ML20072L056
| ML20072L056 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 03/02/1983 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20072L014 | List: |
| References | |
| PROC-830302-01, NUDOCS 8303310092 | |
| Download: ML20072L056 (52) | |
Text
{{#Wiki_filter:a I 5/15/82 LZP INDEA PAGE 1 PROC. 6G. TITLE RE/. dEV OATE CISetETT.) LIP 10C-1 DELETED C3 11/80 01
)
P 100-2 DELETED C+ 11/80 31 LZP LCC-3 DELETED 03 10/80 01 P 20C-1 DELETED 02 11/80 01 l 200-2 DELETED C2 11/dC Cl EP
.20 200-3 DELETED C2 11/80 C1 LP 2CC-4 DELETEC C3 11/oO 01 L4P 210-1 DELETED C2 10/80 01 LP 3C0-1 DELETED C4 d/dC C1 LLP 3CC-2 DELETED >
C3 11/80 01 LP 310-1 DELETED C3 11/80 01
~ . LP 320-1 OELETED 02 10/dC 01 ZP 33C-1 DELETED 01 10/80 01 l's 36C-1 CELETED -
01 10/80 01 LLP 350-1 DELETED 02 10/80 01 LP 3eC-1 CELETED 02 10/60 01 LLP 370-1 DELETED 01 10/60 01 id *CC-1 DELETED CZ 11/80 01 ZP eCC-2 OELETED C2 10/8C 01 IP *CC-3 DELETED C1 ll/8C 01 iP *10-1 DELETED C1 11/oG 01 L49 *20-1 OELETED 01 11/8C C1 ZP 510-1 DELETED C2 10/80 01 LIP 520-1 DELETED C2 10/80 01 ZP 320-2 CELETED C1 10/8C C1 LP 52 -3 DELETED Cl 1C/80 Cl ZP 53C-1 DELETED CL 10/8C 01. E 8303310092 830325 PDR ADOCK 05000373 PDR p A l __ _ _ _ _ _ _ .+_ _ _ _ . _ - _ _ _ . . . _ . ._ _ _ _ _ . _ _ _
l E_ ___ 5/15/32 LZP INDEX PAGE 2 ]
>RuC. NO. TITLE REV. REV DATE CISAETT LZ3 530-2 DELETED C2 10/80 01 ZP -i-C-l DELETED C1 10/8C 01 L4P 7CC-2 CELETED 01 11/60 01 EP 710-1 DELETED C2 10/ oc Cl IP SIC-1 DELETED 01 10/dC 02 RIP el;-l DELETED C1 10/dC 02 2P S3C-l DELETED C1 10/80 C2 LZP 350-1 DELETED CL 10/8C 02 4P 8::C - 1 DELETED Cl 10/8C 02 L49 SJG-l DELETED 01 11/80 02 ZP. ill0-1 STATION DIRECTOR (ACTING STATION OIRECTOR) IMPLEMENTING PROCEDURE k J 02 LP 1120-1 GPERATICNS DIRECTOR IMPLEMENTING 04 z/S3 02 OIRECTOR
- P L13C-1 TECHNICAL DIRECTOR IMPLEMENTING PROC. C3 4/81 02 LLP ll*C-1 MAINTENANCE DIRECTOR IMPLEMENTING C1 11/SC 02 PROCEDURE _
EP ll50-1 STORES CIRECTOR IMPLEMENTING PROCECURE Cl 11/80 C2 l f gL2P llo0-Cl ACMINISTRATIVE DIRECTOR IMPLEMENTING C2 1/82 02 t g PROCEDURE l LIP ll70-1 SECURITY DIRECTOR IMPLEMENTING C3 1/82 02 PROCECURE L4P ,1150-1 RAC/ CHEM OIRECTOR IMPLEMENTING 03 7/81 02 PROCECURE t!P . LEO-2 RAD / CHEM OIRECTOR INITIATdo Cl 11/80 02 ENVIRCNMENTAL MONITORING ACTIVITIES LL2 1200-1 CLASSIFICATIONS OF GSEP CONDITIONS C3 f/83 Cl LLP 12CC-2 CLASSIFICATION CF A NO3LE GAS RELEASE Of la.lga 02 E LLP 12CC-3 CLASSIFICATION CF AN I3 CINE RELEASE 01 2/82 01 LZP A20C-4 CLASSIFICATION CF A LI'JdID R ELE AS E C1 5/s2. al L!c 1410-1 HAZARCOUS MATERIAL INCIDENTS REPORTING Cl 11/81 01 E
. . . . . . . . - - . - . . _ .L- -
5/15/42 LZP INDEX PAJE 3 300C. NO. TITLE REV. RE/ OATE DISKETT:' LZP 1220-1 EMERGENCY TELEPHONE NUMBER Cl 5/81 01 0 12 2 0 -<, DELETED Cl 7/81 Cl l E 03 L .'. P 131C-1 NOTIFICATIONS .3/gg 02 P 132C-1 AUGMENTATION CF PLANT STAFFING @ l[g3 C2
!P 133C-1 P C & OF REACTOR Cl ll/3C 02 L40 1330-2 Pd IDEN SAMP NG OF TH,5 PRIMARY C1 3/81 C3 C 0 f, TAIF T SP RE FOR R iDIGIDINES DE1 E All C
N b [%ms ES i 1 ZP 1330-3 POS T-A tT Mg . LIMARY C2 3/81 03 C O.]TAI 4j Pi l f , LP 1330-4 PC CCIO T SA PLING OF HE PLANT Cl ll/8C C3 VE T R P TICULATES LIP 133C-5 POST-ACCICENT NOBLE GAS RELEASE RATE CO 11/80 03 DETERMINATICN I LIP 1330-6 DELETED 01 7/81 03
~
5 . LIP 133C-7 P T- 6 ET - N F HE STANDBY Cl 11/80 02 GS T, - T T M EFFLUENT LIP 1330-8 SAMPLING LIQUIO PROCESS MONITCRS Cl S/Sa G3 DURING LICUID MONITOR HIGN RACIATION ALARM CCNDITIONS E LZP 1330-10 DELETED Cl 1/32 03 5LZP 133C-Il DILUTION ANC TRANSFER OF GAS SAMPLES 00 ll/dl 03 ZP 1330-20 POST-ACCICENT ANALYSIS OF 3 ARON 00 3/a1 03 l (BACKUP PROCECURE) ZP 1430-21 PCST-ACCIDENT ANALYSIS OF CHLCRIDE C3 V82 03 LIP 133C-22 CALISPATION OF THE MOCEL 10 CIONEX C2 4/b2 03 l IGN CHRCMATCGRAPH l IP 133C-23 CETERMINATION OF REALTOR CJGLANT PM, C2 6/d2 CJ CO.10UC T I V I TY ANC OISSCLVE0 GXYGEN CONCENTRATIO'4 AT THE HIGH RADIATIO.a E l SA"PLE S Y $ T E :'
- .. . ~.- -.....--. . - -... -
E..... 5/15/92 LZP INOEX PAGE 4 3RCC. NO. TITLE R EV . REV OATE DISKETT 2P 1330-24 DETERMINATION OF REACTOR COOLANT 02, '/83 C3 HYOROGEN CONCENTRATION AT THE HIGH RADIATICN SAMPi.ING SYSTEli LIP 13aC-25 SAMPLING OF REACTOR CCOLANT AT THE C2 6/62 03 HIGH RAGIATION SAMPLE SYSTEM i 2P 1330-26 SAMPLING OF CCNTAINMENT AIR AT THE C3 4 82 03 ( HIGH RACIATION SAMPLING SYSTEM LE dY I? 133C-28 SAMPLING OF R A010 ACT IV E W A ST E L'I:Jb ICS C2 6/32 C3 RADICACTIVITY AT THE HIGH RADIATION LP 1330-29 SAF Ie T T ?f1 A TION CO 4/82 C3 SA.1P lTG YST (VA RATION AT TH ALTE N L PANEL) LP 133C-30 TRANSFER CF WASTES FROM THE HRSS WASTE 00 11/81 03 TANK AND MASTE PUMP 133C-31 ST ACCIDEN M' l b AMPLE MOVEMENT AMPLING OF THE GENERAL ATOMIC CO 00 12[82 6 81 03 13'JO ~ @ 133C-50 b b Ni(YGY bNDER ACCIDENT CC 10/81 03 L4P CONDITIONS IMPLEMENTING PROCEDURE FOR FIRE: C1 9/81 02 L2P 134C-1 . FIRE MARSHALL IMPLEMENTING PROCEDURE FJR FIRE: Cl 9/dl 02 LLP 1340-2 FIRE CHIEF (CESIGNATED SHIFT FOREMAN) L(P 134C-3 IMPLEMENTING PROCEDURE FOR FIRE: Cl 9/61 C2 FIRE OFFICER #1 (CGGNIZANT MAINTENANCE FCREMAN) 136C-4 IMPLEMENTING PRCCEDURE FOR FIRE: 01 9/61 02 LZP FIRE BRIGADE IMPLEMENTING PROCEDURE F1R FIRE: Cl d/bl C2 LLP 1340-5 FIRE COMPANY NO. 1 (MAINTENANCE ( PERSONNEL) LZP 13 .> C - 1 PROTECTIVE MEASURES FCR ON-SITE C3 7/81 C2 l PERSONNEL L40 L3oG-2 USE OF POTASSIUM IOCICE (KI) AS A Ol l!D Ga TH(RCIO 3 LOCKING AGENT 1300-4 RACIATION PROTdCTION PRACTICES CURING CO 11/61 C3 ELi? ACCIDENT CONDITIor.S
