Text

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures LZP-1200-5 Re Generating Station Emergency Procedure Guidelines for Offsite Protective Actions & LZP-1310-1 Re Notifications
	ML20086J819
Person / Time
Site:	LaSalle
Issue date:	10/17/1984
From:	; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20086J811	List: ML20086J815; ML20086J819;
References
	PROC-831017-01, NUDOCS 8401250314
	Download: ML20086J819 (74)
	v • d • e

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s. d G !LZP 51C-1 DELETED C2 10/cc Cl

.J - C2 10/8C G1 /<i LIP SZO-1 -CELETEC 2 MjLLP 520-2 DELETED Cl 1C/8C 01 '5LZP 520-3 DELETEC C1 1C/80 Cl 'LZP 53C-1 DELETED C1 10/80 Cl i 1 0 F

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. z,IP 830-1 OELETED 01 10/80 C2 A ' dL P 850-1 DELETED C1 10/6C 02 .y LIP 860-1 DELETED C1 10/80 02 .]

jZP 68C-1 DELETED C1 11/80 02 02 SIP 1110-1 STATION DIRECTOR (ACTING STATION gg fc/gy DIRECTOR) IMPLEMENTING PROCEDURE 14 9 1120-1 OPERATIONS CIRECTOR IMPLEMENTING C4 2/83 02 PROCECURE

! ZP 113C-1 TECHNICAL DIRECTOR IMPLEMENTING PROC. C3 4/dl 02 'Z P 11*C-1 . MAINTENANCE GIRECTOR IMPLEMENTING C1 11/8C 02 i PROCECURE 4 XZP 1150-1 STORES CIRECTCR IMPLEPENTIWG PRCCECURE C1 11/80 02 'l (2P L16C-C1 ADMINISTRATIVE DIRECTOR IMPLEPENTIaG C2 1/82 02 PROCEDURE illP 117C-1 SECURITY DIRECTOR IMPLEMENTING 04 7/83 02 'j PROCECURE 'l

ZP 1180-1 RAD / CHEM CIRECTOR IMPLEMENTING C3 7/81 C2 PROCECURE ZP 1180-2 RAD / CHEM CIRECTCR INITIATED C1 11/80 02

~ U TNVIRONMENTAL MONITORING ACTIVITIES ,4 iSLP 1190-1 ENVIRONS CIRECTOR INPLEMEATING CO o/83 G3 _ 1;ij PROCEDURE ZP 1200-1 CLASSIFICATIONS OF GSEP CONDITIONS C3 8/82 01 ?ZP 12C0-2 CLASSIFICATION CF A N0dLE GAS RELEASE CL 5/82 C2 i IZP 1200-3 CLASSIFICATION CF AN 10 CINE RELEASE C1 2/82 01

i-2__ ~ i 7 C8/83 LZP INDEx PAGE / " PROC. NO. TITLE RE/. REV OATE CISKETT 7 $ZP 1200-4 CLASSIFICATION CF A LIOUIC RELEASE C1 5/82 01 12 00- 6 Gs1P 6 i&* tines M reemmat 4 #4+e "LP 121C-1 HAZAR00US MATERIAL INCICENTS REPORTI'4G C2 3/63 01 a [IP 1220-1 EMERGENCY TELEPHONE NUMBER Cl 5/81 01 ZP 1220-4 DELETED Cl 7/81 01 '9 CCNTAINNENT ATMOSPHERE FOR RACICIDINES DETERMINATION } AND PARTICULATES ALTERNATE MEANS -{.Z P 131C-1 NOTIFICATIONS 45r a/g3 C2 jZP 1320-1 AUGMENTATION CF PLANT STAFFING g(, Ap{y 02 ~.. .ZP 133C-1 DELETED C2 7/82 02 !ZP 1330-2 OELETED C2 7/82 03 -i P 1330-3 OELETED C3 7/82 03

ZP 1330-4 DELETED C2 7/82 03

.Z P 1330-5 POST-ACCIDENT NO3LE GAS RELEASE RATE CO 11/SC 03 l OETERMINATION ZP 1330-6 DELETED 01 7/81 03 _ jZP 1330-7 OELETED C2 7/82-02 -J !ZP 1330-8 SAMPLING LIQUID PROCESS MONITCRS CSL 7[I3 03 CURIt.G LIQUIO MCt;ITOR HIGH RAOIATION .j ALARM CCNDITICNS J. 14 G1 1/82 03 .Z P 133C-LC OELETED DILUTION AND TRANSFER OF GAS SAMPLES CO lt/81 03 ,,; 4 P 1330-11 r 'ZP 1330-20 PCST-ACCIDENT ANALYSIS OF dARCN CO 3/81 G3 l (SACKUP PROCECURE) 'I !ZP 1330-21 POST-ACCICENT ANALYSIS OF CHLCRIDE 03 6/82 03 ,u kZP 1330-22 CALI8RATICN OF THE MODEL 10 OIONEX C2

/82 03 "j

ICN CHRCMATCGRAPH 913 1330-23 0ETERMINATICN OF REACTOR COOLANT PH, C2 $/32 G3 ,l CC40UCTIVITY AMD DISSOLVED CAYGEN CCNCENTRATICN AT THE HIGH RADIATION SAMPLE SYSTEM ZP 1330-24 DETERNINATION OF REACTJR C30LANT C3 $[g 3 33 NYJRCGEN AND CFF-GAS CJ.iCENTRATIONS AT THE HIGH RADIATION SAMoLING S Y S T E.* e-

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-l HARDWARE 4P 1330-35 ISOTOPIC ANALYSIS 100I.45 S AMPLES USING CO 6/82 C3 - AAIS SCFThARE AND PARAPS HAR0 WARE +- l "'4 P 1330-36 ISOTOPIC AhALYSIS OF PARTICULATE CO 6/82 C3 4 SAMPLES USING AAIS SOFTWARE WITH -[ PARAPS HARDWARE

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} CONDITIONS r

2P 1340-1 INPLEMENTING PRCCEDURE FOR FIRE

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4 ACCIDENT CONDITIONS

'h.)4P 137C-1 RESCUE 00 10/80 02

'Z P 1370-2 PERSONNEL INJURIES C2 11/62 02 0ZP 1370-3 FIRST AID, DECONTAMINATION AND C0 10/80 02 f)

EVACUATION OF EXPOSED AN0/OR CONTAMINATED CASUALTIES

3

4P 1380-1 CONTROL OF OIL SPILLS C1 12/82 02 LP 1420-1 ROLE ANC STAFFING OF THE OS-SITE TSC 01 11/8C 02

.-Z P 1430-1 ROLE AND STAFFING OF THE CN-SITE CSC C2 4/61 02 'L P 1440-1 ON-SITE GSEP COMMUNICATIONS SYSTEMS C3 12/82 02 .'Z P 1*s0-1 DELETED C1 7/81 02 IP 145C-2 DELETED C1 7/81 C1 !.ZP 151C-1 GSEP OPERATIONAL READINESS CO 10/SC C1 ?.!LP 1520-1 TRAINING RE'CUIREMENTS CO 10/oC C2 4 J-Z P 1530-1 EXERCISES AND ORILLS Of 2/91 02 I ZP 1550-1 FIRST AID FACILITIES MONTHLY C2 12/82 02

lt SUkVEILLANCE

.I ,' I P 155C-2 ENVIRONS SAMPLING 5UPPLIES INVENTCRY 03 12/82 01 - IP 1550-3 DECO.4TAMINATICN FACILITIES MONTHLY C1 5/81 02 SURVEILLANCE j 49 155C-4 ST. MARY'S HOSPITAL HEALTH PHYSICS C1 7/81 02 SUPPLIES LUARTERLY SURVEILLANCE ~.;t:.1 ' ';ZP 155C-5 TECHNICAL SUPPORT CENTER JUARTERLY C2 2/83 C1 SURVEILLANCE 'l 'IP 1550-6 OPERATICNAL SUPPORT CENTER QUARTERLY C2 2/33 C1 3URVEILLANCE ' [Z o 155C-7 DELETEG C3

/63 01 l

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r .i i LZP INDE( PAGE )7/Cd/83 s. JdRCC. NO. TITLE REV. dEV DATE CISAETT i )? 155C-8 DELETED 03 3/83 02 i '(NARS), MONTHLY SURVEILLANCE . ' +,

4P 155C-9 SPECIAL TLD QUARTERLY SURVEILLANCE C2 11/81 03

? \\ l 'ZP 1550-10 ENVIRCNNENTAL SURVEILLANCE STATIONS CO 7/81 02 ( , 'lZ P 1550-11 POST-ACCICENT SAMPLING EGUIPMENT 01 //g3 03 INVENTORY -ZP 161C -1 RECOVERY AND RE-ENTRY PLANS C/ /d T 01 g '.l. Z P 1700-1 GSEP STATION GRCUP DIRECTCRY C5 1/63 01 .il '14P 1700-2 STATION EMPLOYEE LIST 05 ' 7/y3 01. ..j j-2P 1700-3 STATION PHONE LIST 04 7/83 03 ? 2 ." l 3 I 1 i l 4 k I 3 t .i ^ ' s ..-s h .4

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...- :. :.. 2.:.. _ _ y. i i j L2P-1200-5 Revision O Octocer 17, 1983 '? 1 I'C GSEP GUIDELINES FOR RECOMMENDEO OFFSITE PROTECTIVE ACTIONS e

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} A. Mg The purpose of this procedure is to outline the guidelines for recommended offsite protective actions. ) 'C] B. REFERENCES 6 ..1:3 1. Generating Stations Emergency Plan (GSEP) Sect. 6 3. ' 'Jd 373/83-21 -(f 2. AIR 01-83-32106, US NRC Inspection Report 3. AIR 01-81-317, US NRC Inspection Report 50-373/81-14 and 50-374/ 81-09. C. PREREQUISITES 1. None. I O. PRECAUTIONS 1. None. E.

t. IMIT AT IONS AND __ _AQM I

1. State and Local governments have the responsibility to coordinate actions taken to protect tne puolic j during emergency situations. t {,- F. PROCE00RE l.] 1. Only the Station Director or Acting Station Director can make a determination as to what reccmcenaea ' q* ; offsite protective actions are made to offsite agencies. The transmission of the recommencea r actions to the of fsi te agencies can ne celegatea. 39 3 ^ Recommending protective actions to offsite agencies cannot be delegated to any incivioual other then '.y the Acting Station Director (Reference 3). - i; 2. " Attachment A" is to be used wnen making recommenced protective actions for Gaseous Release. -_.s. 9 ,,y

,s 4 I l 1 L4P-1200-5 i Revision 0 Octooer 17, 1983

1 2

,- ) 3. " Attachment 8" is to be used when making recommenced protective actions for protection against ingestion .j of contamination for the offsite puolic. 4. " Attachment C" is to be used as a summary of possiole offsite protective actions to oe recommenced or implemented during an emergency. 4 G. CHECKLISTS , ; e;. 1. None. [ H. T1GMSEQQQTION REFER,gCy

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,,,[. , j. 3. , _, z (,,, ,7 q.j. ,q CSFF 9tiiPFLINE4 f9E FFDTFFTipM AGAIHsy INCesTJON cr CONTANIMAJ}pH fog THE l 2, a.u.- __.._._._.s..1...2.. Ravision 0 [ jl 17,1983,l!, October s! F000 AND WATER CDNTAMINATION 4 l A. Derived Response Levels j; i Preventive Action Levele* Total Intake via A11 Feature Crees Nuclide** Critical Organ Milk / Water *** Foo'd and Water Fathways (Fresh wetaht) ll i 0.09 uCL 0.27 uC1/kg ? j i 1-131 Thyroid 0.012 uC1/1 l Co-137 Whole Body 0.34 uC1/1 7 uCi 3.5 uC1/kg i Sr-90 Bone 0.007 uC1/1 0.2 uCL 0.7 uC1/kg Sr-89 Sone 0.13 uC1/8 2.6 uCL 13 uCi/kg

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1he preventive derived response action levels relate,to a 1.5 rem projected dose commitment to the thyroid Emerneacy action or to a 0.5 rem projected dose commitment to the whold body, bone, or any other organ.

