens CUALITY ASSURANCE (CONTACT 1) Larry Jones Decatur Jim Norris Decatur ^ Larry Parvin Athens Russeil Perry Athens {, PUBLIC IN70RMATION OFFICER (CONTACT 1) Bob Boyer Decatur Beeper { 8 Revision AYg 1 s -a--
a %. q ~ a'f+ 'Page 2 of 6 S' i BFN-IPD BFN-IP-10 A.y FEB 081983 - q 23 armanization amt Duties af..tha Medical Emernanc'y Resconse 23gga _r.' 82 3 1 The medical emergency response team consist of a health physica j technician, an assistant shift engineer, public safety officer, ,j chemical laboratory analyst, and nurse,.The team will be supported by ,] assistant unit operators as available.
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232 Duties and responsibilities of the various members of the response i team - d 2.3 2.1 Team Leader (Unit 1 assistant shift engineer) will: n a. Lead the team in and out of the area by the most direct and/or .Ta appropriate route (with proper considerations of hazarda to ] members of the team and the oportional functioning of the 1+ sj facility. b.- Directs handling of the overall effort. ?j c. Maintain communiction with the shift engineer and keep him advised -
- j of situations, needs, and progress of the team.
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Notify shift engineer, "as~ required, to contact an ambulance and j hospital. (. 'e. Give plant phone number to ambulance service and obtain from 5 .i ambulance service the method of contacting them after their departure from the sito. i _ :1 2 3 2.2 Public Safety Officer will: a. Proceed to the emergency. b. Administer medical treatment. 82323 chemical laboratory analyst will: a. Proceed to the emergency after obtaining medical kit from Medical Services Office. i b. Assist in medical treatment, rescue, and respond as directed. 2 3 2.4 Health Physics technician will: a. Proceed to the emergency. b. Monitor environment and patient as needed. c. Advise team members concerning proper protective clothing, . equipment, and occupancy time needed for their prctection. fn kj ' Revision Af l ' f e o m e ww-a w I + w-ww vi m -+w--v----- -T v
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%..R ~ - ~. ,0 s; ' M w, j- .a. ,a ~ i TENNESSEE VALLEY AUTHORITY, - c-j BROWNS FERRY NUCLEAR PLANT 1 -s .:{ +
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.4 4 RADIOLOGICAL ERERGENCY PLAN LOCAL RECOVERY CENTER BFN, IP-12 c.(. j u s -s s ~ ,..s f Approved by: h ' Plant Su intendent FEB 081983 ~ 0,, n.. e 1%l i w
M .q .,}* P g')Tl'cf 109j BFN - IPD 4 BFN, IP-12 p',. FE8 0.81982) J Local Recovery Center ~ E 1.0 Purpose x. This procedure describes the purpose, location, and communications d for the Local Recovery Center (LRC). fj, 2.0 Description ,y 2.1 The purpose of the Local Recovery Center is to provide a . Q nearsite facility for TVA recovery management as well as d s NRC emergency response personnel and other emergency and/or j recovery personnel. N}f 2.2 The LRC will be located in the NRC Resident Inspectors' ] office on the plant site. y 3.0 Communication ] 3.1 The LRC has voice consnunication capabilities to enable personnel to communicate with the CECC, KEC, and the TSC. ? The following voice communication is available in the LRC a area: j 1. Bell telephone (Dimension) and Bell telephone (Standard) 2. TVA microwave telephone system .t 3. Federal telecommunications system (FTS) 3.2 Meterological information and dose rate calculations are also available to LRC personnel thru Emergency Data Information System. (See IP-19), 3.3 Other equipment available for use by LRC personnel include: t 1. Facsimile machine 2. Copy.machipe 3. Hand calculators i s 4. Tape recorders 5. Plant-specific drawings, manuals, and procedures l c,j
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- "iG Vilr ilADIO INSTR.I'CTION3 7 D EP'I - IP-23
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.B 0 & 19e ~ p .ti r!.\\ f E - Depress SP**i' hurton on BlWICO control box. Switch toggle switch e. (. .in r:.i to-t elephone to 71 position. Lif t rad io-teleptione handset; depress touch s oi:e : u t tons i or mouch : one mi..iber desired. First di;;ic depresced snust he held '..i. n !..n.: nnunis to i t 'uninati-rs d light on radio-telephone to activate the radio. .. p r e. ..i.I i o r in i n h:in.t a i. rip ro s. ra n mi i t, e::" :,.l lo i..u s t l.ur:/ Nu.ibe rs ':.i.i io :ee I 1 1.ct t nrn
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'Ask the officer to' M 'b h J h'ig@ contact the. Radiological Health Staff by phone or ./ ir NdM/.S f ' W.".$.T.f;su.IgME{.h6 telephone? numbers 1for;these ag g (No. : 215) ;and: relay,.the ' accident information. ". Alternate @ x s:4 W.p&f 6 VT;Q'hh.UM.Th&&%&Wy.W-U{y: h&S!MMQSTVA~ Radiological; Emergenc Notification Directory.c. & &sQ$$ (SeetheDNP..& Ji*~ !a ' - W WM.b?d ~ ~ j '...f;; N/W*6'.2;2 ':R The NUCtPR Emergency-Duty. Officer: % m M. wr,)mpmM.p,% J.. j f.M i ~ $. m.d% b. a.. m,., + w'%w i H.3.3.m. m,y. Notification, Board.);7..c, @. y y Vd.pd q m.s.v. t . g a., w ; m +.: n.. m A s. m, ;: o...-:WM.,4Q;6? uyy*.
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..I REVISION LOG SHEET I
Revision Date:
February 14,, 1983 i
'I This log sheet must be retained as the last page of the central Energency
~
Control Center Implementing Procedures Document.
~'
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Inserted by:
Date Inserted:
j
'l Pages to be Removed New Pages to 'e Inserted c
)
Part Page Number Revision
.__Pa rt Page Number Revision IP-2 Cover Page Rev. 2 IP-2 Cover Page Rev. 3
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2 of 4 Rev. 2 2 of 4 Rev. 3 3 of 4 Rev. 2 3 of 4 Rev. 3 4 of 4 Rev. 2 4 of 4 Rev. 3 l
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'U CECC.- IP-2 DNP EMERGENCY DUTY OFFICER /CECC DIRECTOR /DNPEC DIRECTOR NOTIFICATION OF UNUSUAL EVENT
-N,j
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if J;
Prepared By:-
W. E. Webb, Jr.
k,
. C Approved By:
Date:
L 9/25/81 (m-
\\)
()
- i Rev. No.
Date Revised Pages Rev. No.
Date Revised Pages i
0 9/25/81 All 3
2/14/83 2,3,4 1
2/18/82 2
2 OCT 2 61982 m
The last page of this procedure is. Number 4
l e
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.g CECC-IPD IP-2 Page 2 of 4 1
Rev. 3
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(Time / Initials) e 6.0 PROCEDUF2 REQUIREMENTS A
/
6.1 Notify the ODS immediately upon arrival at the CECC/DNPEC.
/
6.2 Notify the Manager of Power Information Duty
' Officer. (See the DNP Notification Board.)
/
6.3 Contact the Site Emergency Director and obtain a current status report.
4 9
~~
The principal means of contacting the plant emergency y
. organizations is.by use of the direct line in the DNPEC.
1 Alternatives to the direct line are listed in the TVA j.
Radiological Emergency Notification Directory.
N
.f 6.4 Notify the following for information only:
(See the DNP Notification Board.)
/
6.4.1 H. J. Green
,~
(
/
6.4.2 H. L. Abercrombie x-
/
6.4.3 Hugh Parris
/
6.4.4 J. A. Coffey
/
6.5
- Notify t'he NSRS Duty Engineer.
(Contact the Knoxville TVA operator, identify yourself, and provide your telephone number. Request the operator to page the NSRS Duty Officer and to have him return your call.)
/
6.6
- Notify the Power Nuclear Safety Staff Duty Officer.
(See the Dh? Notification Board).
l
/
- 6.7 Notify the appropriate Department of Energy (DOE)
Operations Office regarding the existence of an emergency l
condition at a TVA facility if their assistance will be l
required. (See the TVA Radiological Emergency Notification Directory.)