g 4B E LZP 1330-33 ISOTOPIC ANALYSIS OF LIQUID SAMPLES USING AAIS 00 6/82 SOFTWARE WITH PARAPS HARDWARE LZP-1330-34 ISOTOPIC ANALYSIS OF NOBLE CAS SAMPLES USING 00 6/82 AAIS SOFTWARE AND PARAPS HARDWARE LZP-1330-35 ISOTOPIC ANALYSIS OF IODINE SAMPLES USING AAIS 00 6/82 SOFTWARE AND PARAPS HARDWARE LZP-1330-36 ISOTOPIC ANALYSIS OF PARTICULATE SAMPLES USING 00 6/82 AAIS SOFTWARE WITH PARAPS HARDWARE E i E E I E E E i E E E
,a 5/15/s2 LZP INDEX PAGE 5
, PkUC. NO. TITL'E REV. REV C AT E c I S A f:TT 1370-1 LP RESCUE C0 10/80 C2 22 137C-2 PERSONNEL INJURIES 09- Il[IA 02 LZP 137C-3 FIRST AID, DECONTAMINATION AND CC 10/d0 02 EVACUATION OF EXPOSED AN3/CR l B CONTAMINATED CASUALTIES L3 1390-1 CONTROL OF OIL SPILLS OI lAfl2- 02 LP 142C-1 ROLE AND STAFFING OF THE ON-SITE T5C C1 11/80 02 4P 1*30-1 ROLE AND STAFFING OF THE ON-SITE CSC C2 */dl C2 LIP 1*4C-1 ON-SITE GSEP COMMUNICATIONS SYSTEMS D3 12/73 02 LP 1450-1 CELETED Cl 7/81 02 LZP 1*50-2 DELETED Cl 7/81 01 Z3 151C-1 GSEP CPERATIONAL READINESS OC 10/80 01 ZP 152C-1 TRAINING REQUIREMENTS CO 10/d0 02 M4P 153C-1 EXERCISES AND ORILLS 01 Slf! 02 i 15 s C - 1 FIRST AID FACILITIES MONTHLY CA [J.ffA 02 l Ro SURVEILLANCE LLs 1550-2 ENVIRONS SAPPLING SUPPLIES INVENTCRY 03 la,fea C1 - l IP 155C-3 OECONTAMINATION FACILITIES MONTHLY Cl 5/81 02 SURVEILLANCE iP 155C-4 ST. MARY'S HOSPITAL HEALTH PHYSICS 00 [ O [80 C2 SUPPLIES QUARTERLY SURVEILLANCE kB LP 1530-5 TECHNICAL SUPPORT CENTER MONTHLY O2 01 SURVEILLANCE LP 155C-6 QPERATICN AL SUPPORT CE 4TER QUARTERLY 02, L/83 Ci SURVEILLANCE LIP 155 C -7 EM ER GEt4CY OPERATIONS FACILITY O.2, II!E b 01
.10NTHL Y SURVEILLANCE LLP 15 5 C - 8 NUCLEAR ACCIDENT RlPORTING SYSTEM C2 7/81 22 (NARS) MONTHLY SURVEILLANCE ZP if5C-9 SPECIAL TLD QUARTERLY SURVEILLANCE C2 11/ol ;3 ZP 1550-1C ENVIRONMENTAL SURVEILLANCE STATIONS CC 7/81 ;;
P 1550-11
- GEE A'TT A C H LZo lelC-1 DECOVERY AND RE-ENTRY PLANS CO 10/dC 51
E sa LZ P Irid Ex E C.o AFT. Posr-acc.ioe.ar sameuce oc 9f,. -
! LJ-P 1 sso -t t SCUI PmEMT TMoSMTort.Y E
I E E I E E E lE l E 'E E E l 5
. . .. ?~ - . - - . - - - - - - - - - - - - - . - - - - - - - - - - - - = -
LZP INDEX PAGE 6 5/15/82 PROC. NO. TITLE AEV. REV CATE CIS4ETT E LIP 17CC-1 GSEP STATION GROUP CIRECTORY 05 l[g3 at ZP 1700-2 STATION EMPLOYEE LIST 03 ja./ta, 01 ZP 1700-3 STATION PHONE LIST 03 3 1/83 E E E B 5. l l5 . 1E !E I
- E
!E lE I
I E LZP-ll10-1 E RaviSion ', March 2, 1963 1 STATION DIRECTOR (ACTING STATION DIRECTOR) IMPLEMENTING PROCECURE A. _ PURPOSE E The purpose of this procedure i s to outl ine the metnod used to implement tne Station Director's duties. E B. REFEPENCES
- 1. Generating Stations Emergency Plan (GSEP).
- 2. LZP 1200-1, " Classification of GSEP Concitions."
- 3. LZP 1200-2, "Classi fication of a Noole Gas Release."
- 4. LZP 1200-3, "Classi fication of an Icoine Release."
- 5. LZP 1200-4, " Classification of a Liquid Reiease."
- 6. LZP 1310-1, " Notifications."
- 7. LZP 1320-1, " Augmentation of Plant Staffing."
- 8. LZP 1440-1, "On-Site GSEP Communication System."
- 9. LZP 17C0-2, " Station Employee List."
- 10. LZP 1700-1, "GSEP Station Group Directory."
- 11. LAP 900-14, " Fire Protection Program."
- 12. t. Z P 1360-1, " Protective Measures for On-site Personnel."
- 13. OSNRC Audit Report 50-373/81-14 ana 5C-374/81-09 (AIR l-81-317).
- 14. LXP 20C-1, " Threat Response, AttaCnment A BomD Tnreat I Action."
C. PREREQUISITES
- 1. None.
I E
E__._- a LZP-lllC-1 E Revision 4 Marcn 2, 1983 D. PRECAUTIONS
- 1. None.
E. LIMITATIONS AND ACTIONS
- 1. Station Director's responsioilities.
- a. SUPERVISE and DIRECT the GSEP Station Group in organizing and coordinating on-site emergency I ef forts and preparedness (as well as directing all other plant activities).
- o. KEEP the GSEP Command Center Director fully informed of the status of the emergency and the measures oeing taken to deal with the emergency.
I
- c. Establish agreements required oy GSEP Section 8.1.3 for the services specified in GSEP Section E 4.6 and LaSalle Annex Section 4.2 unlass anotner Director has oeen assigned the responsioility of obtaining this agreement.
- 2. Initial nutification by:
- a. Shift Supervisor.
D. Senior Nuclear Station Operator.
- c. Activation Phone List (See Reference 7).
- 3. The Acting Station Director shall perform the duties of the Station Director until ne has been properly I rel i eved of his GSEP duties oy the Station Director or nis al ternate. This may oe accomplisned oy telephone from the Tecnnical Support Center.
lI l l
- 4. The Acting Station Director cannot del egate to eny individual the respons ioil i ty of recommencing protecti ve actions to of f-si te agencies.
