Text

Public Version of Revised Lzp Procedures,Including Procedures LZP-1120-1 Re Operations Director & LZP-1160-01 Re Administrative Director.Revised Index Enxl
	ML20041C026
Person / Time
Site:	LaSalle
Issue date:	01/19/1982
From:	; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20041C017	List: ML20041C021; ML20041C026;
References
	PROC-820119-01, NUDOCS 8202260043
	Download: ML20041C026 (68)
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PAGE I 0/17/81 LZP INDEX RDC. 80. TITLE REV. REV OATE DISKETT l

? 100-1 DELETED 03 11/80 01 I LLP 100-2 DELETED 04 11/80 01 l P 100-3 DELETED 03 10/80 01 P 200-1 DELETED 02 11/80 01 TIP 200-2 DELEiED 02 11/80 01 P 200-3 DELETED ej, 02 11/80 01 LZP 200-4 DELETED // \ 03 11/80 01 RECElygg %

P 210-1 DELETED g gg8 g , j 02 10/80 01 1 -.

' LIP 300-1 GELETED

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882 b4 04 8/80 01 l 6

.: ZP 300-2 DELETED g 03 11/80 01 Q>

' ZP 310-1 DELETED y 03 11/80 01 {

b LIP 320'l DELETED 02 10/80 01 ;

i IP 330-1 DELETED 01 10/80 01 l DELETED 01 10/80 01 LZP 3*0-1 f IP 350-1 DELETED 02 10/80 01 ZP 300-1 DELETED 02 10/80 01 5 LIP 370-1 DELETED 01 10/80 01

. ZP 400-1 DELETED 02 11/80 01 LZP. *00-2 DELETED 02 10/80 01 ZP 400-3 DELETED 01 11/80 01 ZP 410-1 DELETED 01 11/80 01 TZP 420-1 DELETED 01 11/oO 01 ZP 510-1 DELETED 02 10/80 01 LZP 520-1 DELETED 02 10/80 01 ZP 520-2 DELETED 01 10/80 01 ZP 52C-3 DELETED 01 10/80 01 10/80 01 ZP 530-1 DELETED g 01 8202260043 820223 b PDR ADOCK 05000373 F PDR

I d/17/81 LZP INDEX PAGE 1 PRUC. NO. TITLE REV. REV DATE DISKETT ZP 530-2 DELETED 02 10/80 01 LZP 590-1 UELETED 01 10/80 01 ZP 700-2 DELETED 01 11/80 01 LZP 710-1 DELETED 02 10/80 01 ZP 810-1 DELETED 01 10/80 02 ZP d20-1 OELETED 01 10/80 02 LIP 830-1 DELETED 01 10/80 02 AP 850-1 DELETED 01 10/80 02 LZP 860-1 DELETED 01 10/80 02 ZP 880-1 DELETED 01 11/80 02 1110-1 STATION DIRECTOR (ACTING STATION 03 8/81 02 GIP

g DIRECTOR) IMPLEMENTING PROCEDURE OPERATIONS DIRECTOR IMPLEPEhTING 03 n/& 02 1ZP 1120-1 PROCEbuRE LZP 1130-1 TECHNICAL DIRECTOR IMPLEMENTING PROC. 03 4/81 02

ZP 1140-1 MAINTENANCE DIRECTOR IMPLEMENTING 01 11/80 02 PROCEDURE ZP 1150-1 STORES DIRECTOR IMPLEMENTING PROCEDURE 01 11/80 02 LZP 1160-1 ADMINISTRATIVE DIRECTOR IMPLEMENTING O2 t /81 02 PROCEDURE LZP 1170-1 SECURITY DIRECTOR IMPLEMEhTING 03 1/ 6% 02 PROCEDURE ZP 1180-1 RAD / CHEM DIRECTOR IMPLEMEhTING 03 7/81 02 PROCEDURE ZP 1180-2 RAD / CHEM DIRECTOR INITIATED 01 11/80 02 l ENVIRONMENTAL MONITORING ACTIVITIES CLASSIFICATIONS OF GSEP CONDITIONS 01 7/81 01 llZP 1200-1 ZP 1200-2 CLASSIFICATION OF A NOBLE GAS RELEASE 00 10/80 02 I ZP 1200-3 CLASSIFICATION OF AN IODINE RELEASE 00 10/80 01 l

LP 1200-4 CLASSIFICATION OF A LIQUID RELEASE 00 7/81 01 HAZARDOUS MATERIAL INCIDENTS REPORTING Of 10/8/ 01 LZP 1210-1 1

I LZP INDEX PAGE 3

/17/81 REV DATE DISKETT.