- 6.8 Periodic Updating of TVA and Other Emergency Organizations / Personnel i
b/
- Addendum
- Revision.
m
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. +w 3 CECC-IPD
- 4 IP-2 Page 3 of 4-
[
Rev. 3
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^
- 6.8.1 Ob'tain an update on plant status fro's the Site Emergency Director or DNPEC Director approximately j
every hour (or as often as provided by the Site
')
Emergency Director or DNPEC Director if more frequent j
j than once per hour).
N 1
- 6.8.2 Maintain periodic contact with other organizations y
that have been notified.
~dc s
e
- 6.8.3 Provide the personnel contacted as permanent CECC
_J' Director and DNPEC Director with periodic updates of a
the accident.
m a
- 6.9 Actions to be Taken Should the Accident Degrade
'j{
Into a More Serious Condition
~j f
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- 6.9.1 Notification 1
5
- 6.9.1.1 Notify the appropriate State agency as to the nature "1
of the degraded condition.
y l}
- 6.9.1.2 Contact the CECC Director and inform him that he 3
should report to~Ehe-CECC. Review the new emergency j
situation with the CECC Director".
t 3
3.
- 6.9.1.3 Contact the DNPEC Director and inform him that he
]
should report to the DNPEC. Review the new emergency y
A situation with the DNPEC Director.
1
- 6.9.1.4 Contact the MSEC Director and review the new emergency i
situation. If radioactive releases are occurring at a
the plant, request estimated dose rates.
- 6.9.2 Assessment
- 6.9.2.1 Should the emergency degrade to an Alert, Site Area Emergency, or General Emergency, continue to obtain periodic updates of conditions from the Site Emergency t
l or DNPEC Director.
- 6.9.2.2 Establish centact with the MSEC Director immediately after determining plant status, review the status with him, and include the data he can supply regarding offsite doses and environmental sampling to other organizations as appropriate.
l
- 6.9.2.3 Request support from outside organizations as needed to cope with the emergency.
- 6.9.3 Relief of Duties as CECC or DNPEC Director
- Revision 1 l l
l l
a A.7:,y
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'U-CECC-IPD IP-2
> T?l; Page 4 of 4 4.0 Rev. 3 A
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^3 s.a
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- 6.9.3.1 The EDO turns over the responsibilities of CECC and y
DNPEC Director upon the arrival of the permanent CECC y
and DNPEC Directors.
7
- 6.9.3.2 The EDO will brief the. permanent CECC and DNPEC Ns Directors on events which may have developed during
' j) their travel.
c;
,y;
- 6.10 Actions to be Taken When the Accident Terminates Yj w;
- 6.10.1 Should the accident be of a nature such that it is Tt terminated almost immediately after it is declared, h'j inform all parties that the notificat~ ion is for
'j information purposes only and the incident has already
.7 4
been terminated.
d
~. J
- 6.10.2 Upon notification of the termination of a Notification of Unusual Event, the EDO is responsible for notifying l,;
all parties and individuals informed of the emergency yj in sections 6.3 through 6.6 of this procedure.
Q
- 6.10.3 The EDO makes himself,available for review of the accident events at the convenience of TVA management.
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U iTED STATES GOVERN 3tETT Memorandum TENNESSEE VALLEY' AUTHORIT(.
TO IIolders of the Central Emergency Control Center Implementing Procedures Document FRO 3!
E. K. Sliger, Supervisor, Radiological Emergency Preparedness Section, 1470 CST 2-C'
^T" MM 171983
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SUBJECL CENTRAL EMERGENCY CONTROL CENTER IMPLEMENTING PROCEDURES DOCL?iENT The attached revision is for inclusion in your copy of the subject manual.
Section 10.1.5.3 of the Radiological Emergency Plan requires manual holders to acknowledge receipt of revisions. An extra copy of the distributica list is attached for use as your acknowledgment receipt. Please sign the back of the receipt and return it to Barbara Layton, 1700 CST 2-C.
If responsibility for this manual is transferred to.another individual, please note this on your acknowledgment receipt.
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REVISION LOG SHEET 5
Revision Date:
MAR 171983 This log sheet must be retained as the last page of the Central Emergency
' 'i Control Center Implementing Procedures Document.
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Inserted'by:
Date Inserted:
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,3 Pages to be Removed New Pages to be Inserted J)4
.4 Part Page Number Revision Part Page Number Revision j
IP-3 Cover Page Rev. 2 IP-3 Cover Page Rev. 3 1 of 7 Rev. 2 1 of 10 Rev. 3
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2 of 7 Rev. 2 2 of 10 Rev. 3 3 of 7 Pev. 2 3 of 10 Rev. 3 t
4 of 7 Rev. 2 4 of 10 Rev. 3
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6 of 7 Rev. t 6 of 10 Rev. 3 5 of 7 Rev. 2 5 of 10 Rev. 3 7 of 7 Rev. 2 7 of 10 Rev'. 3 4
8 of 10 Rev. 3 9 of 10 Rev. 3 10 of 10 Rev. 3 Att. I 1 of 1 Rev. 2 Att. I 1 of 1 Rev. 3 Att. 2 1 of 1 Rev. 2 Att. 2 1 of 1 Rev. 3 Att. 3A 1 of 1 Rev. 2 Att. 3A 1 of 2 Rev. 3 2 of 2 Rev. 3 Att. 3B 1 of 1 Rev. 2 Att. 3B 1 of 1 Rev. 3 1
Att. 4 1 of 3 Rev. 3 2 of 3 Rev. 3 3 of 3 Rev. 3 Att. 5 1 of 2 Rev. 3 2 of 2 Rev. 3
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.: 36 CECC - IP-3 1
CECC
'l AI,ERT. SITE AREA EMERGENCY, AND GENERAL EMERGENCY
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- s, Prepared By:
W. E. Webb, Jr./)
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Q Approved By:
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p9/25/81 p Da te:
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Rev. No.
Da te Revised Pages Rev. No.
Da te Revised Pages
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9/25/81 All 3
MAR 171983 AH 1
2/18/82~ _ ___2 -
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]CT 261982 All The last page of this procedure is Number 20 i
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CENTRAL EMERGENCY CONTROL CENTER ALERT, SITE AREA EMERGENCY, AND GENERAL EMERGENCY
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1.0 PURPOSE i
This procedure is designed to direct the CECC Director and staff to ensure consistent, accurate, and timely response to the events of an
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3 accident. This procedure further serves to identify the necessary information to provide for prompt, accurate, public-protective action recommendations to appropriate State authorities.
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- 3 2.0 SCOPE
(."
?b This procedure covers anticipated requirements of the CECC Director j
and staff during an emergency classification of Alert, Site Area y
Emergency, or General Emergency.
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3.0 REFERENCES
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Radiological Emergency Plan. 4.0 ABBREVIATIONS AND DEFINITIONS ,-~. (,,
- CECC - Central Emergency Control Center
- DNPEC - Division of Nuclear Power Emegency Center j
y
- EDO - Emergency Duty Officer
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- KEC - Knoxville Emergency Center i
- 0DS - Operations Duty Specialist
- MSEC - Muscle Shoals Emergency Center
- NCO - Nuclear Central Office
- NMC - Nearsite Media Center
- NRC - Nuclear Regulatory Commission
- TSC - Technical Support Center 5.0 RESPONSIBILITIES l
5.1 Upon notification by the TVA Operations Duty Specialist (ODS) I that an emergency condition exists, the DNP EDO is responsible for establishing initial operation of the CECC. The EDO is relieved by the designated CECC Director upon arrival. The CECC Director has general responsibility for verification of notifica-tion and overall accident assessment during an emergency condition. l 5.2 To assist the CECC Director in carrying out the responsibilities of the Director's position, a CECC staff is available. I
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- U Rev. 3 Responsibilities of positions in the CECC are listed below
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5.2.1 CECC Director c 'i
- 1. Directs and coordinates overall TVA activities associated with the emergency.
.1
- 2. Ensures that appropriate measures have been taken to Y
terminate the condition causing the emergency, pro-tects employees and the public, initiates recovery from the emergency, and informs the news media and public.
- 3. Ensures that Federal, State, and local agencies are
-A notified in accordance with established procedures and lj that they are kept fully informed of all aspects of T) the emergency.
- 4. Reviews with the DNPEC and Radiological Health Staff
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representatives the onsite and offsite' consequences .d
- 4 and assesses the adequacy and need for measures taken for protection of the_public.