- 5. The Station Director can del egate the transmiss ion
!g of the recorrmendeo acti ons to off-site agencies, 3 out he alone must determine what actions snould oe recommended. .I
i E LZP-il10-1 E Revision 4 Marcn 2, 1983
F. PROCEDURE
- 1. FULFILL responsibilities of Station Director. 55EP E Station Director (Acting Station Directcr) Actions (Attachment A) may be used as a guide tc implement duties.
- 2. In tne event of a fire, REFER also to GSEP Station Director Actions: Fire Emergency ( Attachtrent o).
G. CHECKLISTS
- t. None.
H. TECHNIC AL SPECTFICATION REFERB G,ES E
- 1. None.
I E E l E E l E 15 I lI
E LZP-il10-1 E Revision 4 March 2, 1983 ATTACHMENT A GSEP STATION DIRECTOR E (ACTING STATION DIRECTOR) ACTIONS
$5 Thi s cneckl i st is providad sol el y for the convenience of the Station Director. It is not necessary to follow this checklist step oy step. Its completion E is not required and its use is determined oy tne Station Director.
E OBTAIN information as required from: 1.
- a. Shift Engineer.
D. Rad / Chem Department.
- 2. CATEGORIZE incident (See LZP 1200-l, " Classification of GSEP Conditions"; LZP 1200-2, " Classification of a NoDie Gas Release"; LZP 1200-3, " Classification of an Iodine Release"; and LZP 1200-4, " Classification I of a Liquid Release"):
- a. Transportation Accident.
D. Unusual Event.
- c. Alert.
- d. Site Emergency.
- e. General Emergency.
- 3. PERFORM the following actions.
- a. For a TRANSPORTATION ACCIDENT condition.
- 1) DECLARE Transportation Acciount condition.
- 2) COMPLETE appropriate sections of the NARS l
form.
- 3) NOTIFY System Power Supply Load Dispatcner.
I E
E E LZP-ll10-1 E Revision 4 March 2, 1983 5
- 4) ACTIVATE GSEP Station Group as ceemed necessary (Sae LZP 1320-1, " Augmentation of Plant Staffing").
a) GSEP Pagers during normal working hours. c) LZP 1320-l Attachment B curing 0FF-hours.
- 5) DISPATCH personnel for evaluation, if deemed necessary.
- 6) DIRECT tne Rac/ Chem Technicians (RCT's) to take surveys or perform sanple collections as deemed necassary (See Attacnnent O for guidance in prioritizing tne collection I of samples).
7), NOTIFY the NRC Regicn III anc NRC Operations Center, Bethesda, Maryl anc. (See LZP 1310-1, " Notifications" and LZP 1490-1,
- "On-Site GSEP Communication System").
- o. For an UNUSUAL EVENT concition.
- 1) DECLARE an Unusual Event condition.
- 2) COMPLETE appropriate sections of the NARS form.
- 3) NGTIFY System Power Supply Load 3ispatchar.
- 4) ACTIVATE GSEP Station Group as ceemed E appropriate (See LZP 1320-1, " Augmentation of P1 ant Staffing").
- 5) DIRECT the Rad / Chem Technicians (RCT's) to take surveys or perform sample collections as deemed necessary (See Attachment O for guidance in prioritizing tne collection of samples).
- 6) NOTIFY the NRC Regicn III and NRC Operations Center, Bethesda, Maryland. (See LZP I
1310-1, "Notificaticns" ar.d LZP 1440-1, "On-Site GSEP Communication System").
M i i LZP-1110-1 Revision 4 Marcn 2, 1983
- c. For an ALERT conoition.
- 1) DECLARE Alert Conditions.
- 2) COMPLETE appropriate sections of tne NARS form.
- 3) NOTIFY System Po.er Supply Load Dispatcner.
- 4) ACTIVATE tnose parts of the GSEP Station Group neeced to meet the emergency (See LZP 1320-1, " Augmentation of Plant l Staffing").
- 5) ACTIVATE tne on-site Technical Support Center (TSC) and the on-site Cperational I Support Center (OSC).
NOTE The Station Director, not the Acting Station Director, should report to, and assume commano of, tne Technical Support Center (TSC) upon its activation. l 6) DIRECT the Rad /Cnem Technicians (RCT's) to take surveys or parform sanpre collections 3 as oeemed necessary (See Atttachment O 3 for guidance in prioritizing the collection l of samples). l
- 7) NOTIFY the NRC Regica III and NRC Operations Center, Bethesca, Maryland. (Se6 LZP 1310-1, "Notificatiens" and LZP 14,0-1, R "On-Site GSEP Coms.anication System").
- d. For a SITE EMERGEwCY condition.
- 1) DECL ARE Si te E,nergency condition.
1
- 2) COMPLETE appropriate sections of the NARS E form.
- 3) NOTIFY System Power Supply Load Dispatcher.
- 4) NCTIFY the f,RC Regicn III and NRC Operations Center, Bethesda, Marylano. (See LZP 1310-1, " Notifications" and LZP 194C-1, R "On-Site GSEP Communication System").
I - - -
II LZP-1110-1 Revision
- E Marcn 2, 7
1983 I
- 5) DIRECT the Rad / Chem Technicians (RCT's) to take surveys or perform sanple collections as deemeo necessary (See AttaCnnent D for
- guidance in prioritizing the collection of samples).
- 6) ACTIVATE tne GSEP Station Group within oO minutes (See LZP 1320-1, " Augmentation of Plant Staffing").
- 7) ACTIVATE the on-si te Technical Support Canter (TSC) and the On-Site Cperational l Support Center (OSC) within 6C minutes.
fi9.T,g The Station Di rector, not the Acting Station Director, shoula report to, and assume commano of, tne Tecnnical lI Support Center (TSC) upon its activation.
- 8) DISPATCH personnel for environs monitoring if required (witnin 60 minutes).
- 9) CALL IN additional personnel as necessary (within 60 minutes).
I
- 10) EVACUATE all non-essential perscnnel for Site ana General Emergency conditions.
I a) Site evacuation plannec - Security l Director consult with Rac/ Chem Director ! to taKO actions to relCCate personnel in accordance with LZP 1360-1,
" Protective Measures for On-Site Personnel ," beginning witn step F.3.
- e. For a GENERAL EMERGENCY condition.
- 1) DECLARE a General Emergency ccncition.
- 2) COMPLETE the appropriate section of the NARS form.
- 3) NCTIFY System Power Supply Load Dispatcher.
- 4) NCTIFY the Illinois ESDA and LaSalle County Sheriff Department (See LLP 1310-1,
" Notifications") of the emergency situation and ma<e recommencaticos consistent with 5
5 I . LZP-1110-1 Revision 4 E Maren 2, 1983 8 GSEP Taoles 6.3-1, 6.3-2, and 6.3-3 (Attachment C to this procecure).
- 5) NOTIFY the NRC Regicn III and NRC Operations Center. Bethesda, Maryland. (See LZP 1310-1, " Notifications" and LZP 14*C-1, "On-Site GSED Communication System.")
- 6) DIRECT the Rad /Cnem Tecnnicians (RCT's) to take surveys or perform sanple collections as deemed necessary (See Attacnment D for I guidance in prioritizing the collection of samples).
- 7) ACTIVATE tne GSEP Station Group witnin 60 minutes (See LIP 1320-1, "Augrentation of Plant Staffing").
- 8) ACTIV ATE the on-si te Tecnnical Support Center (TSC) and tne on-site Cperational Support Center (OSC) witnin 6C a.inutes.
NOTE The Station Director, not the Acting Station Director, should report to, and assume command of, tne Tecnnical Support Center (TSC) upon its activation. E 9) DISPATCH personnel for environs monitoring if required (witnin 60 minutes).
- 10) CALL IN additional personnel as necessary (within oO minutes).
- 11) PROVIDE plant status upoates to tne plant personnel via tne P.A. system and to tne State and local authorities until tnese authorities can ce informed oy the Corporate 5 Command Center Director (See LLP 131C-1,
" Notifications" and LZP 144C-1, "On-Site GSEP Communicati on System") .