4 levels are equal to ten (10) timas the preventive levels and relate to either a 15 rem projected dose com-j l mitment to the thyroid or a 5 res projected dose commitment to the whole body, bone, or any other organ. 4

- 1f other nuclides are present, use Regulatory Guide 't.109 to calculate the dose commitment to the critical l

Inf ants are considered to be the critical segment of the population. organ (s). Recesamended Protective Actions l B. Emersency Level Exceeded t s Preventive Level Exceeded Isolate food containing radioactive contami-For pasture; remove lactating dairy cows from o nation to prevent its introduction into case-e contaminated pasturage and substitute uncon-merce and determ1pe whether condemnation or l taminated stored feed. Also, substitute a another disposition is appropriate. Before 1 source of uncontaminated water. taking this action, considert 4 p For milk; withhold milk from market to allow e radioactive decay. Consider diversion of fluid -Availsbility of other possible actions; milk for production of butter or evaporated milk. -Importance of particular foods in For fruits and vegetables; wash, brush, or scrab to remove contamination. Allow radioactive decay nutrition; and e -Time and ef fort required to take actior.. through canning, dehydration, or storage. For grains; mitt and po11eh. e

- - The preventive action levels apply to water as well as milk; the protective action for water would be f

to use a euttable source of uncontaminated water. i i .\\ i 1 ATTACHMENT 8 o 4 l 2 l

a -. 1=Nw- - Q -"&5~- S '- ' ~~ s.H h. uo-5 " ~ - y i-a --7v-~ .....u ..c. a Revision a ?- October 17, 1983 4TTACHMENT c 5 (Final) .,ll' 4 SUHHARY OF POSSIBLE OFFSITE PROTECTIVE A'YONS TO BE RECOMMENDED OR IMPLEMENTED DURING AN D.hMGENCY, tt ACCIDENT FilASE EXPOSURE PATilWAY EXAMPI.ES OF ACTION TO RE RECOMMENDED Inhalation of gases, Evacuation, nheiter, access control, respiratnry protection. I l EMERCENCY radiotodine, or particulate prophylaxis (thyroid protection) s I"IIASE (0.5 to 30 hours)

Direct whole twidy exposure Evacuation, shelter, access control Ingestion at milk Take cows off pasture, prevent cows from drinking surface water, discard contaminated milk, or divert to stored products sisch as cheese Ingestion of fruits and Wash all produce, or impound produce, delay harvest until 2 INTERMEDIATE vegetables approved, substitute uncontaminated produce i

HIASE Ingestion of water cut off contaminated supplies, substitute from other sources. filter, demineralize J (30 hours to 30 days)* Whole body exposure and Rglocation, decontamination, access control inhalation Ingestion of food and water Decontamination, condemnation, or destruction of food; deep contaminated from the soil plowing, condemnation, or alternate use of land either by resuspension or 3,0NG TERN uptake through roots ] 1 PilASE l Whole body exposure from Relocation, access control, decontamination, fixing of j' (over 30 days)* deposition material or can'tamination, deep plowing inhalation of resuspended j, j material t' 4 1 Emergency phase - Timn period of major release and subsequent plume exposure. I 2 l Intermediate phase - Time period of moderate continiscus releases with plume exposure and contamination of environment. 3.ong Term Phase - Recovery period. 1 1 f

" Typical" Post-accident time pertodo.

Reference:

USEPA " Manual of Protective Action Culdes and Protective Actions for Nuclear Incidents," 1975. s' 0

t' - s ( i } ' I, LZP-1310-1 Revision 5 7 Octooer 17, 1983 1 T. .i NOTIFICATIONS 4. P UR PO S C-j i The purpose of this procedure i s to outline the various notification requirements for GSEP response concitions. .. i B. REFERE_NCE1 1 ~ 3 1. IE Bulletin No. 79-068. .l.' 2. IE Bulletin No. 79-08. l 3. IE Bulletin No. 80-15. 1 4. IE Information Notice 80-06. i 5. Supplement to IE Inf ormation Notice 80-06, cated July 29, 1980. + 6. 10CFR Part 50 Section 50 72, Notification of Significant Events. ) 7. 10CFR Part 20 Section 20.403, Notification of Incidents. 8. Nuclear Stations Division Manager's Directive No. 21 014. t ~ ~f 9. Generating Stations Emergency Pl an, Section 6.0. l 10. Regulatory Guide 1 16. J 11. Technical Specification, Section 6.6. 12. LZP 1110-1, " Station Director Implementing Procedure." - 7 13. LZP 1210-1, " Hazardous Material Incidents Reporting." +il 14. LZP 1380-1, " Control of Oil Spills." hj 15. Environmental Emergency Plan Inplementing Procedures. 16. 10 CFR Part 70 Section 70.52. 17. 10 CFR Part 73 Section 73.71 .+ -<---g ---p-- w., - wn ny -w,~ f w. -n-- n -e-e w.

I3 1 i 1 s 1 [ LZP-1310-1 Revision 5 ,e Octooer 17, 1983 3 2 i 1 18. LXP 100, " Security Contingency Events (Generall." ,i 19. 10CFR50 Section 54, Condi tions of Licenses. 20. AIR 01-83-60006. Y C. PREREQUISITES . g\\ 1. None. s 't -j 0. PRECAUTigg} .i 1. All information given over the ENS phone will De designated as unofficial and preliminary until it ~ is reviewed and finalized oy tne Snift Engineer, the Station Director or Command Center Desk. E. LIMITATIONS AND AETIQgi

1.

Whenever the NRC phone (ENS) is used, notification of the General Of fice Nuclear Outy Of ficer ~is required. Normally, tne station will infers tne ~ Power Supply Load Dispatcher to make tnis required notification. However if shift supervisor received Instructions (via the nignt orders or direct j communication with the specific Duty Officer) to j take the responsiellity for direct notification of tne Outy Cf ficer, they must then inform the load 1 dispatcher that the station will make the required a notification. ';s 2. In accordance with parts (X) and (Y) of Reference 4 19 and part (C) of Reference 6 (See Reference 20), a license may take reasonaole action that aeparts from a license condition or a Technical Specification in an emergency when this action is immeciately 't r neecea to protect the puolic he'lth and safety ano a no action consistent witn license conditicns ana ,j Technical Specifications tnat can provice adequate 'u or equivalent protection is immealately apparent. t These actions require:

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Approval, as a mini mum, by a licensed senior -1 ooerator prior to taking the action, and b. Notification oy telephona to the NRC Operations Center of the emergency circumstances requiring the action. Wnen time permits, tne notification i m -e .-...m . =.

t l LZP-1310-1 Revision 5 l Octooer 17, 1983 '? 3 1 must ce made oefore tne protective action is -j taken; otherwise, tne notification must De maae as soon as possiole tnereafter.

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~ .} F. PROCEDURE s' i 1. When Initial notification of an ecargency is made .I to State or local authorities the State of Illinois ,1 Nuclear Accident Report Form (Attachment C) is to 1 os used to compile the information needeo for the 'k report with periodic uodates made whenever possiole - 1 if plant or atmospheric conditions change i s i gn i f icantl y. Per 10 CFR 50 App E. 0 3, State and local authorities must be notified within 15 min. i of ceclaring an emergency (initiation of GSEP). 2. A requirement to notify the NRC within cne (1) hour applies to the folluwing events which should De reported on the Control Room phone: a. In accordance with References 1 and 2, one hour noti fications shall De made when the reactor i is not in a controlled or expectec concition wnlle operating or shutdown. This conoition is interpreted to mean: 1) A LOCA or similar failure of tne reactor coolant system which resul ts in an uncontrolled increase in containment radiation levels, pressures, or temperatures or unexpected uncontrolled release of radioactivity off-site. ] 2) When the reactor coolant system pressures l and temperatures are not under control or 2.I following expected trends within a reasonaole amount of time such as 15 minutes after <j a transient. o. In accordance witn Reference 4, 5, 6, and 9. notification shall oe made as soon as possiole ~; such that activity will ne released to vented ouildings. (i.e. - start of pumps witn controlled leakage seal s ) C 5) Any fatality or serious injury occurring on the site and requiring transport to an i off-site medical facility for treatment. 1 k ---d%-- ea,--, h, e w, - - w-t- ---rri g - + - - w- -mp er---- e--+ ef t w' 9 r -+

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._ _ _ + _. _. L. i 7 I LZP-1310-1 Revision 5 I Octooer 17, 1983 'l 6 ) Serious injury i s considered to oe any 9 injury tnat i n the judgement of the licensee 1 representative will require aamission of I 1 i the injured individual to a hospital for j treatment or ooservation for an extended period of time (greater than 48 nours). s ~S Injuries that only require treatment and/or .b ; sedical observation at a hospital or off-4 c4ff site medical facility, but do not meet "i the conoitions satisfied aoove, are not . fj required to oe reported. 'I.]f a) Notification should also De made for less severe injuries i f contamination complications also exist or i f an I ambulance servico is used to transport the victim to an off-site medical facility. 4 6) Any serious personnel radioactive contamination requiring extensive on-site decontamination or outside assistance. 7) Any i ncident involving Dy-oroduct, source, or special nuclear material whicn, in accordance with 10CFR section 20 403, may have caused or threatens to cause: a) Exposure of the whole Dody of any 3 individual to 25 rems or more-of-radiation; exposure of the skin of the wnole body of any incividual of .i 150 rems or more of radiation; or exposure of the feet, ankles, hands ,, a ,2 or forearms of any individual to 375 0-rems or more of radiation; or f l c) The release of radioactive material l. .j in concentrations which, if averaged over a period of 24 hours, would .j exceed 5,000 times the limits specifica , :j for sucn material s in 10CFR 20 Appendix B. Taole II (see Attachment B); or aj i - ' c) The loss of one working ween or more of the operation of any facilities affected; or j i l-l- t t w =- -w - - - m - y 7 y yrtw:- -p+, -ew-,r yw- 'w-e e, y+ ,,-,y-w-- ,,w-- tw--9-mmyc-,ery-3-+-- - - 7- - * - w mew

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j h, ~ ] l ,LP-l';0-1 Revision 5 -N October 17, 1983 r j d) Damage to property in excess of i 9 5200,000 00. 'i i 8) Strikes of operating employees or security j guards, or honoring of picket lines oy these employees. - q .d d. In accordance with Reference 3, notification }$ shall ne made witnin one hour, by commercial telephone or relayed message, to the NRC .; g;)3 Operations Center, when one or more extensions 'J 'Q of the Emergency Notification System (ENS) is , ] found to De inoperaole for any reason. (See precaution #1) ,. j ) (( 3. Notification of reportaDie Oil or Hazardous Suostances. I a. Oil spills shall ne reported as required per Reference 14. n. Hazardous material s shall be reported in accordance with Reference 13. l ~i 4. A requirement to notify the NRC within twenty-four (24) hours applies to the following events,which should be reported on the Control Room phone. Tnese events should be confirmed by telagrapn, mailgram, or facsimile transmission oy no later than the first ~4 working day following the event, with a written followup report within two.. weeks. .j "i.j a. In accordance witn Reference 7. any incioent involving licensed material wnich may have J.; ; causes or threatens to cause: 7 1) Exposure of the wnole oody of any individual to 5 rems of more or radiation; exposure of tne skin of the =nole Docy of any individual to 30 rems or more of raciation; or exposure of the feet, ankles, hands, ] or forearms to 75 rems or more of radiation; or g , c.j - 2) The release of radioactive material in '4 concentration which, if averaged over a e period of 24 hours, would exceed 500 times the limits specified for sucn materials In 10CFR20 Appendi x 8, Table II (see Attachment B); or 4 .. - - - ~,,,. -. - -. -

^...L_..... a. ~- LZP-1310-1 h Revision 5 j Octooer 17, 1983 4' 8

k

'?! 3) A loss of one day or more of tne operation j) of any facilities affected; or .i ] 4) Damage to property in excess of 52,000.00. iif D. In accordance witn Reference 10, notification l.( shall be made as expeditiously as possiole, - ; sj but within 24 hours by telephone for the G-following events: hM f}y 1) Failure of tne reactor protection system (j or other systems subject to limiting safety-system settings to initiste tne -( required protective function by the time 1 a monitored parameter reaches the setpoint i specified as the l imiting safety-system setting in tne technical specifications or failure to complete the required protective function. ~ 2) Errors discovered in the transient or j accident analyses or in the methods used for such analyses as descriced in tne safety analyses report or in tne cases for the technical specifications tnat have or could have. permitted reactor operation in c manner less conservative than assumed I' in the analyses.

{.

3) - Performance of structures, systems,- or

.j 1 components that requires remedial action

d or corrective measures to prevent operation h!

in a manner less conservative than tnat lJ. assumed in the accident analyses in the ,.] safety analyses report or technical 'i specifications bases; or discovery curing .j plant life of conditions not specificall y considered in the safety analyses report '.t or technical specifications that require ~] remedial action or corrective measures to 1 prevent existence or oevelopment of an unsafe condition. ' [I 5. Accidental criticality requires immediate NRC Regional -} Office notification (Region III) Dy telephone and .j a followup telegram, mailgram or facsimile (Reference 17). 'k i ~

f L i LZP-1310-1 Revision 5 j October 17, 1983 9 ,i 2 6. As required in Reference 17 and 18, one nour f notification of the NRC Operations Center via the ' i, ENS line is required for: ) .. ) ~ a. Any event wnich significantly threatens or j lessens the effectiveness of a physical security system. t il O. The loss, unlawful diversion, theft, attempted ") theft or suspected attempted theft of special nuclear material. This event also requires g immediate notification of the NRC Regional ? Office ny telephone gng followup telegram, mallgram or facsimile notification. 1 c. An act of radiological sanotage against tne plant or its transportation system. [ G. $HECKLISTS 1. None. H. TECHNICAL SP_EQJE1 CATION _REEERENCES 1. Section 6.6. s t ~ i . a., 4 k -t I e

.....~.-l..~ ..-. a za.. ...., :... a;.:.2 a.....a .a.:. .-.c ..o... AliACliflENT A 4 I.ZP 1310-1 1 Revision 5 Lacs mERGENCY ACTI608 f.EVElm October 17, 19533 .l. 10 l l e Cf.JsERAI. SITR l titsUSUAl EVElfr AtEtrP ENERGENCY MERGENCY CUNDITIO.N Class Denctlption Events in progress Eyesets In progress Events in Event's in progrens. or have occurred which or have occurred which progress or have or have occurred which i Indicated a potential Involve and actual or occurred which involve actual or degradation of the potential substantial involve actual 1suminent nuhnt.ntial level of Safety of degradation of the or likely major core degraslation or the plant. level of safety of failures of melting with potential the plant. plant functions for loss of contain-1 I need for pro-ment integrity. tection of the pubtle Impacted on-site and, Impacted on-site

1) Aircraft Crash Impacted on-site or minniles from requiring unit shut-and, requiring unit down dose to the shutdown due to puntever source.

laptementation of the implementation l an ACTIcel statement of Technica! l of the Technical Specification Specifications section 3.0.3.

