Text

Public Version of Rev 4 to Emergency Plan Implementing Procedure LZP-1170-1, Security Director & Rev 4 to LZP-1310-1, Notifications
	ML20076L261
Person / Time
Site:	LaSalle
Issue date:	07/08/1983
From:	; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20076L250	List: ML20076L252; ML20076L261;
References
	PROC-830708-01, NUDOCS 8309150449
	Download: ML20076L261 (43)
	v • d • e

s 7/C5/d3 LZP INDEA PAGE 1 DRJC. NO. TITLE REv. REV OATE CISAET l_______..__________________________________________________________________________.

iP 100-1 DELETED C3 11/80 C1

_ZP 100-2 DELETED C4 11/8C 01

.Zo ICC-3 DELETED C3 10/80 01

_ZP 200-1 DELETED C2 11/80 01 l LZP 200-2 DELETED C2 11/80 01

.43 2 0-3 DELETED C2 11/80 01 Ltd 200-4 DELETED C3 11/80 01

,20 21C-1 DELETED C2 10/80 01

.4P 300-1 DELETED C4 8/80 Cl

.42 300-2 DELETED C3 11/80 01

_9 31C-1 OELETED C3 11/80 01 LZP 320-1 DELETED C2 10/8C 01 um 3J:-l DELETED Cl 10/80 01 LZP 390-1 DELETED C1 10/80 01 uiP 35C-1 DELETED 02 10/80 01 LLP 36G-1 DELETED 02 10/80 01 LZP 37L-l DELETED 01 10/80 01 LZP 4C0-1 DELETED C2 11/80 01 LZP 4CC-2 DELETED C2 10/8C 01 LZP 400-3 DELETED C1 11/80 01 LZ3 41C-1 DELETED 01 11/80 01 LLD 420-1 DELETED 01 11/80 01 LZP SIC-1 DELETED C2 10/8C 01 LZP 52C-1 OELETED C2 10/ec ut LLP 520-2 DELETED C1 10/8C 01 LZP 52C-3 DELETED Cl 1C/80 01 LZP 530-1 UELETED C1 10/80 Cl 8309150449 830907 PDR ADOCK 05000373 F PDR

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7/00/d3 LZP INDEA PAGE 2

RCC. NO. TITLE REV. REV DATE DISsETT P $30-2 DELETED C2 10/80 01 P 5*C-1 DELETED 01 10/80 01 P 70C-2 DELETED 01 11/80 01 P 710-1 OELETED C2 10/80 01 ZP d1C-1 DELETED C1 10/80 02 P d20-1 DELETED C1 10/dC C2 ZP' 8J0-1 DELETED 01 10/80 C2 P d50-1 DELETED C1 10/8C G2 P 860-1 DELETED C1 10/80 02 P 68C-1 DELETED Cl 11/80 02 P 1110-1 STATION DIRECTOR (ACTING STATION C4 3/83 02 DIRECTOR) IMPLEPENTING PROCEDURE

'P 1120-1 OPERATIONS CIRECTGR IMPLEMENTING C4 2/83 02 PROCEDURE P 113C-1 TECHNICAL DIRECTOR IMPLEMENTING PROC. C3 4/81 02 P L190-1 . MAINTENANCE DIRECTOR IAPLEMENTING Cl 11/80 02 PROCEDURE P 1150-1 STORES CIRECTCR IMPLEPENTI.4G PRCCEDURE C1 11/80 02 P 11o0-C1 ADMINISTRATIVE DIRECTOR IMPLEPENTING C2 1/82 02 i PROCEDURE I

[2P 117C-1 SECURITY DIRECTOR INPLEMEATING 04 7 /83 02 PROCEDURE 1180-1 RAD / CHEM DIRECTOR IMPLEMENTING C3 7/81 02

{ZP PROCEDURE P L180-2 RAD / CHEM CIRECTCR INITIATED G1 11/80 02 ENVIRONNENTAL MONITORING ACTIVITIES

'P 1190-1 ENVIRONS DIRECTOR INPLEMEhTING CO 6/83 C3 PRCCCOURC iP 1200-1 CLASSIFICATIONS OF GSEP COaDITIONS C3 8/82 01 ZP 1200-2 CLASSIFICATION CF A N06LE GAS RELEASE Cl 5/82 G2 P 1200-3 CLASSIFICATION CF AN IOGINE RELEASE 01 2/82 01

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L 7/06/83 LZP INDEx PAGE .

ROC. NO. TITLE RE/. REV OATE CISKETT P 1200-4 CLASSIFICATION CF A LIQUIO RELEASE Cl 5/82 01 f

P 121C-1 HAZARDOUS MATERIAL INCIDENTS REPORTING C2 3/83 01 P 1220-1 EMERGENCY TELEPHONE NUMBER CL 5/81 01 P 1220-4 DELETED C1 7/81 01 CONTAINMENT ATMOSPHERE FOR RACIGIDINES DETERMINATION AND PARTICULATES ALTERNATE "EANS i P L31C-1 NOTIFICATIONS Ott 7/83 C2 P L320-1 AUGMENTATION CF PLANT STAFFING C5 7/83 02 P 133C-1 DELETED C2 7/82 02 P 1330-2 DELETED C2 7/82 03 P 1330-3 OELETED C3 ,

7/82 03 P 1330-4 DELETED 02 7/82 03 P 1330-5 POST-ACCIDENT NOBLE GAS RELEASE RATE CO 11/SC 03 I DETERMINATION P 1330-6 DELETED 01 7/81 03 l P 1330-7 DELETED C2 7/82 02 LP 1330-8 SAMPLING LIQUID PROCESS MONITCRS 01 8/82 03 DURING LIQUID MONITOR HIGH RADIATION ALARM CCNDITIONS P- 1330-10 DELETED 01 1/82 03

~P 133L-11 OILUTION AND-TRANSFER OF GAS SAMPLES 00 11/81 03 P 1330-20 POST-ACCIDENT ANALYSIS OF BARGN CO 3/81 03 (BACKUP PROCECURE)

~P 1330-21 POST-ACCICENT ANALYSIS OF CHLCRIDE 03 6/82 03 2P 1330-22 CALIBRATION OF THE MODEL 10 DIONEX C2 4/82 03 ION CHROMATOGRAPH

'P 1330-23 DETERMINATICN OF REACTOR COOLANT PH, 02 6/82 03 CONOUCTIVITY AND DISSOLVED OXYGEN CONCENTRATION AT THE HIGH RAOIATION SAMPLE SYSTEM (LP 133C-24 DETERMINATIGN OF REACTJR COOLANT C2 1/83 03 HYOROGEN AND OFF-GAS C3aCENTRATIONS AT