- 12) EVACUATE all non-essential perscnnel for Site and General Emergency conditions.
a) Site evacuation p1anned - Security Director consult with Rac/ Chem Director to take actions to relocate persconel in accoroence nitn LLP 13oC-1, I 5
E E ' LZP-lll3-1 Revision
- E March 2, 1983 9
" Protective Measure for Cn-Site Personnel," oeginning witn step F.3.
t l
- 4. NOTIFY the f ollowing and complete the appropriate sections of the NARS form as necessary:
- a. Command Center Director; the Commard Center I Director is initially contacted oy the System Power Supply Load Dispatcner. Unless requested by the Command Center Director, no furtner notification is required.
- o. Local support agencies, including embulance service, as required in crder to expedite tneir I response to the emergency (See LZP 1700-1, "GSEP Station Group Cirectory").
- c. LaSalle County Sheriff during tne following type GSEP events (See LZP 1310-1, "Nctifications")
in order to keep local authorities alerted:
- 1) Scmb Threat.
- 2) Fire.
- 3) F1ood.
- 4) Civil Disturoance.
- 5. TSC ACTIVATION.
- a. Verify the following TSC personnel requirements as specified in' Table I cf LZP 132C-1 are met.
NOTE NumDers shown are for the SITE and GENERAL EMERGENCY. Refer to Taole I of LZP 1320-1 to determine TSC I requirements for the UNOSUAL EVENT cr ALERT condition.
- 1) STATION DIRECTOR (1).
- 2) OPERATIONS DIRECTOR (1).
- 3) MAINTENANCE DIRECTOR (1).
I E
f' __ E
-5 .
LZP-1110-1 Revision 4 March 2, 1963 10
- 4) TECHNICAL DIRECTOR (1).
- 5) ACMINISTRATIVE DIRECTOR (1).
- 6) STORES DIRECTOR (1).
- 7) RAD / CHEM DIRECTOR (1).
l 8) SECURITY DIRECTOR (1). ,
- 9) ENVIRONS DIRECTOR (1).
l o. Establish on going communications, as deemec l necessary, oetween the following locations:
- 1) TSC/ CONTROL ROOM.
- 2) TSC/NRC.
- 3) TSC/CCC f. EOF.
- 4) CONTROL ROOM /OSC.
- c. Notify the Shift Engineer:
- 1) When TSC is activated and is ready to assume respons ioil ity for off-site l communications.
- 2) When the Station Director assumes commano (formal statement of turnover).
- d. Note the name of the person in charge at tne OSC ano tne time the OSC is activatec.
E 1) Name of person in charge __ _ _ ____
- 2) Time activatec _ _ _
NOTE TSC and OSC must ce activated .vithin 60 minutes for SITE or GENERAL EMERGENCY.
- e. BRIEF TSC Group Di ractors of pl ant status.
- f. Verify that all applicaole actions ano i notifications of nis attacnaent are compl eted.
E
l l E. i LZP-il10-1 l E W aevision
- March Z, 1983 11
- 6. PROVIDE the Command Center Director and Nuclear Regulatory Commission infcrmation as to the status of the plant as determined by the staticn staff.
l g Ig 7. In case of a hazardous material incident, incluaing l a radioactivity i nc i dent , REQUEST support personnel from the Command Center Director to assist in I performing environmental surveys and PRCVIDE otner technical assistance curing the emergency as required.
- 8. IMPLEMENT emergency and recovery efforts as directec by the Command Center Director.
- 9. ASSIGN duties as manpcder becomes availaole.
- 10. REQUEST, through the Command Center, acci tional l 3 materials and moolle equipment from the Division 5 cirector as necessary to perform oecontamination, repair, and restoration work.
- 11. DIRECT the Station Training staff to prcvide training E in direct support of recovery efforts.
- 12. Acti on s requ i red-Compl eted as necessary.
- a. Personnel Accounti ng - contact Security Director.
- 1) Personnel accounted for or a sserrol ed.
_= l
- 2) Personnel missing (list).
E
- o. Injured personnel - contact Operations Director.
- 1) Rad / Chem notifiad for first aic/ survey and decontamination.
E -- - 5
r l
- l. II LZP-il10-1 Revision 4 Marcn 2. 1983 12
- 2) AmDulance arrangeo.
- 3) Hospital arranged.
- 4) Command Center notified.
NAME _ HOSPITAL,_ _ _ _ _ AMBULANCE _ __ __ l
- c. Plant Access - Contact Security Director (Security Administr3 tor).
l
- 1) Gate House secured.
a) Locked oy guard. o) Open to allow cff-site access ano notified to di rect of f-site assi stance.
- d. Contact Industrial Relations regarcing injuries (After incident is under contrc1).
- e. Recovery.
- 1) Determine extent of contamination.
a) Gn-s i te - contact Raa/ Chem Director. o) Of f-s i te - contact Off-site Environs Director. Il E
E 5 ' i LLP-illC-1 Revision
- I Marcn 2, 1983 13
- 2) Protecti ve .neasures set for personnel.
- 3) Oose management set.
- 4) Unit status se t and stable - contact Operations Director.
- 5) Damage estimateo.
- 6) Development of specific recovery plan.
- 13. Maintain a record of the GSEP related activities.
5 E E lE . 5 E E E E E
I E LZP-il10-1 Revision 4 Marcn 2, 1983 L4 E ATTACHMENT S l GSEP STATION DIRECTOR E (ACTING STATION OIRECTOR) ACTIONS: FIRE , 1. COMPLETE Attacnment A of tnis procecure as appropriate. inclucing:
- a. CATEGORIZE i nc i den t ano implement applicaole GSEP program.
- o. NOTIFY proper responsiole personnel as appropriate:
- 1) Station Director (to oe notifiec oy acting Station Director if Station Director is not on-site).
- 2) Pl an t Security. .
- 3) Fi re Marshall .
- 4) Others as requirec.
- 2. The Shift Engineer will coordinate tne cverall fire-fighting response as follows:
- a. SOUND the fi re alarm and announce fire 1ocation over station P.A. system.
- o. RECUEST the status of tne Fire drigace ana Fire E Company No. I as they are assemolec.
- c. NOTIFY Fire Officer No. 1 if the Fire Brigaae E needs assistance from Fire Company Nc. 1.
- d. NOTIFY Fire Company No. 2 (Off-Site Fire Deparment) when assistance may ce requirea (See I Reference 10, LZP 1700-1, "GSEP Station Group Cirectory" for phone 1istings): Supply Fire Company No. 2 witn as mucn pertinent infcrmation concerning the fire as necessary fcr the ir e f f i c i eret response.
- e. KEEP the Fire Marsnal1 informea of the situation.
- f. Make evaluation as to tne necessity for unit shutdown.
E
B ' LZP 1110-1 Revision 4 March 2, 1983 i Page 15 ATTACHMENT C GSEP GUIDELINES FCR RECCMMENDED CFFSITE PRCTICTIVE ACTIONS FCR GASECUS PLUME EXPCSURE CCNDITION RECCMMENDED ACTICN
- 1. Unusual 2 vent o Protective action recommendations g g re Alert late directly to these emergency classes Site Emergency themselves, but to the projected offsita doses. Refer to Items #3 and #4 below.
- 2. General Emergency o Because of the serious nature of this emer-gency class, recommend that the public be notified of the emergency situation.
Recommend heltering for a two (2) mile radius around the nuclear station, as a i siinimum. Make subsequent recommendations in accordance with offsite dose considera-
' tions given below.
- 3. Doses to the offsite o Recommend a two (2)~ mile radius evacuation.
public have been pro-- jocted to be: o Roc-ad seeising shelter in the three-doms-I wind 2240 standarti sectors to a distance
- -- Whole bodyr 1 to '5 rem; - appropriate i:o the 'do'se p'rojected, normally to five '(5) or' ten"(10) miles.
-Thyroid: 5 to 25 rom. o R contedllin' g. access 'ii;o affected
~arenar.
- 4. Doses to the offsite a Recosmienci a two (2) mile fadiw-evacuation.
public 'haveleen pro--
~
jected to bet o Recommend evacuation of the three downwind
~2 f(* s+==4med sectors to a distance appropr iatt.