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- 5. Commits TVA resources and provides'necessary 5
I' information to assist the State, Federal, and local 3 k,- agencies to the extent possible. j s
- 6. Maintains accurate records of decisions made and j
actions started and completed.
- 7. Coordinates TVA's efforts with State and Federal agencies involved in the offsite aspects of the emergency.
- 8. Makes recommendations to State and local agencies on protective actions for the public.
5.2.2 MSEC Communicator
- 1. Responsible for maintaining communications with the MSEC and ensures continuous and timely information flow related to the dose assessment activities and information required for transmittal to the State (see attachment 4).
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- 2. Maintains a summary of key offsite events and ensures i
this summary is distributed to all emergency centers. This summary is to be updated, at a minimum, on an hourly basis. ()
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- 3. Ensares the CECC status boards are maintained (see attachment 3). Will call-in additional personnel as necessary.
- 4. Provides pertinent offsite assessment information to the DNPEC Emergency Prep'aredness and Protection Branch i} '
representative for transmittal to the TSC (see j$ attachment 5). ~
- 5. Assists the CECC Radiological Health Staff representative in tracking offsite releases, decisions, responses, etc.
r N 5.2.3 Radiological Health Staff Representative .i AE
- 1. Serves as the CECC Director's chief advisor in offsite 1'
radiological assessment matters. . ;} }
- 2. Ensures that all appropriate information provided from the MSEC, related to the dose assessment activities 1
and results, is accurate and timely. }
- 3. Coordinates with the'NSEC Communicator in tracking pertinent information and ensuring ' status board infor-c
mation is current and accurate and that dose assessment (, information for the State is kept current and accurate.
- 4. Responsible for ensuring that any technical clarifications required by the State related to TVA's i
dose assessment activities are being provided. 5.2.4 State Communicator.(TVA Employee)
- 1. Acts as TVA's primary communicator and source of information to the State.
- 2. Acts as contact for the State to clarify any descrepancies between information supplied from the CECC and any other TVA or non-TVA organization as they pertain to TVA-related activities.
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- 3. Responsible for ensuring pertinent information related to plant status, onsite responses, and TVA's dose / environs assessment activities is being provided to the State (see attachment 4).
This information i shall be provided, at a minimum, hourly, or when significant changes occur. Communication contact shall be made at least at 30-minute intervals.
- 4. Assists the State as requested in providing TVA resource assistance to the State.
i Entire Page Revised 3 i y es y-7+ m- ---r e------- -m-iy E-- -m-e w:-----r-w- -u-
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- 5. Provides the State with name and number for technical clarifications related to dose / environs j
assessment matters.
- 6. Assists the MSEC Communicator 'as necessary in
~ maintaining summary of ke'y offsite events and -j maintaining status boards (see attachment 3). W
- 7. Assists the State Coordinator (State Government Representative) as necessary to keep him briefed of the plant situation and coordinating responses to State inquiries, etc.
,9 5.2.5 State Coordinator (State Government Representative) j s i The State Coordinator's role in the CECC is to observe -1 events taking place, licensee actions, and advise the A' State agencies appropriately throughout the emergency. ~ He will receive assistance as necessary from the State Communicator. 5.2.6 NRC The NRC role in the CECC is to observe and advise as ( appropriate with licensee decisions and actions. 5.2.7 Power Information Staff
- 1. Responsible for monitoring the emergency from the CECC, drafting and coordinating written TVA news releases, and securing approval of the draft from the CECC Director. -
- 2. Responsible for assisting the media in covering the activities of the emergency.
- 3. Responsible for periodically briefing the CECC Director on specific media concerns and actions.
- 4. Responsible for activating and coordinating activities of the nearsite press center.
5.2.8 Clerical Staff
- 1. Operates CRT terminals of the CECC Emergency Computer System.
- 2. Maintains log of events.
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- 3. Answers telephones.
- 4. Maintains CECC organization board.
- 5. Operates Dimension telephone co'nsole.
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- 6. Operates Panafax machine.
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- 7. Other duties as assigned by CECC staff.
6.0 PROCEDURE REQUIREMENTS '5 NOTE: The EDO, will follow this procedure until relieved' by the } permanent CECC Director. The permanent CECC Director debriefs ai the EDO and continues with the procedure where the EDO left 'l off. i 6.1 Notifications 6.1.1 Upon reporting to the CECC, the Director will verify that j communications have been established with the MSEC and State and that the nature-of the accident has been reviewed with them. s i
- 6.1.2 The CECC Director shall ensure that notification of the
\\ event is made to all those listed on the Notification x Check Sheet (attachment 1), as appropriate. Priority is noted on the attachment. 6.1.3 The CECC Director shall ensure that those listed on attachment 1 are kept briefed periodically, as appro-priate, on the prog'ression of events and in particular when the accident classification is either upgraded or downgraded. 6.1.4 Upon termination of the emergency, the CECC Director shall ensure that all attachment I notificaticas are made as appropriate. 6.2 Accident Assessment
- 6.2.1 The CECC Director is responsible for directing TVA's overall response to the emergency.
- 6.2.2 The CECC Director shall ensure that all i n fo rmation required by State authorities to perform their assessment function and carry out necessary protective actions is being provided to them in a timely and accurate manner (see attachment 4).
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d. 6.2.4 The CECC Director shall schedule periodic briefings (at a J . minimum, hourly) with the DNPEC Director, CECC 2 Radiological Health Staff representative, Power Q Information Director, 'and others as necessary to review g all appropriate information as identified in ,c a attachment 2. '4 i .9 6.2.5 The CECC Director shall ensure that the accident information collected is posted appropriately on the [ status boards (responsibility of the MSEC Communicator). W The information en the status boards must be kept current for the benefit of the CECC Director, DNPEC Director, and their staffs. i.f m 6.2.6 The CECC Director shall ensure that a chronology of '] offsite activities is ireing kept and distributed to other emergency centers as appropriate. This responsibility is 4 assigned to the MSEC Consnunicator. 4 (,. i 6.2.7 The CECC Director shall ensure that appropriate offsite assessment information is transmitted to the DNPEC. ,l 6.2.8 The CECC Director shall utilize the DNPEC and MSEC i (through the CECC Radiological Health Staff representa-4 tive) to continuously review the onsite and offsite a'ccident informati~on, respectively. These reviews should attempt to identify trends in key information (attach-ment 2) and emphasize display and analysis of data for l predictive purposes. Assessments in these areas shall be i updated, at a minimum, on an hourly basis and all TVA and State personnel briefed appropriately. 6.2.9 The CECC Director shall ensure that any descrepancies -z.- between TVA and State information/ assessment are resolved and clarified appropriately. ~ 6.2.10 Potential Release Evaluation 7 6.2.10.1 A potential release evaluation is continuously performed by the KEC. This evaluatio'n. is based on the present plant conditions. The-results are provided to the MSECJfor an associa'ted dose assessment, which 'ss'then provided to the CECC. Entire Page Revised 6 ~ e e %g
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- 6.2.10.2 The CECC Director shall determine the need f
for a potential release and associated dose - y{ '3 evaluation based on a potential change in plant conditions. The need for such an .. i evaluation shall be based on the continuing .u,4 assessments being'made by the DNFEC and MSEC l'j staffs and the information obtained from 4 trending key plant and offsite parameters.