REv.

R OC . No. TITLE 01 5/81 01 ,

1220-1 EMERGENCY TELEPHONE NUMBER 01 7/81 01 1220-4 DELETED 04 t/92 02 1310-1 NOTIFICATIONS 02 6/81 02 P 1320-1 AUGMENTATION OF PLANT STAFFING 01 11/80 02 LLP 1330-1 POST-ACCIDENT SAMPLING OF REACTOR COOLANT 01 3/81 03 P 1330-2 POST-ACCIDENT SAMPLING OF THE PRIMARY CONTAINMENT ATMOSPHERE FOR RADIGIDINES DETERMINATION AND PARTICULATES I ALTERNATE MEANS POST-ACCIDENT SAMPLING OF PRIMARY 02 3/81 03 P 1330-3 CONTAINMENT ATMOSPHERE 01 11/80 03 LZP 1330-4 POST-ACCIDENT SAMPLING OF THE PLANT VENT FOR RADIGIDINES AND PARTICULATES 00 11/80 03 L4P 1330-5 POST-ACCIDENT NOSLE GAS RELEASE RATE DETERMINATION 01 T/81 03 1330-6 DELETED ZP ILLP 1330-7 PUST-ACCIDENT SAMPLING OF THE STANOBY 01 11/80 02 GAS TREATHENTL (SBGT) SYSTEM EFFLUENT 00 d/61 03 LLP 1330-8 SAMPLING LIQUID PROCESS MONITORS DURING LIQUID MONITOR HIGH RADIATION ALARM CONDITIONS 0t a /92. 03 M EBERLINE SAM-2 LZP 1330-10 00 11/81 DILUTION AND TRAN:iFER OF GAS SAMPLES 00 3/81 03 P 1330-11 1330-20 POST-ACCIDENT ANALYSIS OF BARON LZP (BACKUP PROCEDURE) 10/ 81 03 LLP 1330-21 DETERMINATION OF REACTOR COOLANT CHLORIDE CONCEN TRATION AT THE HIGH RADIATION SAMPLING SYSTDi 10/ 81 03 0l 1330-22 CALIBRATION OF THE MODEL 10 DIONEX ILZP ION CHROMATOGRAPH 03 CO 10/61 133C-23 DETERMINATION OF REACTOR COOLANT PH.

CONDUCTIVITY AND DISSOLVED 0xYGEN ILZP CONCENTRATION AT THE HIGH RAOIATION SAMPLE SYSTEM

i 8/17/81 LZP INDEX PAGE 4 {,

ROC. NO. TITLE REV. AEV OATE DISAETT JP 1330-24 DETERMINATION OF REACTOR COOLANT 00 to/8l 03 I

,3 HYOROGEN CONCENTRATION AT THE HIGH RADIATION SAMPLING SYSTEM LP 1330-25 SAMPLING OF REACTOR COOLANT AT THE Hint! 00 10/Bl 03 RADIATION SAMPLE SYSTEM ZP 1330-26 SAMPLING OF CONTAINMENT AIR AT THE HIGH 00 to/Bl 03 RADIATION SAMPLING SYSTEM LLP 1330-27 SAMPLING OF REACTOR COOLANT OFF-GAS AT 00 10 /8[ 03 THE HIGH RADIATION SAMPLE SYSTEM 00 s0/g ) 03 LLP 1330-28 SAMPLING OF PROCESS WATERS CONTAININ( DAnIO_

ACTIVITY AT THE HIGH RADIATION SAMPLING SYSTEM LP 1330-29 SAMPLING AT THE HIGH RADIATION 00 . 0/00 03 SAMPLING SYSTEM (VALVE OPERATION AT THE VALVE CONTROL PANEL)