2) Control Room Evacuation is antict-Evacuation is Evacuation pated or required with required and 4

control estabilshed control is not f rom remotep sinstdoen entahtished panel from remote i nhutdown panet within 15 min. 1 i 4 l !!

...----__.c.:.__......_..m_.;i.,_._,,,, i 1. 1310-1 ATTACEMENT A i LSCS EMERGElM.Y ACTION LEVELS Oct e i 5B SITE GENERAL W NDITI0tt tR0 USUAL EVElry ALERT EMERGENCY EMERGENCY

3) Earthquake Equipment activated At a level greater At a level (Activation of at the artpoint level then an Operating greater than a i

i seismic monitoring (f 0.01g) Basis Earthquake Safe Shutdown alarm with level (0.1 g horizontal - Earthquake with i verification from 0.066 g veritcal), a unit not in the Aux. Electric cold shistdown or refueling Room) (9 2 g horizontal (Not' spurious or testing) O.133 g vertical) s

4) Emplosion Causing Onsite.

Requiring unit shut-Requiring unit down due to the shutdown due f Damage, '

Implementation of to the imple-ad ACTION statement mentation of of the Technical Technical Specifications

' Specifications Section 3.0.3. l i

5) Fire Requiring offsite Requiring offsite Requiring offsite (ongoing as assistance assistance and assistance and detected by requiring unit requiring unit I

observation'or shutdown due to shutdown due to alarm, and verified the implementation the implemen-4 by the Fire brigade) of an AC1l ION state-tation of Tech-ment of the Tech-nical Specifi-nical Specifications cation 3.0.3.' i ~ 6 e 9 t e I

.. L. - a. " " " ' " ~ ' ~ ~ " ~ ' "~~ Y ~ ~ ~ ~ ^ ~ ~ ' LZP 1310-1 ATJACHHENT A Revision 5 j 1 Lscs ENERGEWtf ACTION 1.EVEl.S ? October 17, 1983 -12 SITE GENERAL e CONDITION tlNUSUAL EVENT ALERT ENERGHNCY EMERGENCY j i 1 E) Flood Rupture of cooling

1) filinofs River

1) 1111sols River pond dike afrecting,

~7 610' NSL > 710' MSL (ICS offsite property (OS feet above feet ateve max mas probable flood) probable flood)- 1 i 2)~/25 inches of rain 2)> 25 inches of l in a 48 hour period rain in a 6 i + as determined from hour period. the National Weather Service e

7) FSAR Analyzed

1) Control Rod Drop

1) Pipe Breaks Inside Accidents (FSAR 15.4.9)

Primary Containment (FSAR 6.2, 6.3, 7.1, NOTE: For Fuel

2) Pipe Breaks Outside 7.3, 0,3, 15.6.5)

Handling Accident Primary Containment

2) Caseous Redwaste (FSAR 15.7.4), see (FSAR Appepdix C)

Adsother Tank 9 Rupture (FSAR 15.7.1) l condition no. 17. i l I j li ll l 1 1 .l j 8 s. 2 .

e

's

8e e

i 4

,,n, --u. ^ s w ..;a._$.._.,,.,._ i 1 i ATTAChrtENT A LZP 1310-1 E.SCS EMEAGhf(.i ACTION IAVEI.S Revision 5 October 17, 1983 13 SITE GENERAI. CONDITION UNUSUAb EVENT Al2RT ENEfCENCY EMERGENCY e

8) Security Threat The following events Security Threat t>f Inninent loss of fees of physical as described in the increasing severity physical control of control of facility.,

Security Plans that persists for

facility, more than 68 minutes.

1) Obvious attempt to sabotage.

I

2) Internal disturbance l

(disturbance which is not short lived or is not a harmless outburst involving one or more indivi-deals within the - [ protected area). l

3) Bomb device dis-ll covered.

I ' i

4) Hostage.

5) Civil disturbance (spontaneous cot-t lective group gathering which disrupts normat operations).

.i

6) Armed or forced protected area l

'a e. intrusion.

7) Armed or forced witat area intru-sion.

l !

t 0 i

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... c.. ; ; _,_, l LZP 1310-1 ATTAQtHENT A Revision 5 raCs imERcE*.y ACTaoM r.Evssa October 17, 1983 i

4 B

SITE CENERAI. .i LTNEDITION UNUSUAL EVENT ALERT EMERGENCY ENERGENCY y

9) Tornado or Severe

1) Tornado near

1) Tornado strikes Sustained winds of winds being fac!!!ty.

facility ) 90 mph (Designed experienced a) Control Room Winds) (Hind supeed as informed by

2) Sustained winds of Indicated in Imad Dispatcher

> 75 mph. Control Room) or b) Informed by Station personnel who have made f visseat sighting. I

2) Sustained winds of

> 60 mph. i I i

10) Toxic Gas Incident observed Detected by the Detected by the (Chlorine, near or onsite Chlsrine and Chlorine and Ammonia)

Ammonta Detection Ammonia Detection System with Control System without l Room and Auxillary Emergency Electric Equipment Filtration System Room Emergency operable. Flitration System operable. i Chlorine detected at 5 ppm I Ammonta detected at 50 pre l j l

11) Imse of AC Power Unit shutdown due to Unit shutdown due I.oss of all the

= j implementation of to implementation following 4160 VAC Technical Specifi-of Technical Russes for>15 minutes: cation ACTION Specification 141y (241y), 142y (242y) 4 statement 3.8.1.1. Section 3.0.3 and 143 (243) i e

'+ :

l. t.

i.1.:. a : - :,'...... 3 .f .w.... LZP 1310-1 ATfAClittENT A Revision ~ t.SCS EMERGEleff ACTION IEVEfE October 17,5 1983 ~

.,, e 18i i

81Tg cEseRRAL { CONDITION UNUSUAL EVENT AI.ERT ENFItGEISCY EMERGE 80CY r l

12) DC. Power tinit shutdown due to Urdt shutdown dise to Loss of all the Implementation of inplementation of fo11ouin 7g25 VDC Tecluitcal Specification Technical Specification Distribution i

I ACTION ntatement Section 3.0.3 Panels for> 15 3.0.2.3 minutes 111y(211y), 112y (212y),113(213) j i

13) Plant Shutdowes

1) Loss of all systems Loss of Functions capable of main-sistems capable talning cold shut-of maintaining down, or

%ot shutdown. e i ~

2) Failure of the l

l t l Reactor Protectler. l System lustrumen-tation to initiate j: i and complete a SCRAM I-which brings the reactor soberitical once a limiting Safety systei setting, as spect-j fled in Technical i a Specificettons 2 Section 2.2.1, has been exceeded. l e i

14) Other Systems -

tinit shutdown due to Unit einstdown due to required it any the laptementation of implementation of 1 i Technical ftpecif t-a Tectwelcal Specitt-Technical Speciti-cation (such as cations ACTION state-cationn Section 3.0.3 ECCS, fire pro-ment. i 'I tection systems, control tuom ven- { tilation, etc.) j' i i 4

l _ _. ._.2.;..._.. ..n_ ,,,2,_ ---...a i:........ .....o '[#"I A by.P 1310-1 r A Revision 5 IECS FJtERGEM ACTIOff 12VRI.S October 17, 1983 er i I l e 5tTR GENf:RAL CUtlplTION UDIUStfAl, EVFJef Al2RT EMERGEt0CY FJtERGENCY i 2 R/hr A.2:2ml03 R/hr 2 R/hr A.2 4x10 15), loss of Fission A.h2.10 Product Barriers Primary Contaln-Primary Contaln-Primary Contaln- + l ment Activity, or ment Activity, or ment Activity, and B. Ross of 1 of the B. loss of 2 of the

8. tens of 2 of the following 3 fisalon following 3 fission following 3 finston product barrierne product harriers product barriers, with an imminent loss of the 3rd finston product harrier:

1) Cladding:

1) Cladding

1) Cladding:

grah sample > 300 grab sample > 300 grah n==ple> 300 1 uct/cc equivalent ecl/cc equivalent ocl/cc equivalent of I-131 of I-131 of I-131

2) Reactor Coolant Sys:

2) Reactor Coolant Bys: 2) Reactor Coolant Sys:

l > 1.69 psig dry- >1.69 pelg dry-p 1.69 psig dry-well pressure and well pressure and well pressiere and 3 < -129 inches <-129 inches < -129 inches Reactor Vessel Level Reactor Vessel Level Reactor Vennel f.evel

3) Primary Containment

3) Primary Containment 3) Primary Containment a)> 45 pelg Contain-a)> 45 psig Contain-a)) 45 psig Contain-ment pressure, or ment pressure, or ment pressure, or 4

b) ? 3400r drywell b) > 3400r drywell b) > 3400F drywell ' te gerature, or temperature, or temperature, or c) 7 275 F wetwell c)7 2750F wetwell c)> 2750F wetwell 0 I i air temp., or air temp., or air temp., or d)7 2000r wetwell d)> 2000r wetwell dj7 2000F watwell water temp. water temp., or water temp., or e) toss of Primary e) tons of Primary Containment Containment Integrity when intergity when Containment container'nt Integrity is Integrity in required. reepstred. 9 e

~ . -. ~ . :...L.u. - .u. .:~. >:.;<c. ..:.-.~

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..-..c. LZP 1310-1 ATTACHIENT A Revision 5 IECS EMERGEhCT ACTION LEVELS

*8

? October 37. 1583 ll SITE

CEserRAI, f

EMERGENCY EMERGENCY e t UMepITION tpfUSUAL EVEWF ALEffr I i ): 16).. Loss Palmary

1) ECCS Initiation A>50 gym leakage

1) A> 599 gym 1suminent Core Melt Coolant luot spurious) increase in.a 4 hour leakege increase examples:

period as Indicated in a 4 hour a) fees of F.W. by monitors

ce period as b) teos of Con-totaliser.

Indicated tg monitors

densate

2) A Maln Steam Line Steak

2) Failure et a Outside Con-Primary System tainment without Safety Valee leolation IMSIV to close as Indicated tg closure) an Indicated by position in-dication.

the following alarms: MS line area temp Ris Main steam line flow high.

Monitors are Primary Containment sump flou monitorer or air coolers condensate flow rate monitors.

i I L

17) Fuel Handling Standby gas treatment Standby gas treat-Accident system operable ment system not operable IReport of damage I

to irradinted feet assenhlies and i fuett pont exhaunt thmitor? 199 mR/hr) I I i t 9 0 4e

i '.. r 2:...... :...:.......-. .'. au .. :.ai.. i......-.. ~. -.. i ATTAClinfHT A LZP 1310-1 e IECS EMERGEHf.( M IOff LEVEla Revision 3 ~ j ' October 17, 1983 SITE GENER j CONDITION' IN0tfSUAL EVEffr ALERT EMERGENCY EMERGENCY f I

10) Radiation Releases 1) Gaseous Effluents

1) Gaseous Effluents

1) Geneous Effluents

1) Gaseous Effluents Frbse the Flant 10CFR20 Instantaneous

>10 times the Effluent monitors Effluent so nltors release Ilmits 10CFR2O lastantaneou detect level cor-detect levels 110CFR20.165) are release limits respondiesg to correspoewllrig to exceeded as measured 110CFR20 105) as 750 mR/hr >1 Rem /hr whole 7 uCl/ sect body at the alte l by the went stack measured by the (1.3x19 radiation monitor vent stack radia-for 1/2 hour or bouiwlary. This l and/or counting tion monitor and/ 'y500 inR/hr condition exIatn equipment. or counting squlp. (1.3x198 uCl/sec) when: 7 ment. 3 for 2 minutes at 0/u) 4.5 x 10 the site boundary where (adverse meteor-0-release rate i ology) in ucl/sec jl ~ u=mean wlewl speed in sph or i 0 l 0/ipt=10 where t: Q= release rate in uCl/neo u-sean wind speed in meters /sec

2) Liquid Effluents

2) Liquid Ef fluents

2) Llquid Effluents

( estimated liquid >10-6 uC1/mi as Estlanted Ilquid Estimated IIquid release > 4 Cl measured by mont-release > 2000 Cl release > 2 x 104 but $ 40 Cl** tors' and/or but $ 20,000 Cl C1 I sampled and measured counting equipment counting eqisipment. or Estimated liquid release > 40 C1. but6 2000 C1

Monitors: Radioactive liquid waste effluent radiation monttors service water ef f' uent monitor 4
* >1x10-7pC1/ml but _$, 1x10-6 pCi/mi

{ j i

o - ..tc... u _....b .an,,_,,.,,, 2. ,, a..;,m2.,,.,_,,, _ _ _1._... AlIAtilittNI A LSCS EMERGElWM ACTION LEVEtI ~ October 17,1^O Gh.RAL I 't SITE mHDfTION UNUSUALLEVEIR ALERT EMERGENCY EMERGENCY j t

19) 1drsonnel Injury Transportation of 5

radioactivity con- ,^ taminated injured person to hospital

20) Hazardous As a direct result of Waterials hazardous materials a person is killed cr hospitalized or esti-mated property damage exceeds $50,000.