- - 7&
6.2.10.3 If the CECC Director decides this evaluation M ~ is needed, he shall instruct the DNPEC h*j director to request the KEC. perform the _? necessary calculation to predict the O-potential release. The DNPEC shall also [M provide the KEC with the assumptions and ' 'i postulated plant status that should be O (i.e., expected LOCA, los_s of containment, @4 considered when performing the calculation etc.). 2.3
- d 6.2.10.4 The KEC will calculate the predicted release M
and provide it,to the MSEC who will calculate Ci an associated offsite dose.s The MSEC will j then provide the results of the dose a / assessment to the CECC. ( .i 6.3 General Operation j s m 6.3.1 Physical Security Requirements for CECC iq ,The CECC Director has responsibility for physical security Q of the CECC, DNPEC; and ODS work area. The CECC Director s or his representative will inform the Public Safety i ~ ~ ^ ',. Officer (stationed at the entry vay to'the CECC) if ,7 < visitors requesting admittance to the emergency center
- t should be allowed to enter. Permament members of the ODS, d
CECC, and DNPEC~ staffs will have identification badges. l 6.3.2 Power Informati$n Liason. l The CECC Director will coordinate with the DNPEC Director the selection of one person to serve as a technical J l advisor to the, Power Information Duty Of'ficer in the CECC..The person will be responsible for providing a non-y- ~ technical interprecation of the event for the CECC /- Information Office staff. l ~,- l l f l ? t I l Entire Page, Revised / 7 J' ( ,/ ~ ~ m
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- If the NHC is to be staffed, the CECC Director will
~~ coordinate with the DNPEC Director and the CECC-Radiological Health Staff representative the selection of j two people to serve as technical advisors to the TVA j spokesperson located there. sone will serve as a .7 y Radiological Health Advisor and the other as a Plant j Operations Advisor. These people will be responsible for y assisting the TVA spokesperson in interpreting the 3 approved press releases and events taking place. 6.3.3 Discussion with Other TVA Organizations ) The CECC Director will discuss the efforts being taken by h_j TVA to mitigate the consequences of an accident with 4-representatives of other TVA organizations as needed. 3 Representatives are identified for the Radiological Health 1 Staff, Division of Medical Services, Division of Water .j Resources, the Office of Power Nuclear Licensing Staff, y Office of Quality Assurance, and the Office of the General 9, l Counsel (Law). These representatives may report to the CECC if necessary or desirable. Notification information ' 3 is provided in the TVA. Radiological Emergency Notification Directory. s s (' 6.3.4 CECC Briefings ' \\. The CECC Director shall conduct periodic h-iefings for the ] entire CECC staff to update the emergency situation for 3 them. 6.3.5 State Advisors For a classification of SITE AREA EMERGENCY OR GENERAL EMERGENCY, the CECC Director will coordinate with the DNPEC Director the selection of two people to serve as technical advisors to the State Emergency Operations Center. The CECC Director will authorize travel to the State Emergency Operations Center for the purpose of providing technical information, advice, and interpreta-tion to state personnel. Those personnel will set up a 12-hour shift rotation upon arrival to provide 24-hour l coverage for the State. The CECC Director may provide additional personnel as needed.
- Primary duties of the state advisors are as follows:
A. Technical explanations and clarification on plant status. [.
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%MN IP-3 a e Page 9 of to Rev. 3 me 1-se B. Assist the State by keeping them informed of '[' available TVA resources. -] C. Assist the State in describing / clarifying TVA's -j. I response to the emerge _ncy, understanding TVA's 1 emergency organization,' key TVA staff positions, -3 etc. ]:q 6.3.6 NCO Management Support at the Plant ,j s,, For a classification of SITE AREA EMERGENCY OR GENERAL -4 EMERGENCY, the CECC Director will dispatch a senior j{ management representative to the site to act as senior
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advisor to the Site Emergency Director. This individual will advise the Site Emergency Director en TVA policy ci matters and act as an additional interface with the NRC as JJ ff} necessa ry. He will not control events or operations at the site. If 24-hour. operation is necessary, 2 people should be sent.
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-_7 6.3.7 Relief of Duties N ~ ~ l Should the accident be exp'seted to last for an extended e i period, the CECC Director originates a? schedule for 3' k relief. The duties of CECC Director should only pass to . ;t 4 individuals identified as alternates for the CECC '4 Director'c position. However, for a short period of time, the CECC Director may delegate the authority of CECC Director to a member of the CECC staff until an alternate CECC Director can arrive. The CECC Director also directs his staff and the CECC representatives to prepare a schedule for their-relief to ensure the-necessary staff - and representatives of the CECC are available for the duration of the emergency. The CECC Director gives the DNPEC Management Services representative a copy of the schedule, and he notifies the individuals of the time they are to report. t 6.3.8 Coordination of Recovery Efforts Appropriate recovery efforts shall be initiated upon termination of the emergency. The CECC Director is responsible for assessing and coordinating the recovery efforts for response to an emergency in accordance with the general guidelines provided in the Radiological Emergency Plan. The CECC Director will inform each emergency center when the emergency is terminated and the recovery phase begins. As judgement and events determine, (j '* Revision 9 i' e h ar' y-9,--wpwy---r 7- - - - - T-v w- -ywwy.- -.-+ ,w-ye, ,w -.ily ,wg.--w.-- w -mae.-.,+- -.w 4- -+-- +ev -u n --6-=- - + '
1 A CECC-IPD IP-3 Page 10 of 10 ._j Rev. 3 additional resources outside of TVA may be required to mitigate the consequences of an emergency. The CECC Director contacts these offsite agencies as needed. Some of the groups from whom support can be obtained include: NRC, DOE (Oak Ridge), DOE (Savannah River), INPO, MAELU, 4 NSSS vendors, and other nuclear utilities. i d 6.3.9 Termination of the Emergency Upon termination of the emergency, the CECC Director and staff will make themselves availa' ole for review of the accident. .s j 3 hI.g }he i 'S g_ 4 J i ( i f l 1
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lk. '. x.t CECC-IPD j] " IP-3 7 Page 1 of I =~ Rev. 3 j g 4 Notification Check Sheet j t 1. Power Information Duty Officer (DNP) 3 .s 2. Nuclear Security (DNP) -j A 3. H. J. Green (DNP) [Qy 4. Hugh Parris (DNP) /.1 M I:j 5. J. A. Coffey (DNP) (d 6. H. L. Abercrombie (DNP) k 7. NSRS' Duty Engineer '2 1 y 8. Power Nuclear Safety Staff (DNP)1 3A 9. NSSS W ador (REND)1
- 1 10.
INPO (REND)1 .) s Et 11. DOE (REND)1 - ~ - ('~ a., 12. Division of Purchasing (For Notification of the Insurance j Underwriters) (REND)1 L 3 -:q 13. South Central Bell (REND)1 I NOTE: DNP--Indicates appropriate contact and number is located on the Division of Nuclear Power Notification Beard. I REND--Indicates appropriate contact and number is located in the'TVA Radiological Emergency Notification Directory. i I n IResponse to the emergency takes top priority. These notifications shall be made when there is time and staff to do so. 2Contact the Knoxville TVA operator, identify yourself and provide telephone number. Request that the operator page the NSRS duty officer and have him return your call. l ] Entire Page Revised l 11 i 1 d-dM '=-
g < :fe CECC-IPD ~ IP-3 3 -1 Page 1 of 1 p INPUT FOR Rev. 3 -) e CECC ACCIDENT ASSESSMENT o 9 HEAT REMOVAL CAPABILITY '), -FUEL INTEGRITY SOURCE TERMS T CONTAINMENT INTEGRITY _ MET DATA RADI0 ACTIVITY IN CONTAINMENT FIELD SURVEY DATA
- j PbNTASSESSMENT
'q DOSE ASSESSMENT q KEC +-TSC IP-18 pj 1.u
- d DNPEC
' MSECC ~ s l I 5 ( 1 4 s, SITE EMERGENCY CECC DIRECTOR ] DIRECTOR 1 mr PROTECTIVE ACTION RECOMMENDATIONS h 9
- 12
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-. ;,i g._; i ,.N CECC-IPD IP-3 > 'D y A o' Page 1 of 2 Rev. 3 N .i . A 11 3 CECC STATUS BOARDS / ACCIDENT ASSESSMENT j RADIOLOGICAL /0THER STATUS
- 4 a
I~ RELEASE POINT: STACK (ELEVATED) .d GROUND LEVEL W DIFFUSER <j OTHER -,y Vd II. RELEASE MIX: NOBLE GAS RATE pCi/s* '. d5 IODINE RATE pCi/s*
- w
- %*
PARTICULATES RATE pCi/s* 3+d; GROSS ACTIVITY RATE pCi/s* '.9 cN ' III. MET DATA: a CURRENT FORECAST 21 ft WIND SPEED m/s m/s 9 PLUME DIRECTION 'i WIND DIRECTION .i STABILITY CLASS d ( ~' PRECIPITATION j, V.
- 1 IV.