ZP 1330-30 TRANSFER OF WASTE FROM THE HRSS 4ASTE 00 n /81 03 TANK AND WASTE PUMP ZP 1330-31 r 50 See next paae LP 1340-1 IMPLEMENTING PROCEDURE F0R FIRE: Ol 9/B/ 02 FIRE MARSHALL IP 1340-2 IMPLEMENTING PROCEDURE FOR FIRE: 01 9/& 02 FIRE CHIEF (OESIGNATED SHIFT FOREMAN) i LP 1390-3 IMPLEMENTING PROCEDURE FOR FIRE: 0I 9/B/ 02 FIRE OFFICER #1 (COGNIZANT MAINTENANCE FOREMAN)

ZP 1340-4 IMPLEMENTING PROCEDURE FOR FIRE: On 9/8/ 02 FIRE BRIGADE 1340-5 IMPLEMENTING PROCEDURE FOR FIRE: 01 8/81 02

$2P FIRE COMPANY NO. 1 (MAINTENANCE W l PERSONNE' )

EP 1360-1 PROTECTIVE MEASURES FOR ON-SITE 03 7/81 02 PERSONNEL 1360-2 USE OF POTASSIUM IODIDE (KI) AS A 00 7/81 03 ILP THYROIO BLOCKING AGENT i I

LZP 1360-4 SEE NEXT PAGE 1370-1 RESCUE 00 10/80 02 IP 1370-2 PERSONNEL INJURIES 01 11/80 02 LIP 1370-3 FIRST AID,'OECONTAMINATION AND 00 10/80 02 j LP

EVACUATION OF EXPOSED AND/OR CONTAMINATED CASUALTIES CONTROL OF OIL SPILLS 00 10/80 02 l 2P 1380-1 l

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I LZP 1330-31 POST-ACCIDENT PLANT SAMPLE MOVEMENT 00 12/81 LIP 1330-50 RADIATION SURVEYS UNDER ACCIDENT CONDITIONS 00 10/81 1360-4 RADIATION PROTECTION PRACTICES DURING ACCIDENT CONDITIONS 00 11/81 I !

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d/17/81 LZP INDEX PAGE 6 TITLE REV. REV DATE CISKETT IPROC. NO.

ZF 1420-1 ROLE AND STAFFING OF THE On-SITE TSC 01 11/80 02 LZP 1430-1 ROLE AND STAFFING OF THE ON-SITE OSC 02 */81 02 LP 1440-1 ON-SITE GSEP COMMUNICATIONS SYSTEMS 01 6/81 02 LLP 1450-1 DELETED 01 7/81 02 ZP 1950-2 DELETED 01 7/81 01 l LP 1510-1 GSEP OPERATIONAL READINESS 00 10/80 01 LLP 1520-1 TRAINING REQUIREMENTS CO 10/80 02 ZP 1530-1 EXERCISES AND DRILLS 01 8/dle 02 lLLP 1550-1 FIRST AID FACILITIES MONTHLY 01 7/81 02 SURVEILLANCE LLP 1550-2 ENVIRONS SAMPLING SUPPLIES INVENTORY 02 7/81 01 ZP 1550-3 DECONTAMINATION FACILITIES MONTHLY 01 5/81 02 SURVEILLANCE 1550-4 ST. MARY'S HOSPITAL HEALTH PHYSICS 01 7/81 02 ILP SUPPLIES UUARTERLY SURVEILLANCE f

ZP 1550-5 TECHNICAL SUPPORT CENTER MONTHLY 01 7/81 01 SURVEILLANCE ZP 1550-6 OPERATIONAL SUPPORT CENTER MONTHLY 01 7/81 01 SURVEILLANCE LZP 1550-7 EMERGENCY OPERATIONS FACILITY 01 3/81 01 MONTHLY SURVEILLANCE LZP 1550-8 NUCLEAR ACCIDENT REPORTING SYSTEM 02 7/81 02 (NARS) MONTHLY SURVEILLANCE ZP 1550-9 SPECIAL TLD QUARTERLY SURVEILLANCE 02 II81

/ 03 ZP 1550-10 ENVIRONMENTAL SURVEILLANCE STATIONS 00 7/81 02 LLP 1610-1 RECOVERY AND RE-ENTRY PLANS 00 10/80 01 ZP 1700-1 GSEP STATION GROUP DIRECTORY 03 7/81 01 LP 1700-2 STATION EMPLOYEE LIST 01 7/81 01 ZP 1700-3 STATION PHONE LIST 01 5/81 03

l. .