21) Arty other epndi-Warrants increased tions of equiva-awareness on the part lent magnitude to of the state and/or l

the criteria used local offsite ll i to define the officials accident category i. as determined by Str.tlon Director.* I

Conditions that may or may not warrant classification under GSEP include l

a. Incident reporting per 10CFR50.72 j. i b. Incident reporting per 10CFR20.403 or Illinois Rules and Regulations, Part D.403. i c. Discharges of oil or hazardous substances into waterways per 33CFR153. d. Security conti,ngency evente per the Station Security Plan. The Station Director may, at his dioctetton, categorize the above situations as,CSEP emergencies, depend!'ng upon ti seriousness of the situation. (Refer to Section 10.3 of the generic plan for additional information). e i i l ee

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3 IJ.I' Illo-I R v al'"8 5

ATTACHMENT A Oc tobe r 17, 1933 i 20 t I 1 IACS EMERGENCY ACTION t.EVEL8_ i Transportation Accident ) A. A vehicle transporting radioactive materials or non-radioactive hasardous materials from a l comanonwealth Edison generating station is involved in a situation in which 1 1. Fire, breakage, or suspected redloactive contamination occurs involving a shigunent of radioactive materlat ors a 2. As a direct result of hasardous materials, f li I (a) A person is k!!!eds or (b) A person receives injuries regelring hospitalisations or l (c) Estimated carrier or other property damage exceeds $50,000. j \\ n. Any other condition involving hazardous materlat transportation and equl-slent to the criteria in i Item A. 4 7 1 I I w f i i. i' B, t t 9*

l -~ _: +~ N m m 9 PART 20

STANDARDS FOR PROTECTION AGAINST RADIATION I

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c. .a....... e 1 - - - - ~ ~ ~ - - - - ~ ~ ~.... ~ 4 1 a) - m PART 20

STANDARDS FOR PROTECTION AGAINST RADIATION

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?

a 7 1 S X rrr??*F???????r?????*?rr??rr??r?rar????rteft?=?.?? J1 4.k titttttttttttttttttttttttttttttttE2222222222222222 .x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x x.x.x.x.x.x,.x.x. g g ~s A d 4..................... j 1,g ---S I 444 2 8, gE3 = t

==

S S S S = x 2 12a aaasa22E an aaaa 3.- l i

i 1: . *I I a :

1 { i E'E i m-{d i I

3 8

a E a E wx . w E i,: v . C Md== r 9 7 r ? ? ? ? r**

r ? ? ? r * ? * ? ? ? r * * *
r ? ?
f *
r ? " * * *
r * * * * * *2 2 r

.Y 2E2E2222222t2222222222212t212tt22t222222222222E W< .x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x

g

~ h.. tr??vsv*rv**?**.9?ff*f??f??? vv*f*?9*?*Tr?*?******* 2? S 22222222 22 2 2 t 282 22 2222222 2 2 22 2 E S it t ti' t t t t t t t t t t ti $w .x.x.x.x.x.x.x.x.x x x.x.x.x.x.x.x.x.x,x.x.x.x,x.x.x.x x.x x.x.x.x.x.x.x.x x = x x.x

1 m m

-a-q q X 7,1 ,r---?.vrerrrr5'.rrrrrr-ver*rr-rrrrrrrr=v-rs==-rr**t2222222t2t2t8222222E2222222222222S e ~ I 22222222222222 .x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x ,d a 1 y, g ??'*****99??????ns,,yses??????,ee,.y J ak ???r???*?,8***ttttttttttttttttttttttttttttttttttsstktstittttttts 2 l 4 .x.x.x.x.x.x x x.x x.x.x.x.x.x.x x x.x.x.x.x.x.x.x I i i, ~ ~. ~ i 4. 3g g ~ n 4 j 4 I I T.,

1. "L

=

ii i III2II=a 4s=s;!!!355

~ m'd S 4444.a3JJ33J33e i aaa4 a a aRata a

o

..l e 4 .l g i e P = h ] a c. i ; 1 4 I I ?

- W9h.a.m m e e 9

--g ,,,4--- .,,c,r, ,..m-.,.,,,-- i.--w.- ,-,-m, - - -., ,.---we-rw ...--e------,.,----=-,- -~----a

a _. .., u u,__ __a_., n -w l I.ZP 1310-l'. I 4 f 1:. ATTACittEllT S . Revision 5 p.' 3 ' October 17, 1983 i -23. l amn=s /[ i ammma. c e e.A6 eup A6 0 =.s" t-

Ctd g

i. 46 d 45 A6 is e 6y nd e-.a.-.a

?.L e

m. = <n

. n e ~ m.=<n l 5 s.u.a i.u.i i l i.u. i - i.u.s 4 s n ;.. ce c. ci c.u s si c.6 e cou s con e c.u l, H .k h m. = a t (pct /st) [ pct /et) (,c a/ t] (,cs/.1)

t (pcs/stMyct/=tXpct/at) (,ct/mt) 0 i

.e e x== s==4 inwe ..xw* m - as...... ev su .e o r.= nx= 4 e xw. s xw'. exw w. exwa nw e. un............. em - e owe =w. i nn. an=4 an. m a s = we o w. sxw.

inn, z

i xwe r==- i==. exw4 em s e xwe ow4 e xw. i xw. o a n we, s=== inn s xw. w e rse..........== s exwe . = w* s xw. s xw. I-us an............ = =. e exw*

= w.

n ='. n=== e s ure . x w. e xw. e x e.1 m e xw e xw. e x w '. e. xw. nw wwe

== s ow exw. s xi.. ni.. o a ns e i; i ex=4 u w. e s,we e xw. ix.. r xw. m [ .m e exwe e xw. s=w4 e xwe. wu e exwe us.4 e xw. um.

l s wi. ' e xw'.

exi s =w 3-s owe s==* sxw. i nw. e a nwe s,w. exwe exw. exw m.u n. e e xwe o w. ww. ow. ,e e xw. exw. nw. . p e...

e. w e

owe r-

pes.

i e x w' i x w. exw4 u w. m e xw exw4

=w e

e xw. w e uwe sxw4 s x w. e xw., 8 e xw.e

e. n n

nw. nx w.. e xwe xw s==4 i xw. m a / O l e ww e=w* n=4

xwe s x w.
I-s pg.........: m. w.

s.6 .xw4 l s==4 e sxwe s =4

xm.e nw.

i x -.

s. n s

x .... 4 wee....... g -l =* =w.

xi r m e. *

= ses e sxwe s mi. 4 i

s. w s

aw. xw. s s u e.* s xw. s xie

r xw.

b

s. s.

i. exw s =we e xw. s xw'. s,w m. e e x w. r x w. .we e xw. I fi n an......... so m .s - % 4 *=........... rosa e e xw. i xw. sxw. exw* 8l ww4 r u w. sxwe e xw. ixwe .r=w, aw e xi.4

a. m o

e xi.4 e xo.4 4 x o.

s x e.4 o

j . x.w.*e i e xs.. i n s.4 i nwe e 4 xwe s wi.. i x e.

e x '. 2 e xwa e xw.

e u.* s, w.

o. m e

exwe e xw. ixw4 exw .s .e xw. .e xw..u s. es se. nw. xw x=. e s xwe e x w. nwy e x w. rxwe { i xwa e xt

s mi.1 a xw.

o n ew e exw. s s = w. e xw. r xw. s ww. ,.s.m pse.......... pa i.s s-exw. sxw4 sxw* > i s i e a n..........

i. m e

e xwe = = w. s xw. ixw* i exwe e xw. sxw e e xw. um e owe e xw. sxw4 n w. s exwe e x w. e xw. r = = *ez = ne......

m. n e xwe e xi..

r=we s,w. Q u w-, uw, exw4 suw e 6 n e...... en s e xw. e x w. n = es, suw e s=w4 e xw. ex

se u w, e xw.

i,io i nw. ow. enw. ix=4 u w. ens wse.......... nm e e xwe ow4 e xw. u w.

n. n 3

inw. n m.. s exwe e xwe e xwe uw. s exw. e xw. sxwe e x w. w. e xw. .ex 4 < s e xwe ann

m. =

e sxw. s xw. s xw. exw4 o e exwe exw n m. s r =we nw. sxw. s,w. s,. w.. u s.. l 4,, . g e exwe une sx=4 e xw. a nm e. m, p.e.......... o

m. =

a =w4 n w. . w w. e xw. i e xw. w. e x,.. .w.

t w w.

s

=w.

i n w. ww. u w.

p. m.

. x w. uw. s xw., exw ,.i... o

n. =

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m. w r =w e s xw.

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e...

.s. n o. s =w. u m.e s s xw. e xw e .u. e,. s==> uw-e xw. mm e 4 e xw. e x w. u s.. na.. .i e e xw= e x= > um s.is e

e. m n w.

.um .,w. e xw. us e xw. .s x w 4

== s u s. - .w. s.we. .. a,. .a

s.....

s. xw ,. m u w. e xw. i. e s mie e ,s ixw .w. e,s. ,s =.. exw. l ..w4, uw

== a n=4 x. sxwa ex. s,w. owe

e. u.

s e ow4 um. um. ex. i

~. _ _ _ - NL..o,..........c e:... c _ .._m n i i I m s. m. . PART 20

STANDARD'S FOR PROTECTION AGAINST RADIATION a

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O 3

% >w 1

v**r=v er,rrrev a??vrev?vsts*vv**rrreer e r s?orrvvvr, l

U&y G s' 2222222t222222222222222222222828222222222222323222 W , 4, g .x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x..x.x.x.x.x.x.x.x.x.x i 1 fr?9r=???r???vr???rr???rt?r??trr=vverryrvre???v??r Lt titttttttttttttttttttiskieszzsttE2222222222222222t g .x.x.x.x.x.x.x.x.x.x.x.x.M.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x x.x.x.x.x.x.x.x W 1 i t ( ?r?????teertttte????rtr???tt???*r????tretr??????re $s2222222222t2222222222222222222222222t222222t5222 .x.x.x.x x.x.x.x x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x,x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x W 9 s g ~ 3; 1g IEESSi A tIII!!I ES S = 2 S. S,, tE I i. 2222222aaaaa #22iiaa aaa a.4 i-I .i

: i.

i. C E I I Iji E. I I. E s 8 5 t i t 2 E, .: ud u. s. 1 v?rr=r??r?????r???r??????v?rs?r? :irT?v?T?T?Tv'*?'r EE2222222222222222222222222222E2 i :2222222222222222. C" %W-H' g .x.x.x.x.x.x.x.x.x.x.x.x.x.r.x.x.x.x.x.x.x.x x.x.x.x.x.x.x.x.x.x :g i..x.x.x.x.x.x a..x x l titttttttttttttttt%yys,,yp9yyyyy.,,4,,...e,...,... R 88 9,,ayy,,,,,,,,,,s g& ttttttttttttttttttttttttttttttt .x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x S l i w w b'r*?????'*T9tT? 'A 2 gr==r?rrrrrr=?rr?vervr??rt?rtt?'*i,2S22222222222222 2 2 2 2 2 E22222 E E 222 22222 222 2222 S 232. =;j.x.x.x.xx.x.x.xx.x.x.x.xx.x.x .x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x x.x.x.x.x x : m = 3 g ;- o 1 ,,,,,, r, e v e r, ?, ?,,,, ? e e v e r t r e, t '.s e e e e e t e ? ? ? ? ?

e,

c =k,tsstESEtttttttttttttttttttttstst ~ttttttttttttttts $'l7;.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x.x x x x.x.x.x.x.x.x..x.x.x.x.x ~ - i g g o 3 I. } s } 'I t 8 a' I I I I g 't ! II I i I I I 'Is ! III I I I's I E E .a. 2 2 2 2 = E a 2 2 2 2 2 2 2 2 2 222 2 2 2 8 8 8 8 { i i g d 3 i : d* g i f z. a. I = a z a ] { 1 . __ ud a 3. I q see--.-s-+ w-, -.--ew --,.-,,,wge.,,-- .,ny., g,.,"--og-w-+av-u-y v -w-9-"'-'--e.' -w--- -m-w----www-=---,--um=me-w

9 aA. ma ... u.. w.. 4. n :c i,.... a.w..;.. . :..r.. .q. a .,, 3 v. ~ a m eo m. PART 20

STANDARDS FOR PROTECTION AGAINST RADIATION i

A O ii ------,--,- tr.-erveter--et--.e-, revererreterre52222222222S22222,22222

i t. t. t. t S. t, t, t, t. t. t i, r

a

k,

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=

s m. _a w

n. :~

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j 4W 1

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e ? - - * *
8 ? " " ? ' " * *
M EtttttttttttttttttistSttSSttttttt as
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= (W ..mx. x. x x, w...,.,.x.,. g a

?