I LWhole body: greater than to'the ' dose prdfocted, 'ncmaally to five (5) 5'res; or ten (10) miles. If the wind dirict'on i is g if the start of the variable,, o(f the duration of the release releise in I delayed, or i -
-Thyteid: great 5r'~than
~
is 'long, f. tie' niinbes of eiacuated sectErs
~
25 ren. say increase or possibly extend to a com-plate circle. o If a timely evacuation is not ' feasible (i.e.,
'ths' time available"before cloud arrival is sh5rt compared with the required mobilization,
~
warning and transit time for evacuation), then recommend sheltering for affedted areas I (instead of evacuation). o Recommend controlling access to affected areas. u, .*n a
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Revision is
. March 2, 1983 ATTACHHENT C (Cont.) Page 17 SUHHARY OF POSSIBLE OFF91TE PROTECTIVE ACTIONS 1 TO BE RECOHHENDED OR IMPLEMENTED DURING AN DfERGENCY+
ACCIDENT FIIASE EXPOSURE FATHWAY EKAMPLES OF ACTION TO BE RECOHHENDED Inhalation of gases, Evacuation, shelter, access control, respiratory protection. I radiotodine, or particulate prophylaxis (thyroid protection) EHERGENCY PHASE (0.5 to 30 hours)* Direct whole body exposure Evacuation, shelter, access control ingestion of milk Take cows off pasture, prevent cows from drinking surface water, discard contaminated milk, or divert to stored I l products such as cheese
- Ingestion of fruits and Wash all produce, or impound produce, delay harvest until INTERHEDIATE ' vegetables approved, substitute uncontaminated produce PHASE Ingestion of water Cut off contaminated supplies, substitute from other sources.
. filter, demineralize (30 hours to 30 days)* Whole body exposure and Relocation, decontamination, access control inhalation Ingestion of food and water Decontamination, condemnation, or destruction of food; deep I contaminated from the soit plowing, condemnation, or alternate use of land 3
either by resuspension or i LONG TERM uptake through roots FilASE Whole body exposure from Relocation, access controle decontamination, fining of (over 30 days)* deposition material gr contamination, deep plowing inhalation of resuspended l material I Emergency phase - Time period of me, lor release and subseqdent plume exposure. 2 Intermediate phase - Time period of moderate continuous releases with plume exposure and contamination of environment. 3 Long Term Phase - Recovery period.
*" Typical" Post-necident time periods, Reference ilSEPA "Hanual of Protective Action Cuides and Protective Actions for Nuclear Incidents " 1975.
E . g
r
- L2P-1110-1 Revision 4 harch 2, 1983 -
18 (Final) ATTACHMENT 0 E
- 1. When Control Room Indicators are inoperable or offscale obtain samples as needed so that the true source term E for any potential release can be determined. Obtain needed samples as expeditously as possible in accordance with priorities delincated in the following:
E . RELEASE Rx. COOLANT ORYWELL VENT STACK / POTENTIAL SBGT None 1 2 3 iMMlNENT. I 1 3 OCCURING 3 1 1 VERIFY STOPPED 3 2 1 E E E E 'E
LZP-1310-1 Revision 3 , March 2, 1983 1 - NOTIFICATIONS A. PURDOSE The purpose of this procedure is to outl ine the various notification requirements for GSEP response conditions.
- 3. REFERENCES
- 1. IE Bulletin No. 79-066.
- 2. IE Bulletin No. 79-08.
- 3. IE Bul1etin No. 80-15.
- 4. IE Information Notice 8C-06.
- 5. Supplement to IE Infarmation Notice 80-C6, cateo July 29, 1980.
- 6. 10CFR Part 50 Section 50.72, Notificaticn of Significant Events.
10CFR Part 20 Section 20 403, Notification of I 7. Incidents.
- 8. Nuclear Stations Division Manager's Directive No.
I 014.
- 9. Generating Stations Emergency Plan, Section 6.0.
- 10. Regulatory Guide 1.16.
ll. Technical Specification, Section 6 6.
- 12. LZP 1110-1, " Station Director Implea.enting Procedure."
- 13. LZP 1210-1, " Hazardous Material Incidents Reporting."
14 LZP 1380-1, " Control of Gil Spills."
- 15. Environmental Emergency Plan Inplementing Proceoures.
- 16. 10 CFR Part 70 Section 70.52.
- 17. 10 CFR Part 73 Section 73.71
11 11 LZP-1310-1 E Revision 3 March 2, 1983 2
- 18. LXP 100, " Security Contingency Events (General)."
C. PREREQUISITES
- 1. None.
D. _PR EC AUTICNS
- 1. All infcrmation given over the ENS pncne will oe E designated as unofficial and preliminary until it is reviewed and finalized by tne Shift Engineer, the Station Director or Command Center Cesk.
E. LIMITATIONS AN_O _ ACTIONS
- 1. Whenever tne NRC phone (ENS) is used, nctification E of the General Office Nuclear Outy Officer is required. Normall y, the station will infcrm tne Power Supply Load Dispatcher to make tnis requirec B notification. However if shift supervisor receivec instructions (via the night orders or direct communication with the specific Outy Officer) to taxe the responsibility for direct notification of l I the Outy Officer, they must then inform the loao aispatcher that the station will make the required notification.
F. PROCEDURE
- 1. When initial notification of an emergency is made E to State or local authorities the State of Illinois Nuclear Accident Report Form ( Attach:nant C) is to oe used to compile tne information needed for tne I report with periodic upaates made whenever possiole if plant or atmospheric conaitions cnange s i gn i f i cantl y. Per LC CFR 50 App E. C.3, state and local authorities must ce notifisc witnin 15 min.
I of aeclaring a General Emergency.
- 2. A requirement to notify the NRC witnin cne (1) hour I applies to the following events wnicn srould oe reported on the Control Room phone:
- a. In accordance witn References 1 anc 2, one hour I notifications snall be made wnen tre reactor is not in a controlled or expected concition wnile operating or shutdown. This conoition l I is interpreted to mean:
II
I l l . L2P-1310-1 I Revision 3 March 2, 1983 3
- 1) A LGCA or s i .n i l a r failure of tne reactor coolant system wnich resul ts in an I uncentroll ed increase in containment raciation level s, pressures, cr temperatures or unexpected unccntrolled release or radioactivity off-site.
- 2) when the reactor coolant system pressures and temperatures are not uncer control or I following expected trenas within a reasonaole amount of time such as 15 minutes after a transient.
- b. In accordance with Reference 4, 5, 6, ano 9, notification shall oe mace as soon as possiole and, in all cases, within one nour oy telepnone I for the events listed celow. For tne folloaing events, also estaolisn and maintain an o2gn continuou2 communications enannel witn the NRC I operations Csater and clcso tnis channel anly when notified by the NRC:
Any event requiring initiation cr the 1) I - licensee's emergency plan or any section of that plan as descrioed celcw: a) See Attacnment A (GSEP Taole LA 5-1, I LSCS Emergency Action Levels). b) Fires are reportaole if an off-site I fire department is notifiec to respono or assist, or more than ten (10) minutes is requirec from the ti.r.e of discovery to control or extinguisn I the fire.
- 2) The exceeaing of any Tecnnical Specification I Safety Limit.
- 3) Any act that tnreatens the safety of tne I nuclear power plant or site personnel, or the security of special nuclear material.
This includes civil cistaroances or acts of sacotage or attempted sanotage. (See LXP 100 for additional information.)
- c. In accorcance witn Reference 4, 5, 6, 7, and 8, notification snall os made as scon as possicle
B I L4P-1310-1 I Revision 3 Marcn 2, 4 1983 and in all cases dithin ene hour oy telepnone for tne following events:
- 1) Any event requiring initiation cf shutdown of the nuclear power plant in accoraance wi th Techn ical Specification Limiting Conditions for Operation.
- 2) Personnel error or procedural inadequacy I ahich, during normal operations, anticipatea operational occurrences, or accident conditions, prevents or could prevent, oy i tsel f, the fulfillment of tne safety I function of those structures, systems, and components important to safety tnat are needed to (i) shutdown the reactor safel y anc maintain it in a safe shutcown I condition, or (ii) remove residual heat following reactor shutdown, or (iii) limit the release of racioactive material to I
i acceptable level s or reduce the potential for such release. I 3) Any event resulting in manual or automatic actuation of Engineered Safety Features, including the Reactor Protection System. Notification is required f or unpl anned I unit or reactor trips resulting from valid Reactor Protection System (RPS) actuation. Excluced from noti fication are: a) Partial actuation of safeguards or RPS (i.e. -half scrams). b) Actuation cf ESF inclucing tne RPS wnich result from ano are part of ' tne planned sequence curing surveillance testing or startup testing.