LZP-1120-1 Revision 3 Novemoer 13, 19el 1

OPERATIONS DIRECTCR IMPLEMENTING PROCECURE I

A. PURPOSE The purpose of this proceaure is to outline tne metnoc usec to implement tne Station Operations Director's outies.

3. REFERENCES l

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

2. LZP 1370-1, " Rescue."

3. LZP 1700-1, "GSEP Station Group Directory."

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

C. PREREOUISITES .

1. None.

D. PRECAUTIONS

1. None.

E. LIMITATIONS AND ACTIONS

1. Cperations Director's responsioliities:

a. DIRECT a staff in determining tne nature anc extent of the emergency pertaining to equipment and plant facilities.

o. PROTECT personnel anc PERFORM rescue operation as needec.

c. PERFORM corrective actions to terminate the condition causing tne emergancy.

I c. PERFORM actions to protect equipment and facilities from furtner camage.

2. Notification.

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LZP-1120-1 Revision 3 Novemoer 13, 1981 I 2

a. Initial notification oy:

1) Acting Station Director.

a) Snift Supervisor.

o) Senior NSO.

2) Activation Phone List (See Reference 1).

F. PROCEOURE

l. ASSUME GSEP duties in the Technical Support Center unless otherwise directed oy tne Station Cirector.

, ta0Tfg Attachment A is provided to serve as a checklist

I for the convenience of the Director.

2. VERIFY that the System Power Suppl / Loac Dispatcher nas oeen rioti f ieo.

3. VERIFY tnat the Station Director nas been notifieo.

l 4. DIRECT a staff in determiring the nature ana extent of emergencies pertaining to equipment ana plant facilities.

.I 5. INITIATE immediate corrective actions to limit or contain the emergency.

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n 6. DIRECT switching ana valving operations, equipment operations, equipment checxing, and miscellaneous operations as requirec.

7. IMPLEMENT protective actions for onsite personnel, to include site assemol y and evacuation (wnen ordereo oy the Station Director).

8. ORGANIZE and DIRECT rescue operations of injurea personnel (see Reference 2).

a. VERIFY amoulance services have Deen noti fied as requireo.

I D. COORDINATE the transfer of injured personnel offsite.

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LZP-ll23-1 Revision 3 ,

Novemoer 13, 1901 3

9. ENSURE adequate manning of the onsite OSC ano Control Room.

10. OESIGNATE an indivuoual to manage and supervise activities at the onsite OSC.

11. IDdhTIFY steps or procedures tnat the operations I staff shoulo os utilizing to properl y respond to the GSEP condition.

12. MAINTAIN a record of tne GSEP related activities.

G. CHECKLISTS

1. None.

H. TES,HNICAL SPECIFIQ TIONJ EFER QCy I 1. None.

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L2P 1120-1 I ATTACEMiliI A Revision 3 November 13, 1981 4

OPERATIONS DIRECCR .

CHECKLIST OF INIT!AL GSEP RESPONSIBILITf NOTE This checklist is provided solely for the cenvenience of the Operations Director. It is not necessary to follow this checklist step by step.

Its completion is not required and its use is deter =ined by the Operations Director.

l I. Verify the following personnel have been notified:

l l Syste: Power Dispatcher Station Superintendent

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II. Review initi'ilTanning of~ Control' Room Stations and of Operational Support Center. -

Shif: Engineer. -

Shift Control Room Engineer Operations Duty Supervisor U-l NSO U-2 NSO Center Desk NSO Control Rocc/TSC Con =unicator Control Room /OSC Cc=municator Operational Support Center OSC Supervnsor OSC/ Control Roo= Co=municator III. Monitor operations channel of security radio for vital co=munications.

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C? 1120-1 Revisien 3 November 13, 1981 ATTACECC A (Cent'd) 5 IV. Identify steps or procedures that the Operations Depart =ent should be utiliting to properly respond to the CSE? condition.

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l V. Assess the need for having Operating procedures delivered to tha Operational Support Canter. (?recedures may be obtained from the Shif t Engineer's Office) .

VI. Organi:e and direct rescue operations for injured personnel.

Nu=ber of Injured Asbulance Required Contaminatien Involved Location Injured Type of Contaminated Transportation Personnel Injuries Recuired 1.