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k t i t t t t t t i s t.tt t tt t tt tt t t t t t t t t t t t t 222222 22222 S 22

.x.x.x.X.X.x.x.x.x.X.=.=.X.x.X.x.x.X.X.X.x.x.x.x.x.X.x.x.X x.x.x.x.=.=.= =. =. =..= -g. i g ....................~.......... 3 I ~ I

E I

1 : 1 2 1 3. g 2.3. s.'s t.I I1.t.t-. S. 1 l.. t S E 1 a a s's a a a's a.4 aaes asa 2.* A i i i ~~ "? 8 e7 I } r [ i : [ 1

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A , J. qs..,. s L.M,s...- r 3.__ s ~ r-G 9 PART 20 e STANDARDS FOR PROTECTION AGAINST RADIATION l 7'^D ~ o .;\\ 5%e b Bbb% i. 1 hjf 1 g i 1 2.a u 1 ui-ny9, :, {g l s s stive 8 1 Ese:Ei 4 .(Ijg1;gg ) bg a i ::::: ; - i _ q g!$ jezat L =2 4 [ ell { a 'Il'lil[llilll' 8 'E ID[I lel M l If** i !I 3 nanunni i ig }I3 ::::::::::::j I y l 1 j j c..!!.!.!.!.!.!.!!.!.!.!.! 3 1i:ininniii! i i .,i j j Iq

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i!, n us - A. .,,y,

. _.._.. _... _. __i_._....._.. _f..m n2 ,,, 3 u, , yg _,, LZP-1310-1 ~ Reelsion 5 october 17, 1983 ATTACHMENT C D (Final) i MassAos susCsevs0 STATE OF ILLINOIS NUCLEAR ACCIDENT REPORTING SYSTEM FORM y,ess oAvs T.STATUI

2. SITE IPRA VOL, e

3. ACCIDENT CL ASSIFICAflem EAlg 4, NT(E ASE STATUS S. TVPE OF NELEASE lAl ACTUAL lAl DRESDENil IEl BYR0llVI lAl TRAalSPORTAT104 ACC10ENT lAl NONE (Al RADIDACTIVE SAS 181 EXERCISE /

lel LASALLE411 IF) CLINTONVII 18] UNUSUALEVElli

18) POTENTIAL 181 RA010 ACTIVE LIQUIO ORILL/

ICI OUADCITIEErIV 10l DRAIDWOOOVIH ICI ALERT ICI OCCURRING ICI NO RELEASE TEST 101 210N v 101 SITE AREA EMERGENCY 10] TERMill4TED 10] UNKNOWN lEl GENERAL EMERGENCY e.INCleENT eCCuRREe

2. ACCIDENT CtAss FIED IFl RECOVERY lGI TERMINATE CONDITION jHI OTHER TIME DATE T6ME DATE S. WINO DINECTION DAT A (Chest est Need eereal

9. MConse0ENSED PROTECTIVE ACTIONS:

WINO FR05 DEGilEES Will0 TOWARD A lAl NOT APPLICABLE llNITIAL NOTIFICATION FOR INFOResAT10110NLY) lAl N 349 Il 8 H J K 101 PREPARE FOR POSSiOLE ACTION INVOLVING THE PUBLIC.TO INCLUDE NOTIFICATION lt! NNE 12 33 SSW J K L ICI NOTIFY PUBLIC TO TAKE Ta'E FOLLOWING PROTECTIVE ACT101st-ICI NE 34 68 SW K L te IN it tlNOIS SHELTER EVACUATE IN WISC0ess II/10WA 101 ENE 57 75 WSW LMN 82 MILE RA0lus 101 lHI S2 MILE RA01US lEl E TSlet W si N P lFI E8E 102-123 WilW N PQ 85 helle RADIUS lEl 111 94 letLE RADIUS 1G1 SE 124 144 Ilw P QR iHI SSE 147-lN N4W G R A 2 5 bilLES FOR THREE 13) [Fl lJ1 2 -(R) MILES 18I S ISO 191 N R A B 00WWWIND SECTORS lJI SSW 192 213 NNE A BC IKI SW 214 235 NE 8 C D 5-10 leILES FOR THREtt31 (G) lKl (NIT 010181LES (Ll WSW 237 250 ENE C D E NWINO HCTORE I Ital W 259 201 E O E F TO THE F 0 J INI WNW 202 303 ESE E F G 101 NW 304 326 SE F G H IPl NNW 327 348 $$E S H J [LI OISCONTINUE USE OF POTENTIALLY AFFECTEDWATERIN LOCATIOpetsi lasl PUT IllLK PROO'UCING ANIstALS ON STORE 0 FEED IN DOWNWINO SECTORS OUT TO eslLES.

10. IAESSAGE REPORTED SY:

12 IIESSAGE RECElVED BY: NAME OF CALLER YOUR NAteE i ORGANIZATeON TELEPHONE 800.

13. IIESSAGE VERIFIED IV:

11. NAR$ 01AL C00E usED EV SENDER

14. UTILITY OUTV 0FFICER i

t 4 4*

i i y ( LZP-1320-1 Revision a Jl OctoDer 17, 1983 1 y AUGMENTATION OF PLANT STAFFING I j A. _ PURPOSE 1 The purpose of this procedure i s to outl ine the steps j necessary to meet personnel needs for various GSEP conditions. -1 ..;)j 8. REFER 6NCES .y 1 1. Generating Stations Emergency Plan. 2. LZP 1110-1, " Station Director, Implementing Procedure." f 3. LZP 1700-1, "GSEP Station Group Directory." 4. LZP 1700-2, "GSEP Station Employee List." 5. LZP 1170-1 " Security,0irector." C. PREREQUI_ SITES 1. None. D. PRECAUTIONS 1. None. E. LIMITATION _S.A30, ALT 1Q3S ~~ 4] 1. None. O, F. PROCEQUR{ t. l i 1, As outlined in Attachment B, the acting Station Oirector will activate the GSEP Station Group Directors as follows: a. Transportation acci dent - as deemed appropriate. 7.l ~ l 0. Unusual Event - notification of i nd i vi dual s inaicated in Attachments A and B and others as deemed appropriate. c. Alert - activation of individuals i ndicated in Attachments A ano B and others as deemed i appropriate. t 5 ---e + +, - .-,,v v --w.

J 9 .i i f LZP-1320-1 1 Revision 6 OctoDer 17, 1983 , ;1 2 i'l fj) d. Site emergency - GSEP Station Group within 60 minutes (See Attachments A and B). y) e. General emergency - GSEP Station Group within a 60 minutes (See Attacnments A and B). An .)

{

The GSEP Operations Director is always notified. 3 ".",7{ 2. Use Attachment B for tne purpose of Station Group { Director notifications. i 3. Station ~ Group Directors shall perform duties as i deemed necessary and fill the manpower requirements needed by the use of the Station Employee List (Reference 4). ) 4 If additional personnel are required beyond those available from the station employee list, the Station Dir'ector may request personnel f rom other C.E.Co. l nuclear stations, divisions, general office, or contractors through the Command Center Director. G. CHECKLISTS t 1. ,None. H. TECHNICAL S P EC _I FI(AT ION REFER {NCgi l. None. ? b e I - I l 1 -w + se w. e.- r c -g se l- ,-,y.m ,,n,_ 9__.. _y

9___,

i LZP 1320-1 ^ Revision 6 l i October 17, 1083 l 3 ATTACHMENT A 'l ' ' GUIDANCE FOR AUGMENTATION OF THE ONSITE .i EMERGENCY ORGANIZATION MlTHIN 60 MINUTES Augmentation Within 60 Minutes "i Functional Area Usual Event Alert S! te & General Emergency ( 1 Command & Control Noti fication Only i 1 Station Director 1 1 1 I, Oper. Director 1 1 1

}

Maint. Director

1 1

1

A Tech Director

1 1

1 ~j Admin. Director

1
1 1

/, Stores Director

1
1 1

. _] Rad-Chem Director

't 1

1 ~ Securi ty Director

1
1 1

r 0 Environs Director

1 1

1 .i 2. Notifications & Communi ca tions i 1 3. Accident Assessment Of fsi te

2 4
1 1

Onsite in-Plant

1 1

Rad / Chem (Lab)

1 1

.4 Technical Support Nuclear (Core)

1 1

Electrical

l 1
1 1

Mechanical i 5. Repair & Correction ~ ~ ~ ~ Mechanical

1 1

Electrical

1 1
1 1

,j Radwaste Inst, & Control

1 I

s 6 Protective Actions Radiation Protection

2 4

i aZ-9

/-24 2d 5

3

As needed depending upon the nature of the emergency

'1 M NOTE: Additional support in the areas of Command & Control; Communications; and Accident Assessment will be available from the Corporate Command Center Staff. It is reasonable to expect partial manning of the CCC within 60 minutes for the Site & General Emergencies.

5 l LZP-1320-1 Revision 6 .1 i Octooer 17, Iv83 ) } 4 I ATTACHMENT B '[ INITIAL NOTIFICATIONS AND GESP ACTIVATION PHONE LIST ] (Shift Engineer / Station Director)

Reviewed every calandar quarter.

4 Initial Notifications and GSEP Activation , ij Phone List (Shift Engineer / Station Director) c -? '.j Call List A (Operations Duty Caller) Call List B (Faintenance GSEP Caller) Call List C (Technical Staff GSEP Caller) a Call List 0 (Rad / Chem GSEP Caller) 1. Unusual Event or Tr,ansportation Accident. A. Notify System Power Dispatcher - Dedicateo pnone or radio. ) B. Notify NRC Operations Center by way of the Emergency .j Notification System (ENS) (See PRECUATION 0.1.). If the ENS network is disaoled the alternative methods of notification listed below should oe V attemtped in tne order given.

1

, ~j IELEP!jgg,JYSTEM I E g $ g tg!d g & 'I 1. Commercial Telephone System 202/951-0550 to NRC Operations Center ^i (via Bethesda Central Office) q il 2. Commercial Telephone System 301/427-4056 l to NRC Operations Center (via Silver Spring Central Office) l 3. Health Physics Network to

22 (Toucn-Tone) 4 NRC Operations Center 22 (Rotary Dial) f

\\ l LZP-1320-1 1 Revision 6 October 17, 1983 5 M. ,3 4. Commerical Telephone System 301/492-7000 c' to NRC Operator ~ (via Bethesda Central Office) Y 293,E d NRC Region III may be contacted as necessary on Red I; Phone or by calling 312-790-5500. t,. ij C. Notify Operations Director, Station Director, and a,] Maintenance Director. 02".2 Offigg_,g & H_gg3n_2 .ij Operations Director (1) g R. H. Raguse 215 815-942-3111 J. G. Marshall 216 312-985-3259

0. S. Berkman 217 815-433-2518 Off-Site Pager 815-942-8820 l

e Station Director (1) G. J. Olederich 212 815-942-5427 C. E. Sargent 213 815-942-5608 R. D. Bishop 214 815-467-6545 Mainteg,gn,ge O_i rector 11) J. J. Coonan 221 815-586-4865 j E. E. Soyd 222 815-672-8344 H. L. Mulderink 223 815-942-3067 -3M

-d O.

Notify local agencies (i.e., fire department. .ggf hospitals, etc.) as appropriate. II. Al'ert or Site Emergency. 'j A. Notify System Power Dispatcher (if Corporate Command Center not manned) - Dedicated phone or radio. q ,j B. Notify NRC Operations Center by way of the Emergency .4 Notification System (ENS). If the ENS network is li disabled the alternative methods of notification listed below shoulo De attempted in the order given. ,- -+-, ---i,m

~ i l i I J i-LZP-1320-1 Revision 6 ]- Octooer 17, 1983 / 6 1EkEfHQNE SYSTEM T{LgPHONE NUM8ER 1. Commercial Tel ephone System 202/951-0550 to NRC Operations Center ' i j (via Bethesda Central Office) k 2. Commercial Telephone System 301/427-4056 to NRC Operations Center (via Silver Spring Central Office) y 3 s.7i 3. Health Physics Network to

22 (Touch-Tone) f NRC Operations Center 22 (Rotary Dial) 3 4.

Commerical Tel ephone System 301/492-7000 to NRC Operator j (via 8ethesda Central Office) NM NRC Region III may be contacted as necessary on Red phone or by calling 312-790-5500. C. Activate Station GSEP'Oirectors'Oy use of the pud 1ic address system and the intraplant radio system. During other than normal working hours notify the Operations Duty Supervisor to activate Station Group and requireo augmentation. NQTJ '/j If a SITE EMERGENCY i s declareo prior to TSC Staffing, then the Acting Station Director is responsiole for sounding the assemoly siren ano accounting for site J I.. personnel (LZP 1170-1 Security Director). .e Nm HJ me _Ph_one Operationg_puty Suggevis2I - Calls List A t'i C. E. Sargent 815-942-5608 j R. H. Raguse 815-942-3111 J. G. Marshall 312-985-3259 C';j

0. S. Berkman 815-433-2518

'/ ; R.

8. Bishop 815-467-6545 i

J. C. Renwick 815-744-374o

w. R. Huntington 815-433-5541 y-M

-,y v e v-y -7 --,,op.i.,--,,ww--am-,w.--,vwg 4.m-,-wr-ag---%.*- w y g-e-,9e-a---- ..m --e.