.THE HIGH RADIATION SAMDLING SYSTEM

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7/CS/63 LZP INDEX PAGE -

ROC. NO. TITLE REV. REV DATE CISKETTI P 1330-25 SAMPLIr4G OF REACTOR COOLANT AT THE 02 o/82 03 HIGH RADIATION SAMPLE SYSTEM P 1330-26 SAMPLING OF CONTAINMENT AIR AT THE 03 o/32 03 i HIGH RADIATION SAMPLItG SYSTEM J P 133C-27 DELETED 02 10/82 03

'P' 133C-28 SAMPLING OF RADI0 ACTIVE WASTE LIQUICS 02 o/82 03 RADIGACTIVITY AT THE HIGH RADIATION P 1330-29 DELETED 01 10/82 03 P 1330-30 TRANSFER OF WASTES FRCM THE HRSS WASTE 00 11/81 03 TANK ANC WASTE PUMP P 1330-31 DELETED 01 6/82 03

'O 1330-32 POST ACCICENT SAMPLING OF THE GENERAL C2 3/83 C3 ATOMIC WIDE RANGE GAS MONITOR P 1330-33 ISOTOPIC ANALYSIS OF LIQUID SAMPLES CO 6/82 03 USING AAIS SOFTWARE wlTH PARAPS HARDWARE P 1330-34 ISOTOPIC ANALYSIS OF NOBLE GAS SAMPLES 00 6/82 03

$ USING AAIS SOFTWARE AND PARAPS HARDWARE P 1330-35 ISOTOPIC ANALYSIS IODINE SAMPLES USING 00 6/82 03 AAIS SOFThARE AND PARAPS HARDWARE 1330-36 ISOTOPIC ANALYSIS OF PARTICULATE CO 6/82 03 hP SAMPLES USING AAIS SOFTWARE WITH i PARAPS HARDWARE P 1330-50 RADIATION SURVEYS UNDER ACCIDENT 00 10/81 03 CONDITIONS hP 1340-1 IMPLEMENTING PRCCEDURE FOR FIRE: 01 9/81 02 FIRE MARSHALL P 1340-2 IMPLEMENTING PRCCEDURE FOR FIRE: 02 3/d3 02 FIRE CHIEF (CESIGNATED SHIFT FOREMAN) 1340-3 IMPLEMENTING PROCEDURE FOR FIRE: 01 9/81 02 (P FIRt UFFICER F1 (LUGNILANT MAINTENANLE FOREMAN) 134C-4 IMPLEMENTING PROCEDURE FOR FIRE: 01 9/81 C2

[lP - FIRE BRIGADE P 1340-5 IMPLEMENTING PROCEDURE FOR FIRE: C1 8/81 02 FIRE COMPANY NO. 1 (MAINTENANCE PERSONNEL) f __ -

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7/Cd/83 LZP INDEX PAGE :

TITLE REV. REV OATE DISKETTu ROC. NO.

9 1360-1 PROTECTIVE MEASURES FOR ON-SITE 03 7/81 02 PERSONNEL P 1360-2 USE OF POTASSIUM IODIDE (KI) AS A C1 1/S3 03 THYROID BLOCKING AGENT P 1360-4 RADIATICN PROTECTION PRACTICES CURING 00 11/81 03 ACCIDENT CONDITIONS P 1370-1 RESCUE 00 10/60 02

<P 1370-2 PERSONNEL INJbRIES C2 11/62 02 P 1370-3 FIRST AID, DECONTAMINATION AND 00 10/80 02 EVACUATION CF EXPOSE 0 AN0/OR CONTAMINATED CASUALTIES P 1380-1 CONTROL OF OIL SPILLS C1 12/82 02 P 1420-1 ROLE ANO STAFFING OF THE ON-SITE TSC 01 11/80 02 P 1430-1 ROLE AND STAFFING OF THE ON-SITE CSC 02 4/61 02 P 1440-1 ON-SITE GSEP COMMUNICATIONS SYSTEMS C3 12/82 02 P 1920-1 DELETED Cl 7/81 02 P 145C-2 DELETE 0 01 7/81 01 8P 1510-1 GSEP OPERATIONAL READINESS CO 10/80 01 P 1520-1 TRAINING RECUIREMENTS CO 10/8C C2 P 1530-1 EXERCISES AND ORILLS 01 8/81 02 P 1550-1 FIRST AID FACILITIES MONTHLY 02 12/82 02 SUkVEILLANCE JP 1550-2 ENVIRONS SAMPLING SUPPLIES INVENTCRY 03 12/82 01 h

1P 155C-3 DECONTAMINATICN FACILITIES MONTHLY 01 S/81 02 SURVEILLANCE f

SP 1550-4 ST. MARY'S HOSPITAL HEALTH PHYSICS Cl 7/81 C2 SUPPLIES QUARTERLY SURVEILLANCE 155C-5 TECHNICAL SUPPORT CENTER JUARTERLY 02 2/63- 01

[ZP SURVEILLANCE P 1550-6 OPERATICNAL SUPPORT CENTER QUARTERLY C2 2/83 C1 3URVEILLANCE P 1550-7 DELETED 03 4/83 01 I

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'7/C8/83 LZP INDEX PAGE :

/RCC. NO. TITLE REV. REV OATE DISAETT!

P 1550-8 DELETED 03 3/83 02 l (NARS) MONTHLY SURVEILLANCE P 155C-9 SPECIAL TLD QUARTERLY SURVEILLANCE C2 11/81 03 P 1550-10 ENVIRONMENTAL SURVEILLANCE STATIONS CO 7/81 07.

P 1550-11 PUST-ACCIDENT SAMPLING ECUIPMENT 01 7/,g3 03 INVENTORY P 1610-1 RECOVERY AND RE-ENTRY PLANS C0 10/80 01

'P 1700-1 GSEP STATION GRCUP DIRECTCRY CS 1/83 01 P 1700-2 STATION EMPLOYEE LIST 05 7/g3 01 P 1700-3 STATION PHONE LIST C4 7/83 03 r

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L LZP-1170-1 Revision 4 Jul y 15, 1983

[ 1 SECURITY DIRECTOR IMPLEMENTING PROCE00RE A. PURPOSE The purpose of this procedure is to outline the method used to implement the Station Security Director's duties during emergency situations.