DOSE RATE (REM /H) TOTAL BODY THYROID SECTOR
- 1 O
SITE BOUNDARY ?j 2 MILES a 5 MILES 4 10 MILES DOSE (REM) TOTAL BODY THYROIDi SECTOR PROTECTIt'E ACTION CUIDE (PAG) 5 REMS 25 RENS SITE BOUNDARY 2 MILES 5 MILES 10 MILES V. PREDICTED DOSE RATES (REM /H) at h (DETERMINED BY IP-18) DOSE RATE (REM /H) TOTAL BODY THYROID SECTOR SITE BOUNDARY 2 MILES 5 MILES 10 MILES (,
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,.] a (Continued) .'l 'M;S DOSE (REM) TOTAL BODY THYROID' SECTOR PROTECTIVE ACTION GUIDE (PAG) 5 REMS 25 REMS ' 1, .- 4 SITE BOUNDARY 2 MILES . f(j 5 MILES r 10 MILES .['"e] -yg .s imn 'f 'd
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6 CECC-IPD 1 IP-3 1 B i Page 1 of 1 {' Rev. 3 C <i %-$e. ' B 7 CECC STATUS BOARD / ACCIDENT ASSESSMENT 9 PLANT STATUS ONSITE/0FFSITE
SUMMARY
- x I. HEAT REMOVAL CAPABILITY I. TVA RECOMMENDED PROTECTIVE ACTIONS j II. FUEL INTEGRITY II. STATE PROTECTIVE ACTIONS TAKEN III. RADIOACTIVITY IN CONTAINMENT III. ONSITE RESPONSE ACTIONS IN PROGRESS IV. CONTAINMENT INTEGRITI IV. OFFSITE ORGANIZATION SUPPORT NEEDED .j : 7 k. '.? - 'i. I.) g -j
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.5 .,3 ~ CECC-IPD IP-3 AtLachment 4 Page 1 of 3 ../ Rev. 3 is
- Attachment 4 INFORMATION PERIODICALLY SUPPLIED TO THE STATE
/ t ~. 1. This is at 1 (name) (title) (telephone) J 2. The BFN' SQN WBN BLN 3. Emergency Classification is: Alert Site Area Emergency } .q General Emergency j 11 4. Declared at. CST on (date). 5. Recommended Protective Actions: 1 6. The type of actual or projected release is: Airborne I Waterborne Surface Spill s Other 7. The estimated duration (is/was): Not known Hours 8. The release began at: CST 9. The radioactive material released (is/was): Noble Gas microcuries/sec Jodines microcuries/sec* Particulates microcuries/sec 10. Release point (is/was): Ground Level Stack Other 11. The quantity of radioactive material released was: microcuries 12. Meterological Conditions: ~ Wind Speed: meters /second Wind Direction From:
- (degrees)
To:
- (degrees)
Stability Class: (A, B, C, D, E, F, or G) Precipitation: (Y/N) (Amount)
- Addendum 16
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- Attachment 4 (Continued) 13.
Actual'or Projected Dose Rates: 4 ' Child Thyroid i Distance Whole Body (rem / hour) ^' frem/ hour of inhalation) Site Boundary 2 Miles 5 Miles d - 5 10 Miles Og Other ] 14. Inegrated Dose (in rems): Distance Whole Body (rem) Child Thyroid (rem) l Site Boundary s 2 Miles (f 5 Miles s 10 Miles Other 15. Measurement of surface radioactive contamination, onsite or offsite: 16. Emergency actions at plant include: (i.e., plant evacuation) 17. Onsite support (needed/ requested) from offsite organizations: 18. Plant prognosis is: (stable, deteriorating, etc.) 19. The status of reactor core cooling / heat removal capabilities is: (j
- Addendum 17 a---
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- Attachment 4 (Continued)
,.? 20. Reactor coolant system integrity is: +- $ a 3 -a kd 21. Fuel integrity is: 22. Containment radioactivity is (concentrations and inventories): [ I)
- .4
~.4. 23. Containment integrity is (primary and/or secondary): c{ 4 i + f*
- s
(., g t"'. i,v:^*l
- Addendum 18
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'R m :3 ~ CECC-I I'D 'jj IP-3 Page 1 of 2 Rev. 3 4 '*** Attachment 5 'j TECHNICAL SUPPORT CENTER INFORMATION FORM. r ..} RADIOLOGICAL /0THER STATUS s ~ a:;; I. RELEASE POINT: Stack (Elevated) '_ q Ground Level 5 Diffuser S ?.$ Other Jl II. RELEASE MIX: Noble Gas Rate pCi/s 23} Iodine Rate pCi/s E Particulates Rate pCi/s G] Gross Activity Rate pCi/s o III. MET DATA: Wind Speed m/s m/s (( Plume Direction m/s m/s Wind Direction m/s m/s ~. Stability Class m/s m/s s Precipitation m/s' m/s IV. DOSE RATE (REM /H) TOTAL BODY THYROID . SECTOR
- _3 Site Boundary 5
Two Miles Five Miles Ten Miles DOSE (REM) TOTAL BODY TifYROID SECTOR Protective Action Guide: 5 REMS 5 REMS 25 REMS i l Site Boundary l Two Miles l Five Miles l Ten Miles l V. PREDICTED DOSE RATES (REM /H) at b l (DETERMINED BY IP-18) l
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- ATTACHMENT 5
.i ] TECHNICAL SUPPORT CENTER g?;j INFORMATION FORM -1 DOSE RATE (REM /H) TOTAL BODY THYROID SECTOR 1 Site Boundary Two Miles .2 Five Miles Ten Miles 1 4
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DOSE (REM) TOTAL BODY THYROID SECTOR 2]4 Protective Action Guide: 5 REMS 5 REMS 25 REMS .{ Site Boundary .j Two Miles j Five Miles-Ten Miles 1 3 VI. TVA-RECOMMENDED PROTECTIVE ACTIONS & s, 3 s (- u. Lj i VII. STATE OFFSITE PROTECTIVE ACTIONS:
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-lh nf ':43 ..:.2 ..j o en-I t REVISION LOG SHEET Q q Revision Date: hUIR 171983 .i ~> i .) This log sheet must be retained 4s the last page of the Central Emergency ~ *] Control Center Implementing Procedures Document. 1 ~< Inserted'by: Date Inserted: 1 -iA %? .:} Pages to be Removed New Pages to be Inserted il 21s Part Page Number Revision Part Page Number Revision _;,[} O IP-3 Cover Page Rev. 2 IP-3 Cover Page Rev. 3 Sj 1 of 7 Rev. 2 1 of 10 Rev. 3 j 2 of 7 Rev. 2 2 of 10 Rev. 3 I l 3 of 7 Rev. 2 3 of 10 Rev. 3 4 of 7 Rev. 2 4 of 10 Rev. 3 -{ \\ 5.of 7 Rev. 2 5 of 10 Rev. 3 g3 6 of 7 Rev. 2 6 of 10 Rev,. 3 - "j 7 of 7 Rev. 2 7 of 10 Rev. 3 i} 8 of 10 Rev. 3 4 9 of 10 Rev. 3 '} 10 of 10 Rev. 3 j Att. I 1 of 1 Rev. 2 Att. I 1 of 1 Rev. 3 l Att. 2 1 of 1 Rev. 2 Att. 2 1 of 1 Rev. 3 Att. 3A 1 of 1 Rev. 2 Att. 3A 1 of 2 Rev. 3 2 of 2 Rev. 3 Att. 3B 1 of 1 Rev. 2 Att. 3B 1 of 1 Rev. 3 4 Att. 4 1 of 3 Rev. 3 2 of 3 Rev. 3 3 of 3 Rev. 3 a Att. 5 1 of 2 Rev. 3 2 of 2 Rev. 3 LJ 4 ~ w -.---r---- ,---.--m--
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I w -1 f 3 vi ~ REP-IPO .e CECC - IP-3 .. i CECC u ALERT. SITE AREA EMERGENCY. AND GENERAL EMERGENCY d
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A. Prepared By: W. E. Webb, Jr. M j Approved By: % AjI/ n iw ?! p Date: 9/25/81 s ( y (.. i Rev. No. _Da te Revised Pages Rev. No. Da te Revised Pages -j 0 9/25/81 All-3 MAR 171383 A11 s 1 2/18/82 2-2 _0CT 2 6 882 All The last page of this procedure is Number 20 ? 1 L - e C 1 F ~% [
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o. CENTRAL EMERGENCY CONTROL CENTER 3's . ALERT, SITE AREA EMERGENCY, AND GENERAL EMERGENCY d 1.0 PURPOSE N '.3 ?; This procedure is designed to direct the CECC Director and staf f to ensure consistent, accurate, and timely response to the events of an accident. This procedure further serves to identify the necessary j information to provide for prompt, accurate, public protective action i recommendations to appropriate State authorities. _)
- i 2.0 SCOPE J{
i; This procedure covers anticipated requirements of the CECC Director and staff during an emergency classification of Alert, Site Area Emergency, or General Emergency. j '.1
3.0 REFERENCES
l i Radiological Emergency Plan. 4.0 ABBREVIATIONS AND DEFINITIONS ("
- CECC - Central Emergency Control Center
- DNPEC - Division of Nuclear Power Emegency Center
- EDO - Emergency Duty Officer
- KEC - Knoxville Emergency Center
- 0DS - Operations Duty Specialist
- MSEC - Muscle Shoals Emergency Center
~
- NC0 - Nuclear Central Office
- NMC - Nearsite Media Center
- ***NRC.- Nuclear Regulatory Commission
- TSC - Technical Support Center 5.0 RESPONSIBILITIES 5.1 Upon notification by the TVA Operations Duty Specialist (ODS) that an emergency condition exists, the DNP EDO is responsible for establishing initial operation of the CECC. The EDO is relieved by the designated CECC Director upon arrival. The CECC Director has general responsibility for verification of notifica-tion and overall accident assessment during an emergency
~~ condition. 5.2 To assist the CECC Director in carrying out the responsibilities of the Director's position, a CECC staff is available.