- =.. - i i

i 1

1 LZP-1320-1 Revision 6 -i Octooer 17, 1983 ) 1 7 }'3 Off-Site Pager 815-942-8821 D. Notify local agencies as appropriate. J III. General Emergency. 74 i, A. Notify System' Power Dispatcher (If Corporate Commano Oedicated pnone or radio. Center is not manned) b B. Notify NRC Operations Center by way of the Emergency ()} ^ Notification System (ENS). If the ENS network is 'j disabled the alternative methods of notification d listed below should oe attempted in the orcer given. I j TELEPH0!!g SYSTEM Tg,l,gf!!CNJ NUMBER u 1. Commercial Telephone System 202/951-0550 to NRC Operations Center (via Bethesda Central Office) 2. Commercial Telephone System 301/427-4056 .{ to NRC Operations Center (via Silver Spring Central Office) 3. Health Physics Network to

22 (Touch-Tone)

NRC Operations Center 22 (Rotary Dial) t i ~ 4. Commerical Tel ephone System 301/492-7000 .ij to f4RC Operator .I (via Bethesda Central Office) J E ...] . J. NRC Region III may De contacted as necessary on Red '] Phone or by calling 312-790-5500. R } C4 Notify Emergency Services and Disaster Agency (if Corporate Command Center is not manned) - Green l Phone (Code 25) or call 217-782-7860. s D. Activate Station GSEP Directors oy use cf the puolic address system and tne intrapiant racio system. Ouring other than normal working hours notify the Operations Outy Supervisor to activate Station Group -i and required augmentation. i t l + e m -mw,

,w-

f.* i I LZP-1320-1 j Revision 6 OctoDer 17, 1983 8 ] ILE!S tis *2 Ph002

j go_erations Quig_Sugervisor - Calls List A l

C. E. Sargent 815-942-5608 'j R. H. Raguse 815-942-3111 8 J. G. Marshall 312-985-3259 j D. S. Berkman 815-433-2518 i R. D. Bishop 815-467-6545 cj{ J. C. Renwick 815-744-3746 W. R. Huntington 815-433-5541 '.2.i Off-Site Pager 815-942-8821 .j E. Noti fy local ' agencies as appropriate. 1 0 i 1

i

.I r7 4! - '4 <1 e i 1 1 1 1 'l e m -m.v 3 y w 5 w gy vy. g - + -w

LZP-1320-1 'I Revisicn F October 17, 1983 l 3 ATTACHMENT B CALL LIST A 1 (Operations Duty Supervisor) Reviewed every calendar quarter. i Home Phone Name ) Maintenance'GSEP Caller (1) INITI ATE CALL LIST S FOR A(N) d (ALERT, SITE EMERGENCY OR GENERAL ~ 'I ENERGENCY). n [ G. Cheney 815-476-2415 D. Schafer 815-672-1163 815-942-9681 J. Kain

l W. Halcott 815-672-6244 LASALLE STATION HAD DECLARED A(N)

'} Ger.cral Message: J. (ALERT, SITE ENERGENCY OR GENERAL EMERGENGY). PLEASE REPORT TO THE TECHNICAL SUPPORT CENTER. + NOTE J The following personnel shall be called in the approximate order of distance from the site as they appear below. (Alert, Site Energency or General Emergency) Operations Director (1) 815-942-3111 R. H. Raguse 815-433-2518

0. S. Berkman J. G. Marshall 312-985-3259 815-942-8820 Off-Si te Pager

~ (Alert, Site Emergency or General Emergency) Station Director (1) 815-942-5427 G. J. Diederich 815-942-5608 C. E. Sargent 815 467-6545 i R. D. Bishop li Call Control, Room (X208) or Technical Support Center (X712) and report status of Augmentation from call list A. '? ~~, e e -wyw a, -my-r- y . m -.

?, LZP-3320-1 R2 vision 6 i October 17, 1983 19 i ATTACHMENT S (Cont.) i CALL LIST 8 -l (Meintenance GSEP Caller)

Reviewed every calendar quarter.
Home Phone Name 4

Technical Staff INITIATE CALL LIST C FOR A(N) ~ I GSEP Caller (1) (ALERT, SITE EMERGENCY OR GENERAL LMERGENGY). s 815-434-1873 '1 M. H. Rienter 312-871-3479 J. W..Gieseker 815-434-3606 ] J. M. Damron 815-433-3074 l J. R. Ullrich 815-942-9289 'j M. A. Santic General Message: LASALLE HAS DECLARED A(N) ~i (ALERT, SITE EMERGENCY OR GENERAL EMERGENCY). } ~.j PLEASE REPGRT TO THE TECHNI{AL SUPPORT CENTER. NorE The following personnel shall be called in the approximate order of distance from the site as they appear below. Technical Director - (Alert, Site Emergency or General Emergency) 815-433-5541 (offsite pager 815-942-882 W.

a. rtuntington 815-434-5546

8. S. Westpha!

815-883-9103 T. A. Hammerich 815-774-3746(offsite pasar 815-942-882: J. C. Renwick 1 Maintenance Di rector (1)_ , (Alert, Site Emerge,ncy or General Emergency) 815-486-4865(offsite pagar 815-942-883-i J. J. Coonan 815-672-8344(offsite pager 815-673-345: E. E. Soyd 815-942-3067(offslte pager 815-942-883-H. L. MulderInk Rad / Chem Ot ractor (1) - (Alert, Site Emergency or General Emergency) 815-795-5881(Offsite Pager 815-942-883. "I J ca. Lewis 815-673-2025(Offsi te Pager 815-673-345: F. R. Lawless 309-432-3536 L. N. Shearer l 4 _ Environs Director (1) - (Alert, Site Emergency or General Emergency) 815-433-3566 L. c. aryanc 815-942 281g_ 1 W. F. Eisele 815-741-1015 si D. W. Hieggelke -4 i

f. LIP-1320-1 1' Revis ion 6 I' October 17, 1983 l ATTACHMENT B (Cont.) 11 - i Home Phone Name i J Repair and Correction 4 Mechanical (1) - (Site Emergency or General Emergency) I 815-434-5795 R. Burke 815-634-8554 M. young 815-458-3167 7 J. Ganz 815-237-8184 W. Kirkland 815-942-8828/673-3453 Off-Site Pager j Electrical (1) - (SI to Emergency or General Emergency) .j. 815-795-5876 '. s. s T. Scott !] J. O'Kraski 815-673-1322 815-673-2869 'I W. Petrick 815-584-1325 1 D. Petersen 815-942-8829/673-3454 '91 Off-Site Pager e, jL Radwaste (1) - (St to Emergency or General Emergency) f 815-357-6569 i W. Pulak 815-795-6211 W. McGinty 815-434-4591 S. Davis 815-433-3732 C. Maney 815-673-1432 r K. Francis 815-436-2966 K. Sowker I instrument and Control (1) - (Site Emergency or General Emergency) 815-586-4553 M. Cray 815-448-2260 ~j' O. Welsh 815-448-2347 .i A. Trainor 815-634-8390(Offsite Pager 815-942-8834: l G. Cooper 815-942-8830 l.j Off-ShteiPager 'i (') CALL CONTROL ROOM (X208) OR TECHNICAL SUPPORT CENTER (X712) AND REPORT j STATUS OF AUGMENTATION FROM CALL LIST S. l j

i l

t l l 4 l

t l

t t 4 h

^- ' ^ ~_ 2~- L2P-1320-1 ? Revisten 6 October 17, 1983 f J2 5 ATTACHNENT S (Conc.) I J CALL LIST C (Technical Staff GSEP Caller) l'

Reviewed every calendar quarter

'.4 Home Phone i Name Rad / Chem GSEP Caller - INITIATE CALL LIST 0 FOR A(N) 'l (SITE EMERGENCY OR GENERAL EMERGtNGY) .i 815-795-5881 .) J. G. towis 815-357-8814 l C. E. Magistro 815-434-1142 L. R. Aldrich 815-434-1906 T. D. Hodges 1 815-433-3566 L. C. Bryant 309-432-3536 4_ L. N. Shearer 815-942-8E31/8832/8833

- j Off-Site Pager General Message: LASALLE STATION HAS DECLARED A(N)

(ALERT, $1TE EMERGENCY OR GENERAL EMERGENCY). Pt,EAss REPoar To THE TECHNICAL SUPPORT CENTER. NOTE t The following personnel shall be called in the approximate !'i order of distance from the site as they appear below. ? Security Director (1) - (Site Emergency or General Emergency) 815-942-4432 G. R. Hacke 815-467-6773 ] T. sorzyra 815-942-8825 Off-Site Pager Administrative Olrector (1) - (Site Emergency or General Emergency) y l R. A. klemp 815-357-6403 815-448-2260 i P. A. Welsh 815-672-3851 'i S. Majerchtn 815-727-7737 .] A. Norris Stores Director (1) - (Site Emergency or General Emergency) 815-672-1893 (Off-si te pager 815-673 d

c. sanfora 815-485-3650 R. Frederickt

] Communicators (5) - (Alert, Site Emergency or General Emergency) 815-795-4730

3

a. simers 815-795-5896 I

H. Sarch Jr. 815-433-3732 C. Maney /. i 815-433-1201

5. Seaborn 815-433-3642 l

R. gay 815-672-0213 i T. Novotney 815-672-6765 J. Fulton I l ___2,... ,__1

LZP-1320-1 j Ravi sien 6 October 17, 1983 13 ) ATTACHMENT S (Cont.) CALL 1.15T C (Cont.) .,I 1 Home Phone Name 1 1 Communicators (Cont) 815-673-3571 M L. Melander 815-434 -2179 I J. Houston 815-842-2703 J' W..Lueet 815-476-6778 i C. Kelly 815-741-2319 J. Harrington c.; fj Technical Succort Nuclear (1) - (Site Emergnecy or General Emergency) y 815-434-1873 M. H. Richter 815-942-2025 S. A. Wimmer 815-942-9289 4 M. G. Santic 815-942-6691 L. 8. Wilson 815-942-1936 O. G. Jefferies 815-942-1066 E. R. Pfister Electrical (1) - (Site Emergency or General Emergency) 815-942-5754 t J. J. Hietala 815-433-3074 J. R. Ullrich 815-433-4544 R. M. Shields 815-433-5659 J. A. Miller 312-871-3479 J. W. Gieseker l Mechanical (1) - (Site Emergency or General Emergency) 815-434-3606 f J. M. Damron 815-672-6675 i M. A. Peters 815-434-1755 li K. C. Wittenburg 815-458-2489 J. O. Bruct ak 312-424-2783 -il D. R. Winterhoff s CALL CONTROL ROOM (X208) OR TECHNICAL SUPPORT CENTER (X712) AND REPORT STATUS OF AUGMENTATION FROM CALL LIST C. i r. '3 "e D -=m w-v -m.-- am 3 -.wqn v = 'r-m, q

___ _ 7 _ _ LZP-1320-1 Revision 6 October 17, 1883 J 14 '1 ATTACHMENT 5 (Cont.) 1, CALL LIST D I (Rad / Chem GSEP Caller)

Reviewed every calendar quarter.

\\ ..i General Message: LASALLE STATION HAS DECLARED A(N) J l (SITE EMERGENCY OR GENERAL EMERGENCY). PLEASE REPORT TO ) THE TECHNICAL SUPPORT CENTER. .} NOTE il The following personnel shall be called in the approximate order of distance from the site as they appear below, q .lbi Accident Assessment - ($1to Emergency or General Emergency)

)

~! 0FF-5ITE (4)/IN-Pt. ANT (1) = TOTAL OF 5 ione Phone Name J. G. Lewis 815-795-5881 C. E. Magistro 815-357-8814 L. R. Aldrich 815-434-1142 815-434-1906 T. D. Hodges 815-433-3566 L. C. Bryant 815-584-3090 ~ T. Riner ~ 815-942-8020 P. G. Knol1 815-942-2818 W. F. Elsole 815-476.2337 K. Zitzka 8!5-741-1015 D. W. Hieggerka 815-744-4098 K. C. Watson 815-942-8831 I off-$1te Pager l. 11 M Rad / Chem Lab (1) t i 815-634-2664 R. sayers 815-942-8477 J. A. Schuster 815-942-4788 P. T. Nottingham 815-942-5094

s. Geistkamper 309-432-3536

.j L. N. Shearer 815-433-3958 i J. Terrones 6ff-Site Pager 815.-942-8832 l ed i l i I A t .A : - -......_.:..,.._,. _. _ _ -

LZP-1320-1 R: vision 6 j October 17,,1983 f ATTACHMENT B (Cont.) 15 (Fing!) { f CALL LIST D (Cont.) n \\ e-ON-SITE (1)/RADIAT10N PROTECTION (4) = TOTAL OF 5 Homs Phone

j Name J. Beck 815-357-6987

'j R. Rod 815-357-6951 D. senckendorf 815-673-2625

i G. Thompson 815-448-2551 M. Shabala 815-673-1279

,4j 815-634-8360

.2..

8. Benson

, f.ij R. Rowland 815-672-2095 m S. Kerr 815-673-1620 1 T. R. Brown 815-673-2967 ~.:Il S. Tutoky 815-673-3661 ~i G. Spears 815-434-1759

j C. Kelley 815-433-5756 E. Wol fe 815-434-3940 i

O. Vanderploug 815-942-8131 S. Butler 815-942-0707 J. Fletcher 815-223-8094 4 D. Jerzycks 815-741-9603 K. Skinner 815-722-6969 R. Varju 815-722-0863 T. Gibes 815-833-4215 J. Dietz 312-799-5582 ~ CALL CONTROL ROOM (X208) OR TECHNICAL SUPPORT CENTER (X712) 'AND REPORT STATUS OF AUGMENTATION FROM CALL LIST D. l h

1.1 1

.i t ~ [! l L: i 'f-: ' 'I f J f 4 e wT- -w v---- y --4 r E w e ww&M -- w ye-w -e%--'f*-tr-- - ' - -t-Tw-ow-N we y e' ewe--e-w a-- -== --m.-*-

4 i I L2P-1330-50 l Revision 1 Cctocer 17, 1983 'i 1 RADIATION SURVEYS UNDER ACCIDENT CONDITIONS A. PURPOSE .] The purpose of this procedure is to provide information 'l relevant to the performance of radiaticn surveys in plant ,] areas during accident conditions. Also proviced are survey diagrams for lesser affecteo a.eas which are fj expected to be occupied under these conditions. T; .n a. ggggggggg 6 l. LRP 1280-2, " Dose Rate Surveys." -t 2. LRP 1350-22, " Deployment of the Ecerl ine PING-III." 3. LRP 1350-23, " Deployment of the Ecerline SAM-2." 4. LRP 1360-6, " Air Sampling of Suspected Raoloactive Airborne Areas." 5. LRP 1480-2, " Contamination Surveys." 6. LZP 1360-2, "use of Potassium Iodide as a Thyroid Bl'cking Agent." o A Review cf P MCMELRadi at ion yvel s, 7. 2 t 3.US.k.919lle Qum 5tation in Reg o g j o, J 2 12929._of NUREG-Q1]g, Revision 1, Item 3 ./; August 8, 198C. a 8. CCP-G003, " Particulate Radionucl ice Anal ysi s." 4

d, 9.