2.

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4.

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t.Z? 1120-1 I I Revision 3 November 13, 1981 6

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LZ? 1120-1 I **

CACW.EC A (Cen:'d)

Revisice 3 November 13, 1981 f

VIi1. Personnel in OSC by 'Jork Group.

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L27 1120-1

- Revisten 3 November 13, 1981 AT*ACIOC;T A (Cont'd)

IX. Record GSEP-related activities.

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- LZP-llo0-01 Revision 2 January 19, 1982 1

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ADMINISTRATIVE DIRECTOR IMPLEMENTING PROCEDURE 1 A. PURPOSE

- The purpose of this procedure is to outline the metnod used to implement the Station Administrative Director's duties.

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B. REFERENCES _

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

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

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

C. PREREQUISITES

1. None.

l 0. PRECAUIIONS l

1. None.

E. LIMITATIONS AND AqTIONS lI 1. Responsibility.

a. PROVIDE administrative services including food and lodging for station personnel as required during the emergency.

I b. DIRECT a clerical staff as needed during tne course of an emergency.

2. Notification.

a. Initial notification oy:

1) Acting Station Director.

a) Shift Supervisor.

o) Senior NSO.

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I L2P-ll60-01 I Revision 2 January 19, 1982 2

2) Activation Phone List.

F. PROCEDUM ASSUME GSEP duties in the Techn!tal Support Center l.

unless otherwise directed Dy tne Station Director.

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Attachment C is provided to serve as a checklist l

for the convenience of the Director. -

2. DIRECT a staff in the typing of emergency procedures and interim reports during an emergency.

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3. COORDINATE record keeping efforts of the Station during an emergency.

4. ASSIST the Station Director in arranging for relief and continual manning of the Station emergency crew (See Reference 3).

5. ARRANGE for food and sleeping f acilities for tne on-site employees.

a. Restaurants (See Attachment A).

o. Motel s (See Attachment B).

6. MAINTAII4 a record of tne GSEP related activities.

G. CHECKLISTS

1. None.

H. TECHNICAL Sg g g g TION R EFBMCE

1. None.

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- lip 1160-1 Revision 2

. January 19, 1982 ATTACHt'ENT A 3 RESTAURANTS STREATOR ,,

I Town c Country s'.es taurant 2110 H. Bloomington St.

I (315) 672-3183 (6:00 A.M. -

2:30 P.M.)

(5:00 P.M. - 10:30 P.M.)

I Pine Towers Restaurant Route 23 (815) 672-3168 (11:00 A.M. - 2:00 P.M.)

( 5:00 P.M. - 7 )

I Oogles Re'taurant s

310 N. Park Street (815) 672-2364 (8:00 A.M. - 11:00 P.M.)

Bowl Mor Lanes (Barret Room)

! RFD #4 (815) 672-4579 "

(5:00 P.M. - 9:00 P.H. ,

OTTAVA' Hank's Fine Food The Green Mill 209 20th 100 V. Madison Haptate (815) 434-6626 (815) 433-2540 (6:00 A.M. - 8:00 P.M.

Closed Monday Monte's Res. 6 c 71 at Fox River Bridge Lums (815) 434-5000 Columbus c Marquette St. (Rt. 23 c 71)

( 11 : 00 A. M.---------) (815) 433-3311 (10:00 A.M. - 11:00 P.M. Daily)

(Fri & Sat 10:00 A.M. - 12;00 P.M.)

. LZP 1:50-1

". Revi; Ion 2

.- - January 19, 1982 b

. ATTACHMErsi A (Con t i r.ed)

JOLIET ,

Stock Pot Restaurant i 2231 W. Jefferson (815) 729-1629 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Sy1's 829 Moen

Rockdale (815) 725-1977 Sun thru ~ Frl: 11:30 A.M. -

2:00 P.M.

5:00 P.M. - 10:00 P.M.

Fri - Sat: 5:00 P.M. - Midnight Merichka's 604 Theodore Crest Hill I (815) 723-9371 11:30 A.M. - 11:30 P.M.

Babas

. Rts. 52 & 59 (815) 725-5222-24 hours MORRIS Rockwell Inn Town House 2400 W. Rt. 6 115 E. Jackson St.