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L B. REFEREV M

1. LZP 1320-1, " Augmentation of Plant Staffing."

2. LZP 1700-1, " Station Group Directory."

3. LZP 1700-2, " Station Employee List."

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4. LaSalle Security Procedures.

[ C. PREREQUISITES

1. None. I L. O. PRECAUTIONS r 1. None.

E. LIMITATIONS AND__ ACTIONS

' 1. The Operating Shift Supervisor provides the services of the Station Security Director until relieved of the responsibility by the Security Administrator r per Reference 4.

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2. Responsibility.

a. PROVIDE security services including plant

[' personnel accountability and plant security as required during the emergency.

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3. Notification.

a. Initial notification by:

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1) Acting Station Director.

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i.ZP-1170-1 Revision 4 July 15, 1983 2

a) Operating Shift Supervisor.

b) Senior NSO.

r 2) Activation Phone List.

L F. PROCEDURE

1. ASSUME GSEP duties in the Technical Support Center

( unless otherwise directed by the Station Director.

Attachment A is provided to serve as a checkilst for the convenience of the Director.

2. INFORM the Station Director of tne overall plant security situatlon.

( 3. ACCOUNT for all personnel within the protected area.

a. In the event of an onsite assemoly of all personnel, the Security Ofrector should account

( for all individuals within the protected area at thO time the assembl y was announced, and should De able to ascertain tne names of missing

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< individuals within 30 minutes. Attachment 8 may De used as an assembly program.

( 4. MAINTAIN plant security.

a. Main Access Facility - Extensions 496 and 219.

L O. Guard Force - 312-969-0955, Burns International Security, Services, Inc., Nuclear Unit.

f L, 5. IDENTIFY to the Station Director any non-routine security procedures and/or contingencies that are in effect or require a response.

i l 6. COORDINATE with the Rad / Chem Director in controlling ingress and agress to the protected area.

( 7. MAINTAIN a record of the GSEP relateo activities.

G. C HEC X f.I ST S

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LZP-1170-1 Revision 4 July 15, 1983 3

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1. None.

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_ECHNICAL SPECIFICATION REFERENCES

1. None.

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[ LZP-1170-1 Revision 4 July 15, 1983 4

ATTACHMENT A i

SECURITY DIRECTOR

, CHECKLIST OF INITIAL GSEP RESPONSIBILITIES This checklist is provided solely for the convenience of the Security Director. It is not necessary to t follow this checklist step by step. Its completion is not required and its use is determined Dy tne Security Director.

I. Assembly:

f a. See Attachment 8 for an assemoly outline.

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II. If it is recommended that the site ce evacuated, post r the appropriate exit for traffic control (West and/or

[ South gate).

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LIP-1170-1 Revision 4 July 15, 1983 ;

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[ III. Coordinate with the Rad / Chem Director and control ingress and egress to and from the protected area.

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LZP-1L70-1 Revision 4 i July 15, 1983 l f 6 ATTACHMENT B

[ SECURITY DIRECTOR I ASSEMBLY OUTLINE M3

1. This outline is provided solely for the convenience of the Security Director. It is not necessary to follow

{ this outline step oy step. Its use is to De deterrinec by the Security Director. l

( 2. During Assembly Orills it is necessary to maintain an adequate security posture. Posts and positions not taking part in the Drill should oe pre-noti f ied. During actual

( assemolies the Security Di rector is responsible to assure all Security personnel participate in the assemoly.

ASSEMBLY I. The GSEP activity will De initiated oy the Shift Engsneer cr Station Director.

II. Notification to activate the TSC will be made.

[ III. Upon receipt of notification to report to the TSC, L arrange to take the following materials to tne TSC:

a. ASCI- Alphabetical Iisting - printout. j

o. Unit / Sector Outl i ne.

c. Current PC - Numerical listing printout. I

d. RC - Roll call printcut - request rost current.

f e. Stationery supplles.

Notify the Security Shift Supervisor that you are in the TSC and assuming the security responsibilities of tne

{ station. Request a current Badge Issue Log - form LSF164, a Radio and an Onduty Log from the Security Shift Supervisor.

IV. When necessary, the Station Director may determine if an assembly is required.

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LZP-1170-1 Revision 4 July 15, 1983 V. If a Roll Call - RC - printout i s unavailable, the l

Badge Issue Log - form LSF164 will be used.

I Compare the hand logs to the PC printout to determine tne actual roll call.

VI. Inquire of the Shift Engineer / Station Director if

( an assembly is imminent. Notify the conscle operator of the schedule.

VII. Upon notification that tne assembly is to start, advise the console operator to prepare the computer for the assembly by:

( a. Loading the tape that de-activiates door alarms for the assembly.

o. If the tape is not loaded, the Security Director shall determine if the assembly snculd continue with Active Door Alarms.

VIII. The Conscle Operator will complete the assembly preparations Oy initiating the AA-5 command. The Security Director will oe notified when the computer

{ preparations are completed.

a. If the AA-S command cannot be initiated, advise the security assembly coordinator to nand log the assembly on Badge Issue Form - LSF164.

IX. Advise the Station Director that preparations for the assembly in progress.

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X. Advise the Security Shift Supervisor to man the t assembly areas and secure and evacuate the access facilities.

M An adequate level of security will be maintained during assembly drills.

! XI. Assure that hand logs are develeped for groups and individuals on site and not participat;ng in tne assembly. Included are ISC attendees, Auditors and security personnel on post.

XII. Upon completion of preparations notify the Station Director and Shift Engineer that the assemoly siren may now be sounded.

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l LZP-il70-1 Revision 4 Jul y 15, 1983 8

a. If the assembly siren f alls to operate or is

( operated out of sequence consider using all t available communicati ons to adv i se si te personnel of the appropriate course of action.

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[ XIII. After the assembly has started, contact the security assembly coordinator anc determine how tne assemoly is progressing. l

a. If an individual card readers fail, assure that the inalvidual assemoling are re-directea to an operating reader.

b. If all the assembl y card readers fail, consider aborting the drill. If tne assemoly must continue, assure nand logs are generated.

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c. Actual assemblies must continue until compl et i on.

XIV. Maintain a communication channel with the security assembly coordinator, to verify the estimated y

completion time and assemoly conditions.

t XV. Fifteen minutes after the siren, consider requesting an intermediate assembly report, an AA-R from the console operator.

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XVI. To prepare for the accountability, delete the names of known non participants, obtained in B.III.d, B.V.

and 8.IX.