AIR l-81-331. -l Id. AIR 1-83-32703. 't C. E$1350,UISITE] - ? 1. Prior to entering areas of the plant which have or i are expected to have aonormal radiaticn levels, an assessment of the levels enroute to and near tne j area in question should be perforrec using insta11ec . ?q plant instrumentation. Attachment A provides a listing of instrumentation which may De useful in ..] assessing the situation. 1 -gn w + % -g

l ) I i } f LZP-1330-50 ) i Revision 1 1 I Octooer 17, 1983 4 2 3j 2. Equipment: --5{ a. Oose rate surveys. .1 1) High range exposure rate meter. An }) extendable p,roce is preferred.

L l.1

-d To preclude the entry of noble gases into the chamoer, ' $j air ionization chambers must De sealed in plastic. A jj 2) Appropriate survey sneets for the area to De surveyed. Survey sheets for areas i expected to oe occupied unuer emergency conditions are provided in Attacnments B througn E as follows: a) Attachr.ent 8: Technical Support Center. b) Attachment C: Control Rcom/ Operational Sup. port Center. c) : Assembly Area. 691.E Additional survey forms, for other areas of the q plant, are located in the OSC supply locker. j D. Air sample surveys. .8 1) Grac samples. '1 1, a) AC or DC powered air sampler with 7 comoination particulate /locine i cartridge noloer. 1 o) Particulate filters - 47mm Hollingswcrth .i and Vose Model LB 5211 or equivalent. 1 c') Silver Zeolite cartridges - Science Applications, Inc. Model'GY-130 or ] equivalent. -) 9 ,w--%_

~ 1 l i i 1 i LZP-1330-50 I Revision 1 'l Octooer 17, 1983 3 3 '.;) ] d) Stopwatch. i + 2) PING III constant air monitcrs lccated as follows: a) Tecnn ical Support Center (TSC). d /! 0) Operational Support Center (OSC). <-1 $~} c) Control Room. ?j d) Assemoly Area,.

]

-1 c. Contamination surveys. (See Reference 5.) 4 A 0. PRjQQ],,Q% 3", 1. -Respiratory protection for plant areas where major releases have occurred or are suspected will ce SCBA. In cert.ain circumstances overall exposures can be reouceo by using a combinat,icn Full Face respirator with Potasium Iodice Thyroid olock in 1 jieu of a SCBA, but it may oe determinao ceforehana that the area in question is capable cf sustaining life. (See Reference 6.) E. L E A,,T, IONS ANOJ Q g M 1. If a dose rate survey instrument cver ranges or i responds in a questionaole._anner, immeciately - aM relocate to an area of relatively Icw dose rate levels and investigate tne cause. Do nct assume an - ' q/ over ranged instrument is malfunctioning. 2. Radiation exposures shall oe kept as low as is reasonably achievable celow the maximum allowaole quarterl y values of: a. 3,000 mrem to the wnole booy. y-O. 7,500 mrem to the skin. c. 18,750 mrem to the axtremities. F. gR,,gg,g DyRJ 1. Determine a rcute to the area requiring survey tnat will minimize exposure of the individual performirg the survey. See Step C.l. aDove ano Reference 7.

4 l l f LZP-1330-50 j i Revision 1 1~ Octooer 17, 1983 1 4 i 2. Dress in appropriate protective clotning. Prctective clothing requirements for areas that have not oeen evaluated will be determired by the urgency of tne situaticn. The preferreo clotning is as folicws: a a. Coveralls wi th cloth noco. I o. Cotton or Jersey gloves under latex gl oves. '3s c. Cloth snoe covers under rucoers (or coots). .1 .,j d. SCBA respirator. .y

1 EauI19s 1

Respiratory protection for plant areas wnere major releases have occurreo or are suspected will be SCBA. In certain circumstances overall exposures can be reducec by using a concinaticn Full Face respirator with Potassium Iodide Thyroio clock in lieu of a SCBA, but it must De determined oeforenano that the area in ' question is capaole cf sustaining life. (See Reference 6.) 3. Obtain dosimetry of the proper range. The minimum requirements are as follows: a a. A minimum of 2 self-reading pocket dosimeters, one of which will oe 0-lR or 0-1CR in range 4 ano tne other will oe 1-100R or C-20CR in range. o. TLD ring badge. c. Electronic dosimeter, 0-9999mr in range. GU r i The electronic cosimeter provides a timekeeping aio in that the necessity for repeatec coservations of ,i sel f-reading cosimeters while in elevated dose rates fields can be minimized. It is not necessary for each memoer of a survey team cr work crew to ce l issued a dosimeter of this type. 4. Ootain equipment as specified in Steps C.2.a. Enrougn 4 C.2.c. as appropriate. 3 5. Proceed to the area in neeo of survey cying the following techniques as appropriate: i i-

L2P-1330-50 i } Revision 1 ) i Octooer 17, 1983 -j 5 .' l } a. Minimize time spent in areas of relative nigh j dose rates. ) D. Maintain distance from hot spots or otner ~j sources of high exposure when possiole. l c. Take advantage of installed sn i el d i ng. Note .i areas of relative low dose rate wnich can ce ' M3 used as waiting areas for work crews. Areas Ud of low dose rate should be utilizec for activities ' * "' 1 that must be performed i n tne fielo such as .d checking dosimetry for exposure assessment or sj documenting survey results on survey forms. 1 N 6. Once the area in neeo of survey has osen reached, i conduct surveys in accorcance with Reference 1, 4 i ana 5 as appropriate. Gather all equipment and return to the CSC. l EU To minimize the spread of contaminaticn, survey all equipment. Normal control points may nct, be appropriate under accident conditions, but every .- l effort should be made to maintain the Auxiliary Builcing free of loose surface contamination. 14j 8. Analyze air samples in accoraance with References 3 and 8 or Reference 2 as appropriate. 'J 9. If the TSC and CSC are staffeo, report survey results to one of the following listec in order of priority: -1 M.] 'l a. Rao/ Chem Supervision in the OSC, Ext. 207 wno will in turn relay appropriate results to tne sf j Rad / Chem Director in the TSC, Ext. 723. ' b. Rao/ Chem Director in the TSC, Ext. 723. a 10. If the TSC anc OSC have not yet been staffea, report survey-results to Operating Shift Supervision, Ext. 203. 11. Document all results on appropriate survey forms and route to Radiation /Cnemistry supervision for review (Reference 10). i. o p ,.,--,,A y-e_,.y, p.y_. 7%. ,.,____,w-, ,,,,,e,.,,,,,,,.w,- m.w_y.__ m

.i - ) LZP-1330-50 Revision 1 October 17, 1983 6 G. ggggs s l 1. None. ..I H. TEQHN M SPEQ FIQ TION REFERENQ S 1. None. ..f i . 'l , 'i ; 4 O O k n t .".1, f e 4 .. l{ i t

. 2,,. ;,, s. ;.j,,, b._....., i.,,,, _,,,2,. m.... ?. :..L...a. . 2.. _ _... - u. , r. LZP-1330-50 Kevision 1 October 17, 1983 7 m. j ,/,' -4 hb J p -ATTACHMENT A ~ . PROCESS'AADIATION MONITORS ~" l Range Floor. '~' Channel Name Location Elevation (mr/hr) s. Main Steam L!ne Reactor Bldg. 710' I - 10 Carbon Bed Vault Off Gas Filter Bldg. 674' I - 10 2 Rx Vent. Exh. Auxiliary Bl'dg. 786' .01 - 10 2 Fuel Pool Vent. Er.h. Reactor Bldg. 820' .01 - 10 / Control Room "lVAC intake Auxiliary Bldg. Roof 843' O.1 - 10 Aux. Steam Reboller Turbine Bldg. 768' O.I - 10 t 6 1 -Off Gas Pretreat. Turbine Bldg. 754' I - 10 i i i i

A 1

L ' ~ 4 !- . i.. .t0 1 2 r, -f r j, , u,, ,.., ;f f.ggg,j , g., g. ..._......_._x.c2m a.- m.m., g l. L. I L-1.a e 8. O 1 i. L a: R M.J a.s. LZP-1330-50 ~ ATTACllHENT A (CONT'D) Mevision 1 October 17, 1993 .i AREA RADI ATI(RI iMIIII1Vi!S g Range local Ind. j Channel Name Elevation (or/hr) & Alarm l-1, Standby Cas 820'6" 100 - 104 1-2 RWCU Phase Sep. 807'0" 100 - 104 3 l-3 Ex Bldg. Sample Sink 786 6" 10 10 X 8 O A 1-4 Containment Purge 786'6" 10 - 10 ' t ~I 1-5 North HCU Hodules 761'0" 10 - 10 ~ - 10 l-6 South IICU Hodules 761'0" 10 ~I 3 1-7 Off-Cas Equipment & Sample 754'0" 10 - 10 X 0 1-8 Tip Room 740'0" 10 - 10 X ~I 1-9 Tip Drives 740'0" 10 - 10 1-10 CRD Storage & Repair 740'0" 10~ - 10 1-11 HW RilR lix 710'6" 10 - 10 1-12 SE RHR lix 710'6" 10 - 10 ~I 1-13 Turb. Bldg. Sample Sink 687'0" 10 - 10 X l-14 Cond. Demin. Regen. Viv. Aisle 651'0"

10 - 10 X

l-15 URC Valve Aisle 6Mi' 10 ~ 10 X 613'4" 10 - 10 X l-16 ,RCIC Turbine ~I I-I? IIPCS Pump 673'4" 10 - 10 i 1-18 Conds. Booster Pumps obl'0" 10 ' - 10 ~ 8 I, 4

.s. , 3;,,. i.,,,_ _,,,. f,. f, _,,, _,, _,, c,. - 1.';,.,.. y a ...c,._ ;r..c... ; t'

* ~*

11 L

1....

t L... L J-I.. G 1.- 1. La.a t.no a A.s ~ L4. 4 .a ~ LZP-1330-50 ATTAORfDir A (Colff'D) Revision 1 ~ October 17, 1983 ~._

i AREA kADIATION N0041 TORS 3

a Range Local Isid. Channel Name-Elevation (or/lar) & Alarm

1-20 Spare
1-21 Spare 1-22 Spare 1-23 Spare a

i ] l-24 Spare 1-25 Spara 1 1-26 Spare 1-27 -Spare l-29 Spare 'l-30 Spare 1 1-10 Spare i e t 4 i W e f A ? 1 1

..l- ~ g, ;,g.g.,,,,,, g,,, .... a_ _. , _; C _ e.a. er.. t 1) E t L Li .. a. L 12 ' It..J M. D 'A ' t t.a s LaJ t.a t.. 6.e t LZP-1330-50 j 8*Vl510" I ic ATTACIDIENT A (CONT'D) October 17, 1983

a 10 4.

Area Radiation Honitors l Range Local Isul.. Cliannel

bee Elevation (ar/hr)

& Alarm .2-18 Standby Cas P20'6" 10 - 10

2-2 RWCU Phase Sep.

807'0" 10 - 10 ~ 2-3 Rx. Bldg. Sample Sink 786'6" 10 - 10 X 2-4 Containment Purge 786'6" 10 - 10 2-5 North HCU Hodules 761'0" 10 ' - 10 ~ ~I

2-6 South HCU Hodules 761'0" 10

- 10 ~I 2-7 Off-Gas Equipoent & Sample 754'0" 10 - 10 X 2-8 Tip Room 749'0" 10 - 10 X 2-9 Tip Drives 740'0" IC~ - 10 2-10 CRD Storage & Repair 740'0" 10 - 10 2-11 NW RilR Ilx 710'6" 10 - 10 2-12 SE RHR Hx 710'6" 18 - 10 ~I 2-13 Turb. Bldg. Sample Sink 687'0" 10 - 10 K ~ X 2-14 Cond. Demin. Regen. Vlv. Aisle 687'0" 10 ' - 10 2-15 Spare 2-16 RCJC Turbine 673'4" 10 - 10 X 2-17 IIPCS Pump 673'4" 10'I - 10 i 2-18 Coad s. Booster Pung 663'0" 10 - 10 f 2-19 Sparu ' 2-20 Spare e.

1 1 a, .w.w _..W . a La '. ; -.4. ,,13.g A'_ *,,, _ g,, _ ,- g;, j_ 4 ..w n. t. 1 l..

8. A.

L 4 d. L... La '1Lt kJ Ash b.a.S Esed A L-Lp ^ ~ LZP-3330-50 j ,'d,- ATTACIMENT A. (C(HT'Is) Revisirm I October 17 1983 Area Rad 2atten Monitors gg j; t) ) Range Local Ind. j. Channel Name Elevation (or/hr) & Alarm i i: l. 2-21 Spare 2-22 Spare l, - 2-23 Spare

2-24 Spare iI 2-25 Spare l

2-26 Spare 2-27 Spare 2-28 Spare 2-29 Space 2-30 Spare t i e m o e a e t.