- 4) An y accidental, unplanned, or uncontrolleo I radioactive release (normal or expected releases from maintenance or cther operational activities are not includea).
Gaseous or liquid releases require notification if: a) A minor release which escapes tne plant, is cetectacle either tnrough sampling or ooservation cf a (recording)
E E
~
LZP-1310-1 E Revision 3 Marcn 2, 1983 5 monitor, or reaches a moritor alarm setpoint, anc is associatea witn an unplannea or accidental event. b) The release exceeds a Tecnnical Specification Limiting Ccnoition for operation. c) Excludea from notificaticn are increases in ef fluent monitor from E sampling, inventory changes in rentea tanks or equipment, and increases attributable to operating processes wnerein radioactive water noves through systems with mincr leakage sucn tnat activity will ce releassa to vented ouildings. (i.e. - start E of pumps with controlled leakage seals)
- 5) Any fatality or serious injury cCcurring on the site and requiring transport to an off-site medical facility for treatment.
Serious injury is consicered to ce any E injury that in the juagement cf the licensee representative will require acmission of the injured individual to a hcspital for treatment or ooservation for an extenaea period of time (greater than 48 hours). Injuries that only require treatment ana/or medical coservation at a hospital or off-I site medical f acil ity, out ao not meet the conditions satisfied accve, are not required to oe reported. a) Notification should also oe maae for less severe injuries if contamination complications also exist or if an ambulance service is useo to transport tne victim to an off-site mecical facility.
- 6) Any serious personnel radioactive contamination requiring extensive on-site decontamination or outside assistance.
I
- 7) Any incident i nvol v i ng cy-procuct, source, or special nuclear material whicn, in 1
l l LLP-L310-1 Revision 3 Marcn 2, 1983 b l accordance with 10CFR Section 2C.403, may have caused or threatens to cause: a) Exposure of the whole cocy of any indiviaual to 25 rems or more of radiation; exposure of the skin of tne wnole occy of any incivicual of 150 rems or more of raciation; or exposure of the feet, ankles, hancs or forearms of any individual to 375 rems or more of radiation; or o) The release of radioactive material in concentraticns wnich, if averaged over a period of 24 hours, woulo exceed 5,000 times the limits specifiea for sucn material s in 10CFR 20 Appenaix
- 8. Taole II (see Attachment B); or c) The loss of one working week or more of the operation of any facilities affected; or d) Damage to property in excess of
$200,000 00.
- 8) Strikes of operating employees or security guards, or honoring of picket lines Oy these empl oyees.
- o. In accordance witn Reference 3, notification E shall be made within one hour, oy commercial telephone or relayed message, to the NRC Operations Center, when cne or more extensions of the Emergency Notification System (ENS) is found to be i noperaol e for any reason. (See precaution 01)
- 3. Notification of reportaole Oil or Hazardous Suostances.
- a. Oil spills shall ce reported as required per Reference 14.
D. Hazardous materi al s snall oe repcrtec in accordance with Reference 13.
- 4. A requirement to notify the NRC within twenty-four (24) hours applies to the following events wnich should be reportea on the Control Rcom pncne. Inese
11~ LZP-1310-1 Revision 3 March 2, 1983 . 7 l events'should be confirmed by telegraph, railgram. 3 or facsimile transmission oy no later tran the fi rst working aay following the event, witn a written I followup report within two weexs.
- a. In accoraance with Reference 7, any incicant involving licensed material which may have causes or threatens to cause:
- 1) Exposure of the whole oody of any individual E to 5 rems of more or radiation; exposure of the skin of the wnole Docy of any individual to 30 rems or more of raciation; or exposure of tne feet, ankles, nands, or forearms to 75 rems or more of raciation; or
- 2) The release of racioactive material in concentration which, if averageo over a period of 24 hours, would exceed 500 times E the limits specified for sucn materials in 10CFR2C Appendix B, Toole II (see l Attachment B); or
- 3) A loss of one day or more of tne operation of any facilities affectea; or
- 4) Damage to property in excess cf 52,000.00.
D. In accordance witn Reference 10, nctification shall be mace as expeditiously as possiole, Dut witnin 24 hours by telephone fcr the following events:
- 1) Failure of tne reactor protecticn system or otner systems suoject to limiting safety-system settings to initiate tne requireo protective function by the time I a nonitored parameter reaches the setpoint specifiec as the limiting safety-system setting in tne technical specifications or f ailure to complete the required protective function.
l 2) Errors ciscovered in the transient or l accident analyses or in the methoos usec lg 13 for such anal yses as descr icec in ene safety analyses report or in the bases for the technical specificaticns that nave l I i
LZP-1310-1 Revision 3 Marcn 2, 1983 8 or could have permitted reacter operation in a manner less conservative tran assumeo in the analyses.
- 3) Performance of structures, systems, or components tnat requires remecial action or corrective measures to prevent operaticn in a manner less conservative than tnat assumec in the accicent anal yses in tha safety analyses report or technical specifications cases; or disccvery curing pl ant life of conditions not speci ficall y considereo in tne safety analyses report or tecnnical specifications trat require remecial action or corrective measures to prevent existence or cevelopment of an unsafe condition.
- 5. Accicental criticality requires immediate NRC Regional Office notification (Region III) Dy telephone ano a followup telegram, mailgram or facsimile (Aererence 17).
- 6. As required in Reference 17 and 18, one ncur notification of the NRC Operations Center via the ENS line is required for:
- a. Any event which significantly tnreatens or lessens tne ef fectiveness of a pnysical security system.
- o. The loss, unlawful diversion, tneft, attempted theft or suspected attempted theft of special nuclear material. This event also requires immeciate notification of the NAC Regional Of f ice oy telephone jng f ollonup telegram, mailgram or facsimile notification.
- c. An act of radiological saootage against tne plant or its transportation system.
G. CHECKLISTS
- 1. None.
H. Tgg SPECIFIQTION REFER g @
1
. l 1
LZP-131C-1 Revision 3 Marcn 2, 1963 9 J
- 1. Section 6.6.
i i l I l t ( I I l l f f I l 1 l t l l
ATTACilNElli A I ' LZP 1310-1 Revision 3 LSCS FMERGENCY ACTION LEVELS March 2, 1983 10 SITE a CENERAL UNUSUAL EVENT ALERT EMERGENCY EMERGENCY CONDITION Events in progress Events in progress Events in Events in progress Class Description l or have occurred which or have occurred which progress or have or have occurred which indicated a potential involve and actual or occurred which involve actual or degradation of the potential substantial involve actual imminent substantial 1evel of Safety of degradation of the or likely major core degradation or l level of safety of failures of melting with potential ' the plant. the plant. plant functions for loss of contain-need for pro- ment integrity. tection of the public
- 1) Aircraft Crash Impacted on-site Impacted on-site and Impacted on-site requiring unit shut- and requiring unit or missiles from down due to the shutdown due to phatever source.
implementation of the implementation an ACTION statement of Technical of the Technical Specification Specifications Section 3.0.3.