XVII. As soon as the assembl y appears to be completed request an AA-R printout from the console operator.

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a. If the assembly is a drill and the assemoly is c

not completed by twenty five minutes after the

{ siren, consider aoorting the drill.

XVIII. Review and compare the assembly reports, print outs, handlogs. and cesignated non-participants to aetermine

{ if anyone is unaccounted for.

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[ XIX. After determining who is unaccounted for using the i Unit / Sector outline, advise the Station Director who is missing and their last known location.

XX. Advise the Rad Chem Director of the missing

( individuals, their last known location and inquire if a search is to be i mpl i mented.

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1 LZP-ll70-1 Revision 4 July 15, 1983 9

(finen XXI. Advise the search party of the names of the inoividuals j missing, their company af fil iation and the last i Known location.

r XXII. This concludes the assemoly participation.

l XXIII. If the assembly was a drill, assure that the security l force personnel are released first. Advise the i console operator to run an AA-E and return all al arms

{ and activities to normal.

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XXIV. If the GSEP activity requires an evacuation, request

[ the Rad Chem Director to suggest an evacuation route.

Advise the Security Shift Supervisor of the evacuation and route.

XXV. Upon direction from tha Station Director, release the assemblers either to evacuation or normal duties.

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LZP-1310-1 Revision 4 July 21, 1983

( 1 r NOTIFICATIONS

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A. PURPOSE

( The purpose of this procedure is to outline the various notification requirements for GSEP response conditions.

B. 3EFcRENCE_S

1. IE Bulletin No.79-06B.

( 2. IE Bulletin No. 79-08.

3. IE Bulletin No. 80-15.

4. IE Information Notice 80-06.

5. Supplement to IE Information Notice 80-06, dateo July 29, 1980.

6. 1GCFR Part 50 Section 50.72, Notificaticn of I Significant Events.

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7. 10CFR Part 20 Section 20.403, Notification of Incidents.

8. Nuclear Stations Division Manager's Directive No.

014.

9. Generating Stations Emergency Plan, Secticn 6.0.

10. Regulatory Guide 1.16.

11. Technical Specification, Section 6.6.

12. LZP 1110-1, " Station Director Implementing Procedure."

13. LZP 1210-1, "Hazaroous Material Incidents Reporting."

14. LZP 1380-1, " Control of Oil Spills."

15. Environmental Emergency Plan Inplementing Procedures.

16. 10 CFR Part 70 Section 70.52.

17. 10 CFR Part 73 Section 73.71 s

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1 LZP-1310-1 Revision 4 ,

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18. LXP 100, " Security Contingency Events (General)."

C. PRfRggU! SITES

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1. None.

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0. PRECAUTIONS

1. All information given over the ENS phone will oe designated as unofficial and preliminary-until it is reviewed and finalized oy the Shift Engineer, the Station Director or Command Center Desk.

r E. LIMITATIONS _AND_ ACTIONS

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1. Whenever the NRC phone (ENS) is used, notification . -

of the General Office Nuclear Duty Officer is required. Normall y, the station will inform the

( Power Supply Load Dispatcher to make this required notification. However if shift superv i sor- recei ved r instructions (via the night orders-or direct

( communication with the specific Duty Officer) to take the responsiOllity for direct notification of

, the Duty Officer, they must then inform the load dispatcher that the station will make the required

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notification.

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F. PROCEDURE

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1. When initial notification of an emergency is made to State or local authorities the State of Illinois

( Nuclear Accident Report Form (Attachment C) is to be used to compile the information needed for the , .

report with periodic updates made whenever possiole ' 1 f if plant or atmospheric conditions change L significantly. Per 10 CFR 50 App E. D.3, State and

local authorities must be notified within 15 min. ,

7 of declaring an emergency (initiation of GSEP).

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2. A requirement to notify the NRC within cne (1) hour i applies to the following events which should ba '

reported on the Control Room phone:

a. In accordance witn References 1 and 2, one hour r notifications shall be made when the reactor

[ is not in a controlled or expected condition ,

while operating or shutdown. This condition is interpreted to mean:

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r LLP-1310-1 Revision 4 July 21. 1983 L 3

1) A LOCA or similar failure of the reactor _ '

l coolant system wnich resul ts in an uncontrolled increase in containment ,

radiation levels, pressures, cr temperatures I or unexpected uncontrolled release of radioactivity off-site.

2) When the reactor coolant system pressures and temperatures are not under control or following expected trends 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 ne made as soon as possiolo and, in all cases, within one hour Dy telephone for the events listed below. For the following events, also estaolish and maintain an 2Een t continu2W1 communications channel witn tha NRC Operations Center and close this channel only when notified by the NRC:

1) Any event requiring initiation of the g licensee's emergency plan or any section of that plan as described Delcw:

a) See Attachment A (GSEP Table LA 5-1, LSCS Emergency Action Levels).

b) Fires are reportaole i f an of f-s i te fire department is notified to respond or assist, or more than ten (10)

L minutes is required from the time of discovery to control or extinguisn the fire.

2) The exceeding of any Tecnnical Specification Safety Limit.

3) Any act that threatens the safety of the nuclear power plant or site personnel, or the security of special nucisar material.

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This includes civil disturbances or acts of sabotage or attempted sabotage. (See ,

LXP 100 for additional information.)

c. In accordance wi+.h Reference 4, 5, 6, 7, and

8. notification shall be maoe as scon as possible f

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LLP-1310-1 Revision 4 July 21, 1983 4

and in all cases witnin one hour oy telepnone L for the following events:

1) Any event requiring initiation of shutdown l of the nuclear power plant in accordance with Technical Specification Limiting Conditione, for Operation.

r L 2) Personnel error or procedural inadequacy which, during normal operations, anticipated operational occurrences, or accident

( conditions, prevents or could prevent, by i tsel f, the fulfillment of the safety function of those structures, systems,

[ and components important to safety tnat L are needed to (i) shutdcwn the reactor safely and maintain it in a safe shutdown condition, or (ii) remove residual heat

( following reactor shutdown, or (iii) limit the release of radioactive material to acceptable levels or reduce tha potential I for such release.

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3) Any event resulting in manual or automatic p actuation of Engineered Safety Features, L including the Reactor Protection System.

Notification is required for unplanned unit or reactor trips resulting f rom valid Reactor Protection System (RPS) actuation.

Excluded from notification are:

a) Partial actuation of safeguards or L RPS (i.e. -half scrams).