2 h..--. - ' ' ? - -Y w.O.l: _ -

a.' iL....,...ux' g [ L.,, ( _., i j iA 1_ D 'L. h ad bE L8 L n. LZP-1 30-50 Revis on 1 3 ATTAClelENT A (CONT'D) October 17, 1903 12 Area Radiation Honitors Range local Ind, Channel Name Elevation (mR/hr) & Alara 3-1, Refuel Fir. liigh Range 843'6" 10 -10 X 3-2 Refuel Fir. Low Range B43'6" 10 ' - 10 ~ I 3-3 New Fuel Storage Vault di3'6" 10 ' - 10 ~ ~I 3-4 Refuel Fir. Equip. Itacch 843'6" 10 - 19 X ~I 3-5 Vent Stack Sample I;15'0" 10 - 10 I ~ - 10 3-6 Main Control Room 768'0" 10 3-7 HP Turbines 768'0" 10~ - 10 3-8 Turb. Bldg. Decon. Plt 768'0" 10~ - 10 X l ~I 3-9 Rx Bldg. Trackway; 710'6"' 10 - 10 ~ 3-10 Hot Lab Corridor 710'6" 10 - 10 X ~I 3-11 Turb. Bldg. Bset. Elevator 663'0" 10 - 10 3-!2

0. G. HVAC Exhaust Area 710'6" 10~

10 ~I 3-13

0. G. Upper Beat.

690'0" 10 - 10 X 3-14

0. C. Char. Ads. Viv. Aisle 674'0" 10 - 10 X

t j -2 2 3-15 Serv. Bldg. Office Corridor 726'6" 10 - 10 ~I 3-16 Laundry 710'6" 10 , 10 -I 3-17 Hachine Shop 710'6" to -" 103 X 3-18 Serv. Bldg. Lunchroom Corridor 710'6" 10~ - 10 2 3-19 Spare i f 3-20 Spare I, f

y; .s

.,2 i ': A h;'..

.... ; c. 'c... ds x.;. _.. .._ _ _ _u. u.a. LSd Z.1._ _ r .L 1. a w __..__.__. s 1 ) .u. 3*" L J i _m. 1 na L. uh li. L.s LAa - A L -. - 'a g, i i LZP-1330-50 Revision I eiTTAct'HENT A (CONT'lO October 17. 1933 13 Area Radiation Monitors (Radwaste Control Room)

4 Range leral Ind.

Channel Name Elevation (mH/hr) & local 4-1 Conc. Waste Tanks 10 - 10 4-2 Unit 1 F1. Dr. Conc. Pump & V1v. Rs. 10 - 10 ' 4-3 Unit 2 F1. Dr. Conc. Pump & Viv. Rm. 10 - 10 f.-4 Chem. Wst. Conc. Pump & VIv. Rs. 10 - 10 4-5 Radweste Control Room 10~ - 10 4-6 Drum Labelling Station 10 - 10 ' 4-7 Radwaste Compactor 10 - 10 5-8 N. High -Lyl. Drum Storage 16" - 10 4-9 S. High -Lv1. Drum Storage 10 - 10 e e 6 9 I f + 9 4

wwe.mr- .ee de+= e 6 @**m(- epa.- e d l M ao i A = O a *" N i e = C C l m Q n= - m t== en Q a'$ 8 em O

c. > *e q', N @ O4

.J E O - ..)

1 "I

8 i I I 4 'l ww m3 >= z. w =g =w J

'8 eg. 3e

.'l o >= Z - > L i >- w

8 m

6 2 2 .1 j e. a. ,; t

s: :

4 ,.e ,e

1

.3 ~ sne Neo k CL >= EW f. 443 w _a 4 4 2- >= e-N M M i e 1 i m r Y. z,J L 1 4 .c ,,8 4 ,L 'e 3*+ E v -I (lh.C e . a.4 4g d ,, o<g .E1 w g > = > E Ew2= w J==

i Ww a

2. t

.m >= .a 7.'i gGwwC ~~4 Oc> C AJwmC 4..J g== 4 3

C mwmwa

'4 W *C E .== g m ad => u6 ww e.. >= m *= N M f 1 m. .m, yg y s y -y ..,r

E ., -r 4-6 m 8.,., i _ 4

e. m.

l l l ,.,. 8 .'i h C U m l L ooo F aao- .- l p,__ l T-N - rs y ww mz .- z aw 2-P 4 o L .- w 't -m 3

3. -

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.. 4 j 0 -+, C a r.... [T l ll l I m g .1 0 R Y g t 1.... ...seuw.- c. ~.:.:1 t l s. i l --1 m. r., ao l l E 1 l o n. . I I I L i >= 6

- b.

r_= - m @-l

i._: .::

^ m E. a l a. .i 15 E Em d<.: :...- ;: i '.~ m - m m.a. .a: ac l. m

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== s a. S w=,e L.

==% u:- w. e ac. as sn m \\ s e .J 7 7 d . l., E*... t i f .e s u<-mm s ., *.,.~

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a I. *l %'.*T I -m eeo -een e M -N a y F =--.-e-- -i- ---r. .c- -, --. -+,p g, ,,,..,3-, --.-,.i--m.,yn,.--,y--,---ag-.--mi----9 ,m-,.- ,-,r-g-- =4-mw

~. -.. -.. S..... I.i te e

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~... m- .i 4 g. s c =:i" ' o ~ C

s m~s s.1 i
8 A.!

2==== :. ' m-c

==- - in.o

==: i-

c. >.o.

. t. - ~ :== N eu e ~~ ""o-j s, t. t . =.. ( t.. l M,

:. I:

.t ww en 3 s *. .f. =

EWMW

=, er i, .3 rw

.ll

.s J a -a 1;. l 3 .~, 1 D. s. t.. J y t t . f.l..g * ! ...t,.~., -l i z o t E

*.l-S m,, m a

~. - 9,,; u n. l s. W m m m 5 g= le g' i Es i E.":7 d i 3 m J.___ l -~m .n: lb .. =.. b s. -g i i ii i i ii i i -- ;.i.. g -,o g 4 a O' s[,,/ I i'. : ~ a, = - i, e s 2 a l N. ss u s s s / s .a s s ,4-p x t-E 'T.. *. z~ m x_-

..j 3

6,,,- ,a Illi O W to a aa- . s. .a. s s om<r t m a m ac s s m; E a 03..

s t

v<-~- sid): .:.c pq fl j,1,/,.- Lb 4 -.a e -= w- --m1, _y-_ .w--

q

,) ,.--e.,mw---.--- ,,.,w,,p,~ v

w w

gi-w-.- ..-g-

-. t., .... ~. :. -... c...:'...:.: i c..... =... :.. .... :. ;,.. e: :.. L... w.........~.a. :..... -. ~ i 1.s t-ijju :,o i N' I ....v. ATTACitMENT D October 17, 1983 ..... C.:3,:.'..

i.5 0:'o

.i U: !d! -. l.<f c.. ,7 (Final) ASSEMBLY AREA RW ELEV. 710'/706' 1. RAD LEVELS IN mR/hr DATE 2 i 2. SMEARS ( ) IN dpm/100cm TIME 3 K = 1000 MWE INITIALS R5 VIEW

.......J

[. =,~.. i. : AIR SAMPLE. GRAB-PING

w......

Ar i r, .m y a,J:h, 4.,i. 1 2 - 6 y:. B-8 3 7 i m 4 8 -::'T .n..,,

1...

V < I. e .s ........s- ..: f.'.s.....:..;.: ~ .h.. '..:.:.5;...~..:c;y... i.. :;.'.:..:...:..: :.'i: ; :.:.:::.: :.' '.!. ?*.4 1::r1 VA ^ W . s g.c.. :. : ..s',r_ i.- .5: U u ':y.c. . r.

c.; :- ;i:.
.: i.~. : ~r.~. u,. _.......,..

+ e e e e j m ,4 ~ l .e.-:,'.,.,............... :...::............:....,.., . ~..::. .....e..,...:;.....,.....,~..,,.t: : .,e......... :.., c:..s........,..,...s. s ..e................... .....c........ l i i i I. lI ' I, g e i l 1 i i. ,l i li i e .i ,i e i i, i ii e , e i l

1. 1

.f g I 3 .r g 3 e .t i l . i i i F 3 3 i R i i a e e a .....,..,..J:.s..*.~.=,.,';."...***s.*".**.~.',,., . U. T..g t

:.". ';.,* =.* e' l s ".. :: * '.",,.= :.*.',*. *,.. =... * * * * * ; * :. ',..': % :y. :

.. :~,, : *

s :.

.e... :*. *... t..... : ; ... : e. ....s ,..=...s ...V ~.*g..... ..../;*,,....,,:.,,,,,, 3.g*.*..,.,.;...s*.,..*.,...

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.8... . of..

g.,,... :. ;......

g.

~ j LZP-1610-1 i Revision 1 l OctoDer 7, 1983 1 1 4 i RECOVERY AND RE-ENTRY PLANS .i A. PURPOSE The purpose of this procedure is to provide guidelines for post-GSEP incident recovery and re-entry. i B. REFERENCE 1

j 1.

Rad i ol o_al ca_1__As_si stancg_Plgn, Reg i on 5, Department ,.i of Energy. 'i } 2. Commonwealth Edison Company a Radiation Protection Standards." i 3. Generating Stations Emergency Plan (GSEP), Section 4.0e Recovery. _ EREQUISITg} PR C. 1. None. D. PRECAUTIONS 1. None. E. LIMITATIONj_AND ACTIONS 1. This procedure is intended to serve as a guideline l for recovery and re-entry following a GSEP incident. ( Detailed procedures may De written for specific j operations as the need arises. i F. PROCEDURg 1. All on-site recovery efforts will De oirecteo, l I coordinated, and controlled from the Emergency l Operations Facility (E.O.F.). .'t 2. The Emergency Operations Facility will ce manned Dy i - J the Recovery Organization whicn wil support ene l normal GSEP Organization with the exception of tne l plant operations manager who will remain assigneo to the TSC. l 3. The Recovery Organization shall consist of the following directors: 1

e, s LZP-1610-1 Revision 1 October 7, 1983 1 2 a. Recovery Manager. I i 1) The Recovery Manager is responsible for .j overall activities of the Recovery 4 Organization. D. Emergency News Center Director. j .i.i 1) The Emergency News Center Director is j responsiole for collecting, verif ying and distriouting information about the emergency ~ ?) to the news media. t -{ c. Administrative and Logistics Manager. .j i 1) The Administrative and Logistics Manager is responsible fnr providing administrative, logistics, commmunications, and personnel support for the Recovery Organization. d. Scheduling and Planning Manager. 1) The Scheduling and Planning Manager is responsiole for supporting the Recovery [ Manager in tne short term planning, scheduling, and expediting of Recovery Operations. I e. Tecnnical Support Manager. l 1) The Technical Support Manager is responsible 1 for the analysis and development of plans .i and procedures in direct support of plant , Ji operations personnel witn the objective of taking the plant to ano maintaining a ' ~i safe shutdown condition. i f f. Plant Operations Manager. 1) The Plant Operations Manager is responsiole for the implementation of the in plant -j recovery activities with the cojective of taking the plant to and maintaining it in a safe shutoown condition. ,m g. Waste Systems Rad.lation Control Manager. 1) The waste Systems Radiation Ccntrol Manager is responsicle for aeveloping plans and i s 9* w g 1 ,.e-g. -..y-i- --w. -p

... _. : *.L.. _ ; -- : ' ' ~ ~ T- -~ - ~ - - -7^ n l l e f LZP-1610-1 Revision 1 1 OctoDer 7, 1983 3 a d procedures to process and control liquid, 4 gaseous and solid wastes in a manner ~'

2) section entitled " Personnel Occupational
*j External Dose Limits." i j o. If the limits specified in part F.6.a aoove <? must ce exceeded, restrict personnel exposures fI to the recommendations specified in Ceco '1 Radiation Protection Standards (Reference 2) ) section enti tled, " Personnel Exposures under Emergency Conditions." Prior approval of tne "9j Station Superintencent, the CECO Medical Director and the' Radiation Protection Supervisor snould be obtainea wnenever possible oefore exposing j personnel to doses in this range. 4 w 4-y guirs-- -s+i-- . -.r .--e-'u r -www-+---e.-rw'- '---+2m*-M"-------W --'IT""--PmT'W'M F
P*'r-4ar-su w'v--F'
*'m=-w' D-'m'wY'U--'-'r'we- - ' -7y-ve-9N"*"'7vu - - - - -ry
. - - ~. _ 4 j ,s J .o LZP-16LO-1 Revision 1 October 7, 1983 (final) c. Use personnel cosimetry, as specifiec by Radiation Protection. l 7. Personnel Internal Exposure. 'I a. In emergencies, use respiratory protective -j equipment as determined by Radiation Protection. l b. As soon as possible after an emergency, Dioassay .'j I all personnel who have been oirectly involveo il in the recovery actions by those methods deemed appropriate by Radiation Protection. 8. Determining the Extent of Contamination. a. Recovery personnel will use station instrumentation ano appropriate Raolation Protection surveys to cetermine the extent of radioactive contami nation in the emergency t area. Onsite Radiation Protection survey equipment is normally locateo in the station control room, counting room, radiation protection office, the hot laceratory and in tne station warehouse. Additionall y, a meteorological tower and a system of environmental surveillance i stations monitoring the environs provice. Information useful during offsite emergencies. i o. Routine proceoures nave Deen estaDlisneo for operating survey equipment necessary to oefine contaminated areas. .) G. SHECKLISTS 1. None. H. TESMNIC AL SPECIFIC ATION REFiR[N(El i 1. None. i > 'j i a i i~' x, t 4 t &}}

ML20086J819

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