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'7 A IP-3 Page 2 of 10 Rev. 3 s.. Responsibilities of positions in the CECC are listed below: 5.2.1 CECC Director hi J
- 1. Directs and coordinates overall~ TVA activities I
associated with the emergency. n.
- 2. Ensures that appropriate measures have been taken to terminate the condition causing the emergency, pro-tects employees and the public, initiates recovery J
from the emergency, and informr. the news media and 's public. e
- 3. Ensures that Federal, State, and local agencies are il notified in accordance with established procedures and d
that they are kept fully informed of all aspects of 'i the emergency. -j l i
- 4. Reviews with the DNPEC and Radiological Health Staff f]
representatives the onsite and offsite consequences -1 and assesses the adequac3 and need for measures taken e for protection of the-public.
- 5. Commits TVA resources and provides necessary
( information to assist the State, Federal, and local agencies to the extent possible. s-
- 6. Maintains accurate records of decisions made and actions started and completed.
- 7. Coordinates TVA's efforts with State and Federal agencies involve'd in the offsite aspects of the emergency.
- 8. Makes recommendations to State and local agencies on protective actions for the public.
5.2.2 MSEC Communicator
- 1. Responsible for maintaining communications with the MSEC and ensures continuous and timely information flow related to the dose assessment activities and information required for transmittal to the State (see attachment 4).
I
- 2. Maintains a summary of key offsite events and ensures this summary is distributed to all emergency centers.
This summary is to De updated, at a minimum, on an hourly basis. (j
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- 3. Ensures the CECC status boards are maintained (see
. attachment 3). Will call.in additional personnel as i necessary. 1 e
- 4. Provides pertinent offsite assessment information to i
l the DNPEC Emergency Preparedness and Protection Branch l representative for transmittal to the TSC (see s attachment 5).
- 5. Assists the CECC Radiological IIcalth Staff representative a
in tracking offsite releases, decisions, responses, etc. a 5.2.3 Radiological Health Staff Representative (c
- 1. Serves as the CECC Director's chief advisor in offsite d
radiological assessment matters. Q i
- 2. Ensures that all appropriate info'rmation provided from
.3 j the MSEC, related to the dose. assessment activities ~ ~~. and results, is accurate and timely. t
- 3. Coordinates with thbS'EC Communicator in tracking pertinent information and ensuring status board infor-
^ mation is current and accurate and that dose assessment information for the State is kept current and accurate.
- 4. Responsible for ensuring that any technical f
clarifications required by the State related to TVA's dose assessment activities are being provided. 5.2.4 State Communicator-(TVA Employee) 1 Acts as TVA's primary communicator and source of information to the State.
- 2. Acts as contact for the State to clarify any descrepancies between information supplied from the CECC and any other TVA or non-TVA organization as they pertain to TVA-related activities.
l l
- 3. Responsibie for ensuring pertinent information related l
to plant status, onsite responses, and TVA's dose / environs assessment activities is being provided to the State -(see attachment 4). This information shall be provided, at a minimum, hourly, or when I significant changes occur. Communication contact shall be made at least at 30-minute intervals. i
- 4. Assists the State as requested in providing TVA 7--
resource assistance to the State. l ( Entire Page Revised 3 5 Y- - - - -w-e p y. - i, ----, ,e
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- 5 Provides the State with name and number for technical clarifications related to dose / environs assessment matters.
I
- 6. Assists the MSEC Communicator as necessary in maintaining summary of kep of fsite events and 1
maintaining status boards (see attachment 3). 4 S.
- 7. Assists the State Coordinator (State Government
'1 ~. Representative) as necessary to keep-him briefed of ~ the plant situation and coordinating responses to ~ State inquiries, etc. 4' 5.2.5 State Coordinator (State Government Representative) ,]+
- t The State Coordinator's role in the CECC is to observe j
l events taking place, licensee actions, and advise the f '.d State agencies appropriately throughout the emergency. He will receive assistance as necessary from the State Communicator. 5.2.6 NJR 4 ~, The NRC role in the CECC is to observe and advise as (~' appropriate with licensee decisions and actions. \\~s 5.2.7 Power Information Staff g
- 1. Responsible for monitoring the emergency from the CECC, draf ting and coordinating written TVA news releases, and securing approval of the draf t from the CECC Director. *
- 2. Responsible for assisting the media in covering the
. activities of the emergency.
- 3. Responsible for periodically briefing the CECC Director on specific media concerns and actions.
j
- 4. Responsible for a,ctivating and coordinating activities j
of the nearsite press center, i j 5.2.8 Clerical Staff
- 1. Operates CRT terminals of the CECC Emergency Computer System.
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- 2. Maintains log of events.
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- 3. Answers telephones.
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- 4. Maintains CECC organization bosed.
- 5. Operates Dimension telephone co'nsole.
- 6. Operates Panafax machine.
~LS$
- 7. Other duties as assigned by CECC staff.
[ 6.0 PROCEDURE REQUIRENENTS N, NOTE: The EDO,will foIIow this procedure until relieved by the ]; permanent CECC Director. The permanent CECC Director debriefs j the EDO and continues with the procedure where the EDO left 3 off. tt ni's 6.1 Notifications 4 1 6.1.1 Upon reporting to the CECC, the Director will verify that j communications have been established with the MSEC and j State and that the nature-of the accident has been reviewed with them. s i ,~ (
- 6.1.2 The CECC Director shall ensure that notification of the 4
event is made to all those listed on the Notification -4 Check Sheet (attachment 1), as appropriate. Priority is .] noted on the attachment. 3 6.1.3 The CECC Director shall ensure that those listed on ~ attachment I are kept briefed periodically, as appro-priate, on the prog'ression of events and in particular when the ace,ident classification is either upgraded or downgraded. b 6.1.4 U on termination of the emergency, the CECC Director shall p ensure that all attachment I notifications are made as appropriate. 6.2 Accident Assessment
- 6.2.1 The CECC Director is responsible for directing TVA's overall response to the emergency.
- 6.2.2 The CECC Director shall ensure that all information required by State authorities to perform their assessment function and carry out necessary protective actions is being provided to them in a timely and accurate manner (see attachment 4).