0) Actuation of ESF including the RPS L

wnich result from and are part of the planned sequence during surveillance testing or startup testing.

I L 4) Any accidental, un pl an ned , or uncontrolled radioactive release (normal or expected releases from maintenance or other L operational activities are not included).

Gaseous or liquid releases require notification if:

a) A minor release which escapes the plant, is detectacle either tnrough r sampling or observation cf a (recording)

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LZP-3310-1 A Revision 4 Jul y 21, 1983 5

i monitor, or reaches a monitor alarm '

I setpoint. and is associated witn an unplanned or accidental event.

O) The release exceeds a Technical Specification Limiting Condition for operation.

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c) Excluded from notification are ,

increases in ef fluent monitor from sampl i ng, inventory changes in rented tanks or equipmant, and increases attrioutaole to operating processes wherein radioactive water moves I

( through systems witn minor leakage such that activity will be releasad to vented buildings. (i.e. - start of pumps with controlled leakage seals)

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5) Any f atall,ty or serious injury occurring

( on the site and requiring transport to an off-site medical facility for treatment.

Serious injury is considered to oe any l injury that in the judgement of tne licensee L representative will require aamission of the injured individual to a hospital for treatment or ooservation for an extended a period of time (greater than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ).

Injuries that only require treatment ana/or medical observation at a hospital or off-f site medical facility, but do not meet L the conditions satisfied aoove, are not required to oe reported.

a) Notification should also De mace for les's severe injuries if contamination s, complications also exist or if an

' ambulance service is used to transport ,

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the victim to an off-site medical facility. 4 O &

6) Any serious personnel radioactive contamination requiring extensive on-site decontaminati on or outside absi stanco.

7) Any incident invol ving by product, source, or special nuclear material which, in

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i LLP-1310-1 Revision 4 i July 21, 1983 I 6 accordance with 10CFR section 20.403, may have caused or threatens to cause:

f a) Exposure of the whole body of any individual to 25 rems or more of radiation; exposure of the skin of .

the whole Dody of any individual of 150 rems or more of radiation; or exposure of the feet, ankles, hands or forearms of any individual to 375 rems or more of radiation; or -

b) -The release of radioactive material ,

in concentrations which, if averaged over a period of 24-hours, would exceed 5,000 times the limits specified for such materials in 10CFR 20 Appendix Be Table 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 f

$200,000.00.

8) Strikes of operating employees or security guards, or honoring of picket lines by these employees.

d. In accordance with Reference 3, notification shall be made within one hour, by commercial telephone or relayed message, to the NRC Operations Center, when one or more extensions -

of the Emergency Notification System (ENS) is ' )

found to be inoperable for any reason. (See precaution #1)

3. Notification of reportable Oil or Hazardous Substances.

a. Oil spills shall oe reported as required per Reference 14.

t

b. Hazardous material s snall be reported in accordance with Reference 13. -

4. A requirement to notify the NRC within twenty-four (24) bours applies to the following events which should be reported on the Control Room pnene. Tnese

l

. . - _ _ . - - . .-.- -.-~. --.---..._ . - ..... . . .

f . .

(

LZP-1310-1 Revision 4 July 21, 1983

{ 7 events should be confirmed by telegraph, mailgram, or facsimile transmission ny no later than the first working day following the event, with a written followup report within two weeks.

a. In accordance with Reference 7, any incident involving licensed material which may have causes or threatens to cause:

1) Exposure of the whole body of any individual to 5 rems of more or radiation; exposure of the skin of the whole body of any Individual to 30 rems or more of radiation; or exposure of the feet, ankles, hands, or forearms to 75 rems or more of radiation; or

2) The release of radioactive material in concentration which, if averaged over a period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , would excead 500 times the limits specified for such material s in 10CFR2C Appendix B, Table II (see Attachment B); or

3) A loss of one day or more of the operation '

of any facilities affected; or

4) Damage to property in excess of 52,000.00.

o. In accordance with Reference 10, nctification shall be made as expedi tiously as possible, but within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by telephone for the following events:

1) Failure of tne reactor protection system or other systems subject to limiting ,

safety-system settings to initiate tne . g required protective function by the time I a monitored parameter reaches the setpoint specified as the l imiting safety-system setting in the technical specifications or failure to complete the required protecti ve function.

2) Errors discovered in the transient or

[

accident analyses or in the methods used

( for such analyses as descrined in the safety analyses report or in the bases for the technical specifications snat nave

l L

[ .

(

LZP-1310-1 Revision 4 July 21, 1983 8

or could have permitted reactcr operation in a manner less conservative than assumed f in the analyses.

3) Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than that assumed in the accident analyses in the f safety analyses report or technical specifications bases; or discovery during plant life of conditions not specifically considered in the safety analyses report or technical specifications that require re medi al action or corrective measures to prevent existence or development of an unsafe condition.

5. Accidental critical i ty requi res immediate NRC Regional Office notification (Region III) by telephone ang a followup telegram, mailgram or f acsimile (Reference 17).

6. As required in Reference 17 and 18, one nour notification of the NRC Operations Center via the ENS line is required for:

a. Any event which significantly threatens or lessens the effectiveness of a physical security system.

b. The loss, unlawful diversion, theft, at tempted theft or suspected attemptea theft of special nuclear material. This event also requires immediate notification of the NRC Regional

[

Office by telephone 2ng followup telegram, t mallgram or facsimile notification.

c. An act of re.diological sabotage against the plant or its transportation system.

G. CHECKLISTS

1. None.

H. TECHNICAL SPECIFICATION _ R E F E R E NC E S,, _

(_

t

. . - _ . . - . . . . . - . - - . . - - . - . .~ - - . - - - . -- -- -

LZP-1310-1 Revision 4 July 21, 1983 9 ,

1. Section 6.6.

D L - - -

ATT ACilitENI A

', LZP 1310-1 1

Revision 4

., , ' July 21, 1983' .

LSCS D1ERGENCY ACTION LEVELS l ,

10 i .

SITE . CENERAL EMERGENCY EMERCENCY UffUSUAl. EVEtiT ALERT CofiDITION

Events in Events in progrenn Events in prog ess Events in progress Cinns Description or have occurred which progress or have or have occurred which ,

or have occurreo <:'-ich occurred which involve actum1 or I

Indicated a potential involve and actual or imminent substantial l

degradation of the potential subetantial involve actual or likely major core degradation or i level of Safety of degradation of the level of safety of failures of melting with potential ;

I

- the plant.

the plant. plant functions for loss of contain- l

, need for pro- ment integrity.

tection of the I public n

1 .