- 2) Control Room Evacuation is antici- Evacuation is Evacuation pated or required with required and control established control is not from remote shutdown established panel from remote shutdown panel within 15 min.
h I e i
LZP 1310-1 ATJACHMENT A V LSCS EMERGEWCY ACTION LEVELS - rc $ 983 SITE GENERAL ALERT EMERGENCY EMLRGENCY CONDITION UNUSUAL EVENT ,
- 3) Earthquake Equipment activated At a level greater At a level then an Operating greater than a (Activation of at the setpoint level Safe Shutdown seismic monitoring (js 0.Olg) Basis Earthquake (0.1 g horizontal Earthquake with alarm with level verification from 0.066 g vertical) a unit not in the Aux. Electric cold shutdown or refueling Room) *
(Not' spurious or (0.2 g horizontal O.133 g vertical) testing)
- 4) Explosion Causing Onsite. Requiring unit shut- Requiring unit Damage down due to the shutdown due implementation of to the imple-
' ad ACTION statement mentation of of the Technical Technical Specifications Specifications Section 3.0.3.
l Requiring offsite Requiring offsite
- 5) Fire RegJiring offsite assistance and (ongoing as assistance assistance and f detected by, requiring unit requiring unit ;
shutdown due to ; observation or shutdown due to ' alarm, and verified the implementation the implemen-by the Fire brigade) of an ACTION state- tation of Tech-ment of the Tech- nical Specifi-nical Specifications cation 3.0.3. 4 8
L7.P 1310-1 ATJACHMENT A Revision 3 LSCS EMERCENCY ' ACTION LEVELS March 2, 1983 12 SITE GENERAL ALERT EMERGENCY EMERGENCY CONDITION UNUSUAL EVENT ,
- 6) Flood Rupture of cooling 1) Illinois River 1) 1111noin River pond dike affecting, 7 610' MSL > 710' MSL (188 offsite property (88 feet above feet above max max probaMe Gd? probable flood) 2)725 inches of rain 2)> 25 inches of in a 48 hour period rain in a 6 as determined from hour period.
the Natlonal Neather Service f
- 1) Control Rod Drop 1) Pipe Breaks Inside
- 7) FSAR Analyzed (FSAR 15.4.9) Primary Containment Accidents (FSAR 6.2, 6.3, 7.1, NCTE: For Fuel 2) Pipe Breaks Outside 7.3, 8.3, 15.6.5)
Handling Accident Primary Containment 2) Gaseous Radwaste I (FSAR 15.7.4), see (FSAR Appendix C) Adsorber Tank Rupture (FSAR 15.7.1) condition no. 17. t E i. t 9
ATTACHHENT A I7P 1310-1 IECS EMERGdhlCf ACTION LEVELS hfyIj" hg) 13 SITE CENERAL ALERT EMERGENCY EMERGENCY CONDITION UNUSUAL EVENT ,
- 8) Security Threat The following events Security Threat of Imminent loss of Loss of physical increasing severity physical control of control of facility.
as described in the Security plans that persists for facility, more than 60 minutes.
- 1) Obvious attemt.c to salmtage.
4 2) Internal disturbance ! (disturbance which is not short lived or is not a harmless outburst involving one or more indivi-j duals within the protected area). i
- 3) Bomb device dis-covered.
- 4) llostage.
- 5) Civil disturbance (spontaneous col-1ective group gathering which disrupts normal i
operations).
- 6) Armed or forced
- protected area intrusion. '
- 7) Armed or forced i vital area intro-sion.
I! mW mmM M N m amag
ATTAC11 MENT A " LSCS EMERCENC.f ACTI9N LEVEt,S "Vjc"h a 2, @ th SITE GENERAL ALERT EMERGENCY EMERGENCY CONDITION UNUSUAL EVENT ,
- 1) Tornado near 1) Tornado strikes Sustained winds of
- 9) Tornado or Severe > 90 mph (Designed winds being facility. facility experienced a) Control Room Winds)
(Wind r: peed as informed by 2) Sustained winds of indicated in Ioad Dispatcher > 75 mph. Control Room) or b) Informed by Station personnel who have made visual sighting.
- 2) Sustained winds of 7 60 mph.
Incident observed Detected by the Detected by the
- 10) Toxic Gas Chlorine and ,
(Chlorine, near or onsite Chlorine and Ammonia) Ammonia Detection Ammonia Detection System with Control System without Room and Auxiliary Emergency Electric Equipment Filtration System Room Emergency operable . Filtration System operable. Chlorine detected at 5 ppm Ammonia detected at 50 ppm
- 11) I.oss of AC Power Unit shutdown due to Unit shutdown due Loss of all the implementation of to implementation following 4160 VAC Technical Specifi- of Technical Busses for>15 minutes:
cation ACTION Specification 141y (241y), 142y (242y) statement 3.8.1.1. Section 3.0.3 and 143 (243)
I'I'I I3IU~I ATTACHHENT A 3 IECS EMERCENCf ' ACTION LEVEI,S PV I8 I}H 15 SITE GENERAI, ALERT EMERGENCY EMERGENCY CONDITION UNUSUAL EVENT , Unit shutdown due to I,oss of all the
- 12) DC Power Unit shutdown due to implementation of implementation of following 125 VDC Technical Specification Technical Specification Distribution ACTION statement Section 3.0.3 Panels for > 15 minutes 111y(211y),
3.8.2.3
. 112y ( 212y) ,113 (213)
- 1) Loss of all systems Loss of
- 13) Plant Shutdown systems capable Functions capable of main-talning cold shut- of maintaining down, or hot shutdown.
- 2) Failure of the Reactor Protection System instrumen-tation to initiate and complete a SCRAM which brings the reactor suberitical once a limiting Safety system setting, as speci-fled in Technical Specifications Section 2.2.1, has been exceeded.
I
- 14) Other Systems - Unit shutdown due to Unit shutdown due to I j required by any the implementation of implementation of f; Technical Specifi- a Technical Specifi- Technical Speciff-i cation (such as cations ACTION state- cations Section 3.0.3 ECCS, fire pro- ment.
lg' tection nyntems, control room ven-tilation, etc.) U M M M M M M M M M M M M M M My
- ATTAtllHENT A L7.P 1310-1
#' Revision 3 LSCS EMERCENC ACTION LEVERS March 2, 1983 1A SITE GENERAL IJHUSUAI, EVENT AI,ERT EMERGENCY , EMERGENCY CONDITION A.h2.10 2 R/hr 2 R/hr A. >, 4 x 10 A. 22x103 R/hr
- 15) Loss of Fission Primary Contain- Primary Contain-Product Harriers Primary Contain-ment Activity, or ment Activity, or ment Activity, and D. Loss of 1 of the B. I.oss of 2 of the B. Loss of 2 of the following 3 fission following 3 fission following 3 finnion product barriers product barriers product barriers,
- with an imminent loss of the 3rd fission product barrier:
- 1) Cladding: 1) Cladding: 1) Cladding:
grab sample > 300 grab sample > 300 grab sampley 300 ucl/cc equivalent uci/cc equivalent uci/cc equivalent of I-131 of I-131 of I-131 l
- 2) Reactor Coolant Sys: 2) Reactor Coolant Sys: 2) Reactor Coolant Syst
> 1.69 psig dry- > 1.69 psig dry- 7 1.69 psig dry-well pressure and well pressure and well pressure and
< -129 inches <-129 inches < -129 inches Reactor Vessel Level Reactor Vessel Level Reactor Vessel I.evel
- 3) Primary Containment 3) Primary Containment: 3) Primary Containment a)> ,45 psig Contain- al'2 45 psig Contain- a)) 45 psig Contain-ment pressure, or ment pressure, or ment pressure, or b) ? 3400 F drywell b) >3400F drywell b) > 3400F drywell temperature , or temperature, or temperature, or c) 7 2750F wetwell c)> 2750F wetwell c)> 2750F wetwell air temp., or air temp., or air temp., or d)7 2000F wetwell d)> 2000F wetwell d)7 2000 F wetwell water temp. water temp., or water temp., or c) Loss of Primary e) Loss of Primary Containment Containment
- Integrity when intergity when Containment Containment integrity is integrity is required. required.
I.7.P I 310-I AITACHMENT A Revision 3 LSCS EMERCEhCT ACTION LEVEt,S March 2, 1983 j 17 l SITE GENERAL ALERT EMERGENCY , EMERGENCY CONDITION UNUSUAL EVENT f A>50 gpm leakage 1) A> 500 gpm Imminent Core Melt
- 16) Loss Primary 1) ECCS Initiation Icakage increase Coolant (Not spurious) increase in a 4 hour examples: period as indicated in a 4 hour a) Loss of F.W. by monitors
- or period as totalizer, indicated by b) Loss of Con- monitors
- densate
- 2) A Main Steam
- 2) Failure of a Line Break Primary System Outside Con-Safety Valve tainment without isolation (MSIV to close as indicated by closure) as indicated by position in-the following dication.
alarms: MS line area temp flir Main steam line flow high.
- Monitors aret Primary Containment sump flow monitors or air coolers condensate flow rate monitors.