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.. 4 myNg 4 + g s kyfQ CECC-IPD --n' ~n 1 Ip.3 -]j ! Page 6 of 10 .yl A Rev. 3 4i, k.A/ 56 6.2.3 The CECC Director is responsible for making appropriate 4 public protective actions to State authorities. T provides an overview of the necessary [h information required by the CECC Director to make n?Q appropriate protective action recommendations. 31 ~ d 6.2.4 The CECC Director shall schedule periodic briefings (at-a J minimum, hourly) with the DNPEC Director, CECC 4 Radiological Health Staff representative, Power N ]j Information Director, and others as necessary to review all appropriate informatien as identified in g attachment 2. 31 . m 6.2.5 The CECC Director shall ensure that the accident 1% information collected is posted appropriately on the Nl. status boards (responsibility of the MSEC Communicator). - $M The information on the status boards must be kept current for the benefit of the CECC Director, DNPEC Director, and .3 their staffs. 6.2.6 The CECC Director shall ensure that a chronology of ' ?j offsite activities is-being kept and distributed to other M emergency centers as appropriate. This responsibility is ] assigned to the MSEC Communicator. 1 .1 {+ 6.2.7 The CECC Director shall ensure that appropriate offsite 3 assessment information is transmitted to the DNPEC. 2jjg 6.2.8 The CECC Director shall utilize the DNPEC and M5EC 9 i (through the CECC Radiological Health Staff representa-tive) to continuously review the onsite and offsite a ~ accident information, respectively. These reviews should attempt to identify trends in key information (attach-ment 2) and emphasize display and analysis of data for predictive purposes. Assessments in these areas shall be updated, at a minimum, on an hourly basis and all TVA and State personnel briefed appropriately. U l 6.2.9 The CECC Director shall ensure that any descrepancies between TVA and State information/ assessment are resolved j i and clarified appropriately. 6.2.10 Potential Release Evaluation 6.2.10.1 A potential release evaluation is continuously I performed by the KEC. This evaluation is based on the present plant conditions. The l results are provided to the MSEC for an n l associated dose assessment, which is then i provided to the CECC. l %./ Entire Page Revised i 6 1 -,-~e-,-, e-
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- 6 2 10 2 The CECC Director shall determine the need for a potential release and associated dose evaluation based on a potential change in S
plant conditions. The need for such an d evaluation shall be based on the continuing 4 assessments bein'g made by the DNPEC and MSEC q staffs and the information obtained from a trending key plant and offsit,e parameters.
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6.2.10.3 If the CECC Director decides this evaluation' 1 is needed, he shall instruct the DNPEC 1-j director to request the KEC. perform the 4 necessary calculation to predict the j4-potential releace. The DNPEC shall also provide the KEC with the assumptions and d postulated plant status that should be 11 considered when performing the calculation 3 (i.e., expected LOCA, loss of containment, , ij etc.). ~ -j 1 6.2.10.4 The KEC will calculate the predicted release / and provide _it,to the MSEC who will calculate an associated offsite dose. The MSEC will then provide the results of'the dose j assessment to the CECC. j 6.3 General Operation .i s l 6.3.1 Physical Security Requirements for CECC ? The CECC Director has responsibility for physical security of the CECC, DNPEC, and ODS work area. The CECC Director ~ or his representative will inform the Public Safety Officer (stationed at the entry way to the CECC) if visitors requesting admittance to the emergency center should be allowed to enter. Permament members of the ODS, CECC, and DNPEC staffs will have identification badges. 6.3.2 Power Information Liason The CECC Director will coordinate with the DNPEC Director the selection of one person to serve as a technical l advisor to the Power Information Duty Officer in the CECC. The person will be responsible for providing a non-technical interpretation of the event for the CECC l Information Office staff. I I c' f Entire Page Revised 7
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- If the NMC is to be staffed, the CECC Director will coordinate with the DNPEC Director and the CECC -
d Radiological Health Staff representative the selection of .- O two people to serve as technical advisors to the TVA ~' 3 spokesperson located there.- One will serve as a
- '9 Radiological Health Advisor and the other as a Plant d
Operations Advisor. These people-will be responsible for l] assisting the TVA spokesperson in interpreting the 4 approved press releases and events taking place. (j 4 6.3.3 Discussion with Other TVA Organizations -Jq The CECC Director will discuss the efforts being taken by 1 TVA to mitigate the consequences of an accident with 17 representatives of other TVA organizations as needed. ~T Representatives are identified for the Radiological Health' Staff, Division of Medical Services, Division of Water Q Resources, the Office of Power Nuclear Licensing Staff, d Office of Quality Assurance, and the Office of the General "I Counsel- (Law). These representatives may report to the @d CECC if necessary or desirable. Notification information is provided in the TVA-Radiological Emergency Notification Directory. s 6.3.4 CECC Briefings } J ^ The CECC Director shall conduct periodic briefings -for the
- j entire CECC staff to update the emergency situation for
- I them.
6.3.5 State Advisors For a classification of SITE AREA EMERGENCY OR GENERAL EMERGENCY, the CECC Director will coordinate with the DNPEC Director the selection of two people to serve as technical advisors to the State Emergency Operations Center. The CECC Director will authorize travel to the State Emergency Operations Center for the purpose of providing technical information, advice, and interpreta-tica to state personnel. Those personnel will set up a i 12-hour shift rotation upon arrival to provide 24-hour coverage for the State. The CECC Director may provide additional personnel as needed. i
- Primary duties of the state advisors are as follows:
l A. Technical explanations and clarification on plant status. l l
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B. Assist the State by keeping them informed of 4 available TVA resources. jj ' 1 C. Assist the State in describing / clarifying TVA's j response to the emergency, understanding TVA's emergency organization, key TVA staff positions, .] etc. j 6.3.6 NCO Management Support at the Plant J For a classification of SITE AREA EMERGENCY OR GENERAL EMERGENCY, the CECC Director will dispatch a senior -d management representative to the site to act as senior 'zj advisor to the Site Emergency Director. This individual Js, will advise the Site Emergency Director on TVA policy 1 matters and act as an additional interface with the NRC as c5 neces sa ry. He will not control events or operations at .] the site. If 24-hour operation is necessary, 2 people 4 should be sent. ] 6.3.7 Relief of Duties Should the accident be expected to last for an extended period, the CECC Director originates a schedule for ([N relief. The duties of CECC Director should only pass to individuals identified as alternates for the CECC a s_- Director's position. However, for a short period of time, the CECC Director may delegate the authority of CECC Director to a member of the CECC staff until an alternate CECC Director can arrive. The CECC Director also directs his staff and the CECC representatives to prepare a schedule for their Telief to ensure the necessary staff and representatives of the CECC are available for the duration of the emergency. The CECC Director gives the DNPEC Management Services representative a copy of the schedule, and he notifies the individuals of the time they are to report. 6.3.8 Coordination of Recovery Efforts Appropriate recovery efforts shall be initiated upon termination of the emergency. The CECC Director is responsible for assessing and coordinating the recovery efforts for response to an emergency in accordance with the general guidelines provided in the Radiological Emergency Plan. The CECC Director will inform each emergency center when the emergency is terminated and the recovery phase begins. As judgement and events determine, s (;
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additional resources outside of TVA may be required to mitigate the consequences of an emergency. The CECC Director contacts these offsite agencies as needed. Some of the groups from whom support can be obtained include: l NRC, DOE (Oak Ridge), DOE (Savannah River), INPO, MAELU, j NSSS vendors, and other nuclear utilities. 6.3.9 Termination of the Emergency t Upon termination of the emergency, the CECC Director and ~ staff will make themselves available for review of the "ii accident. i i 4 4, - i ~ k ' t 4
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~}3 CECC-IPD '3 IP-3 Page 1 of 1 Rev. 3 j +' Notification Check Sheet I
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{ 1. Power Information Duty Officer (DNP) + 'x 2. Nuclear Security (DNP) } 23 3. H. J. Green (DNP) 4. Hugh Parris (DNP) ) ) 5. J. A. Coffey (DNP) ]s 6. H. L. Abercrombie (DNP) l$I 'l 7. NCRS Duty Engineer 2 y. 1 .j 8. Power Nuclear Safety Staff (DNP)1 '{ 9. NSSS Vendor (REND)1 i 10. INPO (REND)1 l s 11. DOE (REND)1 d ( 12. Division of Purchasing (For Notification of the Insurance .h Underwriters) (REND)1 1:l 13. South Central Bell (IJDiD)t 2 NOTE: DNP--Indicates appropriate contact and number is located on the Division of Nuclear Power Notification Board. ~ 2 REND--Indicates appropriate contact and number is located in the TVA .t Radiological Emergency Notification Directory. l .g l -)) ..L P j 4 IResponse to the emergency takes top priority. These notifications shall be made when there is time and staff to do so. ~ 2Contact the Knoxville TVA operator, identify yourself and provide 3 telephone number. Request that the operator page the NSRS duty officer and have him return.your call. [ v Entire Page Revised 11 i I g w--- . - m 4---p, -se.- - - -, - -,r-
_i 'y, -s,q CECC-IPD IP-3 9 p INPUT FOR Page 1 of 1 W - -c aev. 3 .,q -e CECC ACCIDENT ASSESSMENT - / 4 .:.c; 7 h ~ HEAT REMOVAL CAPABILITY td = -FUEL INTEGRITY SOURCE TERf1S 3 ~ s CONTAINMENT INTEGRITY _ MET DATA
- j RADI0 ACTIVITY IN CONTAINMENT FIELD SURVEY DATA
..:j lln DOSE ASSESSM'ENT h 1 P NT ASSESSMENT ~ KEC & TSC IP-18 e <R / -1 .J., ~~ ~ ', DNPEC 'f1SECC 12 s l i (= 4 q ~ SITE EMERGENCY CECC DIRECTOR 4 c DIRECTOR 3 1.