Irppacted on-site and Impacted on-site

1) Aircraft Crash Impacted on-site and requiring unit requiring unit shut-l or minniles from down due to the shutdown due to

}#hatever nource. implementation of the implementation f an ACTION statement of Technical of the Technical Specif ication l SpectfIcations Section 3.0.3.

Evacuation is l,

! Evacuation in antici-l 2) Control Room pated or required with required and i Evacuation control established control is not l l [ rem remote shutdo.sn estahtished l I

i panel from remote .

shutdown panel .'l '

. within 15 min. ,

I 9

A

n -,

L 1310-1

- ATJAtllHENT A .

ev sion 4 ,

LSCS EMERGEllf.Y ACTION LEVELS July 21, 1983 ii SITE CEN3RAL EMERGENCY EMERGENCY UNUSUAk,' EVENT ALERT ,

CONDITION At a level greater At a level '

3) Earthquake Equipment activated greater than a at the setpoint level then an Operating (Activation of Basis Earthquake Safe Shutdown seismic monitoring ( f 0.Olg) Earthquake with alarm with level (0.1 9 horizontal 0.066 g vertical) a unit not in verification from cold shutdown or j the Aux. Electric refueling

Room)

(Not' spurious or (0.2 9 horizontal

~ 0.133 g vertical) testing)

4) Explosion Causing Onsite. Requiring unit shut- Requiring unit down due to the shutdown due Damage to the imple-implementation of

' ad ACTION statement mentation of !

of the Technical Technical Specifications Specifications Section 3.0.3.

1 l

Requiring offsite Requiring offsite Hequiring offsite

! 5) Fire assistance and assistance and ;j assistance (Ongoing an requiring unit requiring unit detected by shutdown due to observation'or shutdown due to .

the implementation the implemen-alarm, and verified tatic.n of Tech-by the Fire brigade) of an AC'1110N state- Fl ment of the Tech- nical Specifi-cation 3.0.3. f' nical Specifications !!

o , 1 l

. { i 4 l e

t

e. . .

l

LZP 1310-1 ATJACHMENT A Revision 4 LSCS EMERGENT ACTION LEVELS J July 21,1983

- - L' SITE GENERAL ,

'l ENERGENCY EMERGENCY UNUSUAL EVENT ALERT ,

CONDITION Rupture of cooling 1) Illinois River 1) Illinois River

6) Flood '7 610' MSL > 710' HSL (188 pond dike affecting, feet above max offsite property (88 feet above max probable flood) probable flood) 1 2)'725 inches of rain 2)> 25 inches of in a 48 hou: period rain in a 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months period.

as determined from ;

thre National ,

Weather Service i 1

1) Control Rod Drop 1) Pipe Breaks Inside ,:

l

7) FSAR Analyzed Primary Containment (FSAR 15.4.9)

Accidents (FSAR 6.2, 6.3, 7.1, i 7.3, 8.3, 15.6.5)

2) Pipe Breaks outside NOTE: For fuel Primary Containment 2) Gaseous Radwaste Handling Accident (FSAR Appepdix C) Adsorber Tank

, (FSAR 15.7.4), see Rupture (FSAR 15.7.1) i 4 l

I l t

s-0

$ e

, *4 i e

ATTACHMENT A LEP 1310-1

i . Revision 4 LSCS ENERG(WCf ACTIOli LEVELS July 21. 1983 l 1,

i 13 , J t

SITE GENf:RAL ENERGENCY EMERGENCY UNUSUAL EVENT ALERT ,

i CONDITION '

Imminent loss of foss of physical The followirs events Security Threat of control of facility.

8) Security Threat increasing severity physical control of as described in the facility.

Security Plans that persists for j 4-more than 60 minutes.

1) Obvious attempt ,

' to sabotage.

e

2) Internal disturbance i i

(disturbance which j l

' is not short lived or is not a harmless i outburst involving one or more indivi-

'I duals within the f f protected area).

l,

3) Bomb device dis-covered.

l l: l l .

J' 4) Hostage.

}

!- 5) Civil disturbance (spontaneous col- ,

{2 lective group 1

gathering which i

)

disrupts normal operations).

6) Armed or forced

- protected area .. .

Intrusion. ,

7) Armed or forced vital area intru-sfon. .

s.

i

-- ~.A m - -

w M w &

LZP 1310-1 ATTACHHENT A Revision 4

f.SCS EMERGFHC,Y ACTION I.EVEI.S gly 21,1983 SITE GENERAL EMERGENCY EMERGENCY UNUSUAL EVENT ALERT ,

r CONDITION J

1) Tornado strikes Sustsined winds of

9) Tornado or Severe 1) Tornado near > 90 mph (Designed facility. facility winds being Ninds) experienced a) Control Roem (Hind speed as informed by 2) Sustained winds of Load Dispatcher > 75 mph.

l' indicated in l Controf Room) or i b) Informed by Station personnel who have made l visual sighting. !

2) Sustained winds of ll

> 60 mph. .f' t

I'

! Detected by the Incident observed Detected by the

10) Toxic Gas chlorine and Chlorine and , ,

(Chlorine, near or onsite Ammonia Detection -

/

Ammonia Detection Ammonia) System without System with Control Room and Auxiliary Emergency Electric Equipment Filtration System

' Room Emergency operable .

Filtration System operable.

f Chlorine detected at 5 ppa

Ammonia detected at 50 ppa

~ '

Unit shutdown due Loss of all the

11) Loss of AC Power Unit shutdown due to following 4160 VAC implementation of to implementation * ~' .

Technical Speciff- of Technical Dusses for>15 minutes:

f Spectilcation 141y (241y), 142y (242y)

.' cation ACTION and 143 (243) .)

statement 3.8.1.1. Section 3.0.3

\

, ' s:

I - - _ 1

^

.ee . . . .