- 17) Fuel llandling Standby gas treatment Standby gas treat-system operable ment system not Accident operable (Report of damage ,
to irradiated fuel assemh11es and fuel pool exhaust Monitor 7100 mR/hr) g
ATTACilHENT A g , LSCS EMERCENCY ACTION LEVELS Harch 2, 1983 18 SITE GENERAL UNUSUAL EVENT ALERT EMERGENCY EMERGENCY CONDITION ,
- 18) Radiation Releases 1) Gaseous Effluents 1) Gaseous Effluents 1) Gaseous Effluents 1) Gaseous Effluents From the Plant 10CFR20 instantaneous >10 times the Effluent monitors Effluent mo nitors release limits 10CFR20 imstantameou detect level cor- detect levels release limits responding to corresponding to (10CFR20.105) are exceeded as measured (10CFR20.105) as 0750 mR/hr ?>l Rem /hr whole measured by the (1.3x107 uCi/sec) body at the site by the vent stack radiation monitor vent stack radia- for 1/2 hour or boundary. This and/or counting tion monitor and/ )*500 mR/hr condition exists or counting equip . (1.3x108 uCl/sec) when equipment.
ment. I for 2 minutes at Q/u) 4.5 x 10 7 the site boundary where (adverse meteor- Q= release rate ology) in uCi/sec u=mean wind speed in sph or 8 Q/u)1x10 where Q= release rate in uct/see u=mean wind speed in meters /sec
- 2) Liquid Effluents 2) Liquid Effluents 2) Liquid Effluents 2) Liquid Effluents Estimated 11guld Estimated 11guld estimated liquid ?'10-6 uC1/mi as release > 4 C1 measured by moni- release >>2000 Cl release ?> 2 x 104 tors
- and/or but $E20,000 C1 ci but:$i 40 Cl** ,
sampled and measured counting equipment counting equipment. or Estimated liquid release ?? 40 Cl
. but:52000 Cl
- Monitors: Radioactive 11guld waste effluent radiation monitors service water effluent monitor l * * >1x10-7pci/ml but $$ 1x10-6 pC1/ml w w
ATTACllHENT A , tzp gjto_t LSCS EMERCENf.f ACTION LEVELS Revision 3 March 2, 1983 19 SITE GENERAL ALERT EMERGENCY EMERGENCY CONDITION UNUSUAL' EVENT
- 19) Personnel Injury Transportation of radioactivity con-taminated injured person to hospital
- 20) llazardous As a direct result of Haterials hazardous materials a person is killed or hospitalized or esti-mated property damage exceeds $50,000.
- 21) Any other cpndi- Warrants increased ,
tions of equiva- awareness on the part lent magnitude to of the state and/or the criteria used local offsite to define the officials accident category , as determined by Station Director.*
- Conditions that may or may not warrant classification under GSEP includet
- a. Incident reporting per 10CFR50.72
- b. Incident reporting per 10CFR20.403 or Illinois Rules and Regulations, Part D .403.
- c. Discharges of oil or hazardous substances into waterways per 33CFR153.
- d. Security conti,ngency events per the Station Security Plan. GSEP emergencies, depending upon The Station Director may, at his discretion, categorize the above situations as seriousness of the situation. (Refer to Section 10.3 of the generic plan for additional information).
i i
'i
1.7.P l 310-1 ATTACHMENT A Harch 2, 1983 20
)
IECS EMERGENCY ACTION LEVELS Transportation Accident , A. A vehicle transporting radioactive materials or non-radioactive hazardous materials from a Commonwealth Edison generating station is involved In a situation in which
- 1. Fire, breakage, or suspected radioactive contamination occurs involving a shipment of radioactive material ort
- 2. As a direct result of hazardous materials, I
(a) A person is killed; or (b) A person receives injuries requiring hospital 12ations or (c) Estimated carrier or other property damage exceeds $50,000.
- in
! n. Any other condition involving hazardous material transportation and equivalent to the criteria Item A. k U U M M M M M M M g g g
.E i
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March 2, 1983 27
. ATIACBMElfr C .
MEs5 AGE IDENTIFICATION DATI I TIME STA f* 'LL1 215 4 CLEAR AC... 46TTEM F0m
- 2. ACC!Otiff CLA55!F1 CAT 10N 3. REETOR umstR (5) l 1. 3 A TRANSPORTATION ACCIDENT ONE (1)
@ DRt30D hSRA10W000 (st! ITEM #18) ~
G s UNU5UAL EVENT @TWO(2)
@OunoCITits h110N @ ALERT @THRE!(3)
D LA SALLI @51TEAREAEMOGENCT @NOTAPPLICA8LE E h3720N h GEERAL EMAGEET TIME Daft
- 4. TIM AS DATE OF INCI0 TNT /tvDT: .
- 5. IEIDENT fMvOLVts:
~
I .
- 6. SITUATION INVOLTts: 7. TYPt OF RELEA51 15 A RA010ACT!Yt GA$tous
@NORELIA5E
@ POTENTIAL (P0551stt) REMA51 h NON.RADIDACTIVE EAsttNS
@ Im1mMT (FRosasu) RELEASE [ RA010ACTIVt UQUID E 0 A RELEASE IS OCCWRINS *@ K3N.RA010 ACTIVE L1331D g A auASE THAT OC==o. wr STOPPa. @ WN.APPuuCu , .
- a. REC m m uoto PRottCTITE ACTIOut:
E, h Ft2 INP0mATION 012.7 (UW50AL [ VENT. ALERT OR TRANSPORTATION ACCIDENT) f h PREPARE FOR POSSIBLE ACTION INv0LVINE tnt PUBLIC. TD INCLUDE WTIFICATICE. (ALDT O IM RE DCT OR TRANSPORTATION ACCIDENT) Ei h WTIFT PUBLIC TO TAK! THE FOLLOWIN PROTECTIVE ACTIONS. (SITE OR GEERAL EMOGDC TRM5PORTATION ACCIDENT.) l
.2!EIII .P.5lEL O N 0 2 MILE RADIUS (GAS [ mis RELIASE) l [ [ 15 MILE 5 FOR THREE (5) ImWNWIW SECTOR 5 (GAsttus REttist) J l @ @ 510 M135 FOR TWRtt (3) 00WNWINO SECTORS (GA510U5 RELIA $t) l h E MILES (TRAN5PORTATION ACCIttWT OR OTHER) l L DISCDNTINut USE OF POTINTIALLY AFFECTD WATER IN '
1 L Meunm PUT CATTu UN STORED FIED IN 00WNWIW SECTORS GJT TO MILL 5. I 9. RELIASE 15:
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@ CDNTIWING . EXPECTED CURATION OR MAGNITUDE .
i l [ Tim!NATED AP'RCI1 Matt CURATION OR MAGNITUCE
- 10. MEIGHT OF $45[0US RELIA 5E 15: GROUNO LEYtk @ ELEVATED 8
l
- 11. WIND SPEG PCTERS PER SECOMO I 2
- MILES PER MOUR l I l 6 NCTE: USE NOT APPLICABLE (N/A) WHERE APPROPRIATI.
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- 13. CURRENT CUT 5!Of TDiptRA19 tut: A . 'F B 'C B 14. vtATHER CouCITipus (RAlu, sucW. SLEET. ETC.):
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- 15. TDetRATURE O!PFEREIEE (AT): A
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E 16. RELEASE DCTICTED ST: hT!5 MAL h Safett Rt3 ULT 5 ARE: E C 1RSTIt3MENTATIC latNTIFICATI E "' A014 E i 17 . ACCIOtJrf RELATIO IRMLits: AW @ T15 @ meter OF IICURits
- 18. A. LOCATItal 0F TRANSPORTAT!tBI ACCIDDIT:
- 8. TTPE OF SMIP43ff (NEW FUEL. SPENT TutL LDs WASTE, ETC.):
l C. TYPE OF VINICLE OR C!alTAINER l
- 0. FG48 0F MAftA1AL S!!IIS SHIPPG ( SCLID. LIQUID. GASE3J5):
E. CICO. PtR5WuutL D15PATotG TO TRAM 1PORTAT10m ACCIDENT 3CENE: A NO 8 Yt1 7 14#ett
- 13. OTHta !W ORMATION:
1 5 23. Mt35AEt REPORTED ST: m VR W uAsesE a&d N R& (OUT5IDE #)
- 21. M.A.A.5. p(15 AGE RECIITED BT rwa m .m eis I 22. MC55 AGE VERIFIED: h4 h Yt3 IF Yts. BT wMG4: .
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