(815) 942-6224 (815) 942-5132 Mon-Frl: 11:30 A.M. - 11:00,P.M.

Sat: 5:00 P.M. -

12:00 P.M. '

Sun: 4:00 P.M. - 10:00 P.M.

Dinger's The Golden Flame 312 Liberty 1-80 and Rt. 47 (815) 942-0903 (815) 942-6887

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Revision 2

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, . ATTACHr'ENT A (Continued)

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MARSEILLES lilini Lounge Main St. !

(815) 795-4442 I

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LZP 1160-1

, Revision 2 6f anua ry 19, 1982 ATTACHMENT B .

MOTELS STREATOR Town & Country Inn 2110 N. Bloomington St.

(815) 672-3183

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Pine Towers Notel Rt. 23 (815) 672-3168 OTTAVA Sands Notet ,

1215 N. LaSalle St.

(815) 434-6440 I

Ramada inn ;

Res. 23 & 1-80 (815) 434-3400 JOLIET Holiday Inn West 1-55 & Rt. 52 .

(815) 725-2180 Holiday Inn South I-80 & Larkin Avenue

.(815) 729-2000 NORRIS g Holiday Inn l Rts. 47 & I-80 ,,

(815) 942-6600 4

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LZP 1160-1 Revision 2 January 19, 1982 ATTACHMENT C 7 ADMINISTRATIVE DIRECTOR CHECKLIST OF INITIAL GSEP RESPONSIBILITIES NOTE This checklist is provided solely for the convenience of the Administrative Directo..

It is not necessary to follow this checklist step by step. Its completion is not required and its use is determined by the Administrative Director.

1. Maintain a master log of major GSEP-related activities (Dictaphone, stenographer, etc).

II. Identify manning relief requirements and ensure an Individual is available to call reliefs (reliefs for comunicators, TSC personnel,'OSC person .el and I other emergency crews).

I Ill. Ensure training schedules are established for Radiation Protection and Security courses as appropriate.

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LZP 1160-1 ATTACHMENT C (Cont) Revision 2 Janyary 19 IV. Arrange for food and slee9ing facilities for the on-site employees e (Final)1982 I

I V. Record GSEP .related activities.

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I LZP-il70-1 Revision 3 January 19, 1982 l 1 i SECURITY D IR EC". 3R

. IMPLEMENTING PROCEDURE A. PURPOSE The purpose of this procedure is to outline tne metnoo used to implement the Station Security Director's outies.

8. PEFERENCES

l. LLP 1320-1, " Augmentation of Plant Staffing."

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

3. LZP 1700-2, "Stati on Empl oyee Li st."

4. LaSalle Security Procedures.

C. PRjREQUISITES -

l. None.

0. PRECAUTIONS I

1. None.

E. LIMITATIONS AND ACTIONS

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

2. Responsibility.

a. PROVIDE security services including plant personnel accountaoility and plant security as required during tne emergency.

3. Notification.

a. Initial notification oy:

1) Acting Station Director.

a) Operating Snift Supervisor.

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LZP-1170-1 Revision 3 January 19, 1982 2

o) Senior NSO.

2) Activation Pnone List.

F. PROCEDURE

1. ASSUME GSEP duties in the Technical Support Center unless otherwise directed Dy tne Station Director.

NOTE s

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

2. INFORM the Station Director of the overall plant security situation.

3. ACCOUNT for all personnel witain the protected area.

a. In the event of an onsite assemoly of all I personnel, the Security Director should account for all individual s wi thin the protected area at the time tne assembl y was announced, and I should De aole to ascertain the names of missing individuals within 30 minutes.

4. '4AINTAIN plant security.

a. Guard House - Extensions 218 and 219.

D. Guard Force - 312-860-5005, Burns International Security Services. Inc., Nuclear Unit.

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

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

7. MAINTAIN security at tne nearsite EOF if it is activated. ,

8. MAINTAIN a record of the GSEP related activities.

G. C,H E C K L I ST S I

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I LZP-ll70-1 I Revision 3 January 19, 1982 3

1. None.

i H. TECMiGAL SPECIFICATION REFERENCES

1. None.

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W LLP-lL70-1 I Revision 3 January 19. 1982 4

ATTACHMENT A SECURITY DIRECTOR CHEC..u1ST OF INITIAL GSEP RESPCNSIBILITIES liolg This checklist is provided solely for the convenience of the Security Director. It is not necessary to follow this checklist step by step. Its completion I is not required and its use is determined oy the Security Director.