LZP 1310-1 ATTAtllMENT A Revision 4

. , t.SCS EMERGENCY ACTION LEVELS July 21, 1983

. 18; SITE GENERAL EMERGENCY EMERGENCY UNUSUAL EVENT ALERT ,

CONDITION Unit shutdown due to Unit shutdown due to Loss of all the

12) DC. Power implementation of following 125 VDC

~ ' implementation of f Technical Specification Technical Specification Distribution l

ACTION statement Section 3.0.3 Panels for> 15 minutes 111y(211y),

3.8.2.3

. 112y (212y) ,113(213)

, i ,

1) Loss of all systems Loss of ,

13) Plant Shutdown capable of main- systems capable i Functions talning cold shut- of maintaining down, or hot shutdown. #

! l r

2) Failure of the !:

Reactor Protection System instrumen-

'4 tation to initiate i and complete a SCRAM '

j which brings the s, reactor soberitical once a limiting Safety system

~

setting, as speci- i l ;'

i fled in Technical t

'! ' Specificatit,ns '

i Section 2.2.1, has been exceeded.

il j 14) Other Syntems - Unit shutdown due to Unit shutdown due to !i the implementation of implementation of I required by any Technical Specif1- a Technical Specifi- Technical Speciff-cation tsuch as cations ACTION state- cations Section 3.0.3 l

. ECCS, fire pro- ment.

'I tection syntems, ,

, control room ven- i

tilation, etc.)

f i

^

i

- - - . _ _ _ __ h .

-~ >

.....o .

ATTACHMENT A L7.P 1310-1 I' levision 4

+

., ,' [SCS EMERGENCY' ACTION LEVEIS July 21o 1983

M SITE CWMAI*

AI,ERT mf.RGENCY . EMI:RGENCY CONDITION UNUSUAL, EVENT A.>,,,. 2.102 R/hr A. >,, 4x 10 2 R/hr A. 22x10 3 R/hr f 15), loss of Fission Primary Contain- Primary Contain- Primary Contain-Product Barriers ment Activity, or ment Activity, or ment Activity, and B. t,oss of 1 of the B. foss of 2 of the B. toss of 2 of the following 3 fission following 3 fission following 3 fission 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 ,N 300 grab sample > 300 uci/ec equivalent uci/cc equivalent uci/cc equivalent of I-131 of I-131 of I-131

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

>1.69 poig dry- 71.69 psig dry-

> 1.69 psig dry-well pressure and well pressure and well pressure and

I

< -129 inches

< -129 inches < -129 inches Reactor Vessel Level Reactor Vessel Level Reector Vessel f.evel

3) Primary Containment: 3) Primary Containment: 3) Primary Containment:

a) >, 45 psig Contain- a)> 45 paig Contain- a),> 45 psig Contain-ment pressure, or ment pressure, or ment pressure, or b) > 3400F drywell b)> 3400F drywell b) >3400F drywell temperature, or temperature, or

' temperature , or j

c) 7 2750r wetwell c)7 2750r wetwell c)> 2750F wetwell j air temp., or air temp., or air temp., or j

d)> 2000 r wetwell d)> 2000F wetwell d)7 20007 wetwell water temp., or water temp., or water temp.

e) tess of Primary e) tens of Primary Containment Containment

Integrity when intergity when Containment Containment i Integrity is integrity is required. required.

l u u w % % u

s....

LZP 1310-1

' ATTACHHENT A Revision 4

' 'e ,

LSCS EMERGEhCT ACTION LEVELS July 21, 1983

,e I/

- . ~ GENERAL SITE EMERGENCY . fMRRGENCY UNUSUAL EVENT ALEIrf CDNDITION

1) A> 500 gpm Iminent Core Melt

16) I.oss Primary 1) ECCS Initiation A>50 gpm leakage Increare in a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months leakage _ increase Coolant (Not spurious) examples: period as indicated in a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months l by monitors

Or period as a) Loss of F.W. indicated by b) Loss of Con- totalfrer.

i monitors

densate

2) A Main Steam Line Break

2) Failure of a Outside Con-Primary System tainment without

Safety Valve isolation (MSIV to close as closure) as indicated by Indicated by j position in- the following dication. alarms: MS i

j line area temp His Main steam line flow high.

1

?

Monitors are Primary Containment sump

! flow monitorst or air coolers condensate flew rate monitors.

'I i

Standby gas treatment Standby gas treat-

17) Fuel Handling system operable ment system not Accident ,

operable l (Report of damage

I to irradiated fuel assemblies and fuel pool exhaust Monitor > 100 mR/hr)

\

i a

4

--_P % __

n . . . . . , ,

5 ATTACHMENT A LZP 1310-1 I.9CS EMERCENtf MION LEVEtE Rtvision 4

, ' AIy-41, 7383

SITE CENER f EMERGENCY EMERGFHCY UNUSUAL EVEfff ALERT ,

CONDITION

1) Gaseous Effluents 1) Gaseous Effluents 1) Caseous Effluents

18) Radiation Releases 1) Gaseous Effluents >10 times the Effluent monitors Effluent mo nitors Frba the Plant 10CFR20 instantaneous detect levels l 10CFR20 instantaneou detect level cor-release limits responding to corresponding to (10CFR20.105) are release limits j

exceeded as measured (10CFR20.105) as 750 mR/hr >l Rem /hr wiele (1.3x10 7 uCl/sec) tody at the site by the vent stack measured by the for 1/2 hour or toundary. This

rediation monitor vent stack radia- condition exists and/or counting tion monitor and/ 7 500 mR/hr whent i' '

equipment. or counting equip . (1.3x10 8 uC1/sec)

I for 2 minutes at O/u'y4.5 x 107 ment.

the site boundary where (adverse meteor- Q* release rate 4 l ology) In uC1/sec l I

u=mean wind speed in mph or 0/if/1x19 8 s

where 4

i Q* release rate i in uci/sec f u=mean wind speed in meters /sec *

2) Liquid Effluents 2) Liquid Effluents

2) Liquid Effluents

2) Liquid Effluents Estimated 11guld Estimated 1Iquid estimated liquid >10-6 uCl/mi as release > 2 x 10 4 measured by mont- release > 2000 C1 release > 4 Cl but $ 20,000 Ci Ci e but S 40 Cl** tors

and/or ,

sampled and measured counting equipment counting equipment. or ;

Estimated liquid '

I't release ?"40 C1 l butd 2000 C1 i

Mcasitorst Hadioactive liquid waste effluent radiation monitors l l

j service water effluent monitor !

* > 1x10-7pC1/mi but $ 1x10-6 pC1/ml t

~ - - - _

ATTACHHENI*A . LZP 1310-1 LSCS EMERCENCf ACTION LEVELS Rsvision 4

,1 , . . . . , ..