- j.,
f .e u ~ 4 n l ~ PROTECTIVE ACTION V 7' REC 0f1MENDATIONS y 4 6 .g 4 ( *% o,
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.4 '.. JJ CECC-IPD ,IP-3 A ~' = Attachment 3A - --S Page 1 of 2 . a '!, Rev. 3 3 1 ~ ~ - A ^ CECC STATUS BOARDS / ACCIDENT ASSESSMENT Rt.DIOLOGICA1./_0THER STATUS .x ./ '4 .4 , I. RELEASE POINT: STACK (ELEVATED) c.j c GROUND LEVEL d DIFFUSER +- OTHER ~ i l3 II. ' RELEASE MIX: NOBLE GAS PATE pCi/s* . IODINE RATE pCi/s* s PARTICULATES RATE pCi/s* 2 GROSS ACTIVITY RATE pCi/s* III. MET DATA: CURRENT FORECAST '3 1 [,[ WIND SPEED m/s _m/s E ~ PLUME DIRECTION q ~, l WIND DIRECTION, ~ STABILITY CLASS i PRECIPITATION j (' ' 2 IV. DOSERATE(REM /Hi-TOTAL BODY THYROID SECTOR ?j SITE BOUNDAR'Y l 2 MILES ~ 1 5 MILES rj ~ 10 MILES l -} sDOSE (kEM) TOTAL BODY. THYROID SECTOR PROTECTIVE ACTION GUIDE-(PAG) 5' REMS 25 REMS ~ 1 l SITE BOUNDARY T_. 2 MIISS 4 ~ 5 MILES l 10 MILES' 3 1 l h [ y .,V. ' PREDICTED DOSE RATES (RCI/H) at (DETERMINED BY IP-18) t> ' DOSE RATE (REM /H) TOTAL BODY THYROID SECTOR SITE B0UNDARY 2 MILES l ,5 MILES 10 MILES /
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5 A i I (Continued) 1 .i DOSE (REM) TOTAL BODY THYROID' SECTOR d PROTECTIVE ACTION GUIDE (PAG).5 REMS 25 REMS ] SITE BOUNDARY 2 MILES 5 MILES ] 10 MILES f ] 1 4 A'! Jl '1 t - - ~ ~. I, s i I ( (, e; .j q l 1 l i -+ 1 I i 4 1 1 Revision (pagination) (j 14 1 l l
>,] s.. - g CECC-IPD '.'j IP-3 ' B Page 1 of 1 Rev. 3 h' 'i
- ~; B CECC STATUS BOARD / ACCIDENT ASSESSMENT PLANT STATUS ONSITE/OFFSITE
SUMMARY
, s I. HEAT REMOVAL CAPABILITY I. TVA RECOMMENDED PROTECTIVE ACTIONS II. FUEL INTEGRITY II. STATE PROTECTIVE ACTIONS TAKEN 'i III. RADI0 ACTIVITY IN CONTAINMENT III. ONSITE RESPONSE ACTIONS IN PROGRESS b IV. CONTAINMENT INTEGRITY IV. OFFSITE ORGANIZATION SUPPORT NEEDED j 3 -1 i w 4 ( ~ a J l 4 l
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INFORMATION PERIODICALLY SUPPLIED TO THE STATE i i 5 .d, 1. This is at (name) (title) (telephore) ~ 2. The BFN SQN F4N BLN 3. Emergency Classification is: Alert Site Area Emergency j General Emergency l 4. Declared at CST on (date). , l, 5. Recommended Protective Actions: s 1 6. The type of actual or projected release is: Airborne Waterborne Surface Spill f Other j 7. The estimated duration (is/was): liours ~~ ((_ Not known j i 8. The release began at: CST j l 9. The radioactive material released (is/was): 4 Noble Gas microcuries/sec Iodines microcuries/sec Particulates microcuries/sec 10. Release point (is/was)': Ground Level Stack Other } 11. The quantity of radioactive material released was: I microcuries-12. Meterological Conditions: l Wind Speed: meters /second l Wind Direction From:
- (degrees) i To:
- (degrees)
Stability Class: (A, B, C, D, E, F, or G) Precipitation: (Y/N) (Amount) g \\s,l
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, u 13. Actual or Projected Dose Rates: (.s ' N1 Child Thyroid . Distance Whole Bodv (res/ hour) (ren/ hour of inhalation) Site Boundary .j J) ' 2 Miles .3 d.,A 5 Miles .~3d 10 Miles .. -yl _,Other .g. o 14. Inegrated Dose (in ress): d je Distance Whole Body (rem) Child Thyroid (ree) s - t; Site Boundary I i w 2 Miles (.... 5 Miles i s.- _J, i. l 10 Miles fj a Other I 15. Measurement of surface radioactive contamination, onsite or offsite: 4 l 16. Emergency actions at plant include: (i.e., plant evacuation) ) i 1 3 17. Onsite support (needed/ requested) from offsite organizations: j 18. Plant prognosis is: ?, (stable, deteriorating, etc.) t 19. The status of reactor core cooling / heat rer. oval capabilities is: l
- Addendum 17 2
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- Attachment 4 (Continued)
?; ',Ni] 20. . Reactor coolant system integrity is: .,,n. . :.3 - G-j , - *' t: _ ~. 74 21. Fuel integrity is: . :JJ; r .' b/ d-22. Containment radioactivity is (concentratione and inventories): -r;.m& -Q 23. Containment integrity is (primary and/or secondaryl: My + . s, ') ..f q s ,,..- r
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- Attachment 5
'ci] .. :c j ' TECHNICAL SUPPORT CENTER ,1 INFORMATION FORM 'E N j ~5) RADIOLOGICAL /0THER STATUS s
- 2.1 I. ' RET. EASE POINT:
Stack (Elevated) '- / 'j Ground Level . -a Diffuser ' 'Od Other ~,'j r;4 II. RELEASE MIX: Noble Gas Rate pCi/s '. a Iodine Rate pCi/s [f Particulates Rate pCi/s V: Gross Activity Rat _e pCi/s 2j ,4 m III. MET DATA: Wind Speed m/s m/s -j Plume Direction m/s m/s 1f Wind Direction m/s m/s ~_ Stability Class m/s m/s -} s Precipitation m/s m/s q C-- 'i IV. DOSE RATE (REM /H) TOTAL BODY THYROID SECTOR i; Site Boundary W Two Miles
- ]
Five Miles 4 Ten Miles ~:-( DOSE (REM) TOTAL BCDY THYROID SECTOR Protective Action Guide: 5 REMS 5 REMS 25 REMS i 'i Site Boundary i Two Miles Five Miles Ten Miles 1 u, V. PREDICTED DOSE RATES (REM /H) at h (DETERMINED BY IP-18) e .c n. k e
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- ATTACHMENT 5
.i . TECHNICAL SUPPORT CENTER .,3
- i INFORMATION FORM d
.~ t N DOSE RATE (REM /H) TOTAL BODY THYROID SECTOR '3 Site Boundary Two Miles [ Five Miles Ten Miles -) DOSE (REM) TOTAL BODY THYROID SECTOR Protective Action Guide: 5 REMS 5 REMS 25 REMS 3 Site Boundary '1 Two Miles Five Miles ~l . Ten Miles ',) VI. TVA-RECOMMENDED PROTECTIVE ACTIONS.-- ~, d ,l q 4 l~ 3 1 VII. STATE OFFSITE PROTECTIVE ACTIONS: 'I i m 4 f i' ~ t 1
- Addendum I
v 4 20 N _,_}}