.. . , , . m.so ,, -

SITE GE ERAL EMERGENCY EMERGENCY UNUSUAL ' EVENT ALERT CONDITION . .

i ]

19) personnel Injury Transportation of radioactivity con-I taminated injured person to hospital

20) Hazardous As a direct result of M'aterials hazardous materials a person is killed or hospitalized or esti-mated property damage I exceeds $50,000. I 1 e 21) Any other epndi- Warrants increased ,

tions of equiva- awareness on the part lent magnitude to of the state and/or j the criteria used local offsite to define the officials

' accident category ,

as determined by Station Director.*

I. .

Conditions that may or may not warrant classification under GSEP includet Incident reporting per 10CFR50.72 l'i a.

b. Incident reporting per 10CFR20.403 or Illinois Rules and Regulations, Part D .403. j l

c. Discharges of oil or hazardous substances into waterways per 33CFR153. j Security conti,ngency events per the Station Security Plan.

d.

The Station Director may, at his discretion, categorize the above situations ag GSEP emergencies, depending upon tu seriousness of the situation. (Refer to Section 10.3 of the generic plan for additional information).

e

<~ ..

.oa...

I,ZP 1310-1

"" 4 j ', ,

ATTACHHENT A July 21, 1983

. 20 l -

i 4

' LSCS EMERGENCY ACTION LEVELS _

?

I l Transportation Accident i

4 e

A.

A vehicle transporting radioactive materials or non-radioactive hazardous mater!lats from a I

Commonwealth Edism generating station is involved in a situation in which:

1. Fire, breakage, or suspected radioactive contamination occurs involving a shipment of radioactive material ors I

2. As a direct result of hazardous materials, s

(a) A person is killeds or (b) A person receives injuries requiring hospitalizations or 3 (c) Estimated carrier or other property damage exceeds $50,000.

i l'

t in Any other condition involving hazardous raterial transportation and equivalent (to the criterla t

n. ,

Item A. !:

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4. ?!M Am DATE OF INCIDENT /tVtNTs TIM CATE

3. IK: DENT TWWOLVE5:

6. 51TuaTION INv0Lyts: 7. TfPt OF RELEASC 13 A RAO!0ACT!?! 445ttRIS heRELEA$t S NOMA 010 ACTIVE G4381385 h POTDff!AL (POE51SLC) RELCASE t rag 10 ACTIVE LI WID

. @ tret18mff (PamABLE) RELCAgg l

o A RELCAst ts oCCmRINs *@ noN.aActoACT27t L!calle gA u. TOC RE...urTom. g .N.A,PuCA.a .

8. RECIpometS PROTECTIVE ACTIONS:

h F1R tuPOpt4710N OIR.T - (UW5UAL EVOff, ALDtf OR TRANSPORTAnON ACCIDDIT)

I @ PREPAar Pot ressiou Act:ON INvotvins TNr PusuC. To InCLust eTtrtCATICBi. (AI,CET OR $!TE l DOEDCT OR TRANSPORTATION ACCIWhT)

C IRff!PT PUBLIC TO TAdCE THE FOLLatf]NE PROftCTIVE ACTIONE. (SITE OR GDOAL DEEENCT OR

TRammmm ACCantur.)

MM h N 01 PILE RA0!US (SAstt311 RELIASC)

({ E h 2 5 MILES FOR TMIEt (3) OOMeHE SECTOR $ (GASECRIS RELIASE)

F h 5 10 n!LES FOR TWEEC (3) claNwing stCTons (EASEOUS RELIASC)

G E MILf3 (TRANEPOR*ATIOli ACCIDENT OR OTHER)

}

h 313CONTimt USE OF POTDff1 ALLY AFFECTED _ WATDI .~ IN MILES.

f @ PUT CATTLC tus $10ltED FtCD IN OthNed!E SECTOR $ (Rif TO jf 9. ELIASE 15:

I

@ Couns:Ns . EmCno manor oR msNmot .

t i TrminnTto . APPaoximTC OunAnON oR nAsamat j 14. IEllBIT OF GA$tt385 AELIASE !$:sacum @ LEYtk @ Elt1ATED ETDt1 PER SECOND I I

M1Lts PfA HOUR j 11. v1PS SPitD WTE: uSC NOT APPLICABLE (R/A) WMOtt APPeOPRIATE.

= -

=_ ---- =_ -.

\

.m.,.4-gs_.

=h-LZP 1310-1 '-

nevision 4

- - . . - ~

-? ---

-= --

' . - July 21., 1 ./.. -.. i.

28 (Fina1) 933

- ATTACEME!rr c -

12. wie C1 RECT 13u QSTA (OttCx Ont. uAD ACRoss!

v1g ngy: g wine mdano er m arrr m 389-11 ! -M J K auf 12.r !*" 2KL T 34 5 ". L m LMN M $7 7- f"

=aP

@ ! 79 101 102 12*

"PQ

@ - =E3E u t2 is. -

0=

$5E 147 1C 0RA

! 166 191 "Ai sr ist.n- .E . C a 5 no.2r T *C3 L L _' N .255 DE 01 59 231 E 2EF

-t F 3

- 2 300 '11

@ *GM T 304 325 11

@ 5MJ I:

327.:"! 511 - -

13. CURIENT TRIT 5!DE TUrthelWE: A

'T h 'C

14. WEATNER CIMl!T1045 (RAIN. Sum. 5LttT. ETC.):

15 . TDeta47Unt DIFFEREME (AT): A F* 5 C' or @ C'/100N 3 ELEVAT10E W TDJ. O!FFERDC MA$UEMENT:

16. RELD 5E DETICTED ST:

h T! SAL

[3af8LERENLTSAAtt C INSTRsWITAT!t leENTTF1CAffr _ 'AD14 17 . ACC10Elff RELATED Iluhalts: @ @ NOft1 @ mesta OF !aast!!3

18. A. LOCAT13 W TRAMP 0 ETAT 1'3B ACCDEllT:

8. TTPC or Sminerf (utV FUEL. $ POT FUEL. LW WASTE. ETC.):

1 C. TTPC 7 Vtp!CLE Olt CIBITAIER l

0. ftem 0F MATERIAL SEING $NIPPG ( 5(R.10. LIOUIS. GAsttNS):

5 Yt3 [ 14pett

1. CICO. rTRSONFIL DISPATQtID TO TRMSPORTATIDs ACCIOtNT SCtnt: h NO

19. OTHER lh70R84T10u:

1

20. nt35Ast aEPORTED ST: e anw6.a .wmas m (DJTSIDE d)

21. N.A.R.S. MESSAst atCt!YtB af m ..

r, =

C. W E YTRiFIG: W 70 l iF fu. T -: _ o rm:.

L - -

_ _ _

ML20076L261

Text

F. PROCEDURE

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