I. Identify to the Station Director any non-routine security procedures ana/or contingencies tnat are in effect or that require a response.

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II. Assembly:

a. Consider placing key coors in access to allow a more rapid pedestrian flow.

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LZP-L170-1 Revision 3 January L9, 1962 5

b. Notify the SCC to activate the security computer accountaoility program and within 1/2 nour ootain printout lists of those indiviauals not in tne assembly area.

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c. Obtain update printout l i sts of individuals not in the assemoly area as necessary.

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t III. If it is recommended that the site ce evacuated, post the appropriate exit for traffic control (West anc/or South gate).

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LZP 1170-1 ATTACHMENT A (Cont) Revision T 4 January 19, 1982 l 7

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

1 V. Maintain security at the nearsite EOF.

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L b LZP 1170-1 Revision 3 January 19, 1982 8 (Final)

ATTACHMENT A (Cont.)

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, VI. Record GSEP-related activities.

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11 LZP-1310-1 Revision 1 l January 19, 1982 l 1

NOTIFICATIONS A. PURPOSE The purpose of this procedure is to outline tne various notification requirements for GSEP response conditions.

B. REFERENCES

1. IE Bulletin No. 79-068.

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, cateo July 29, 1980.

6. 10CFR Part 50 Section 50.72, Notification of -

Significant Events.

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

Nuclear Stations Division Manager's Directive No.

I 8.

014.

9. Generating Stations Emergency Pl an, Secti on 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, " Hazardous Material Incidents Reporting."

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

15. Environmental Emergency Plan Inplementing Proceoures.

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16. IE Bulletin No. 80-17.

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C. PRjRj0UISITjS 1

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LLP-1310-1 Revision 1 l January 19. 1982 2

' I l. None.

D. PRECAUTIONS

1. None.

E. LIMITATIONS AND ACTIONS

1. None.

F. PROCEDURE

1. When initial notification of an emergency is made to State or local authorities tne State of Illinois Nuclear Accident Report Form (Attachment C) is to

g De used to compile the information needed for tne I report witn periodic updates made ~nenever PoSSioie

E if plant or atmospheric conditions enange s i gn i f icantl y.

i

~

2. A requirement to notify the NRC within one (1) hour applies to the following events which should oe reportea on the Control Room phone:

a. In accordance witn References 1 ana 2, one hour

- notifications shall be made wnen the reactor is not in a. controlled or expected condition J

of operation. This condition is interpreted to mean:

1) A LOCA or similar f ailure of the reactor coolant system which results in an

- uncontrolled increase in containment l radiation levels, pressures, or temperatures or unexpecteo uncontrol'.ed release of radioactivity off+ site.

4 I 2) when the reactor coolant system pressures and temperatures are not under control or following expected trenas within a reasonaole amount of time such as 15 minutes after a transient.

O. In accoraance with Reference 4, 5, 6, and 9, notification shall De mace as soon as possiole and, in all cases, within one hour oy telepnone for the events listed below. For the following events, also estaolish and maintain an ooen continuous communications channel with the NRC

L-I f

LZP-1310-1 Revision 1 January 19, 1982 ;

I f

3 l Operations Center and close tnis channel only when notified by tne NRC:

I 1) Any event requiring initiation Cf the licensee's emergency plan or any section of that plan as descrioed below:

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

b) Fires are reportaDie if an off-site fire department is notified to respond or assist, or more than ten (10) minutes is required from the time of.

discovery to control or extinguish the fire.

The exceeding of any Tecnnical Specification I 2)

Safety Limit.

1) Any event that results in the nuclear I power plant not being controlled or expected condition while operating of shutdown.

4) Any act that tnreatens tne safety of the nuclear power plant or si te personnel, or the security of special nuclear material.

This includes civil disturoances or acts of sabotage or attempted sanotage.

c. In accordance with Reference 4, 5, 6, 7, and 8, notification shall oe made as soon as possible and in all cases within one hour oy telepnone for the following events:

1) Any event requiring initiation of Shutdown of the nuclear power plant in accordance wi th Techn ical Specification Limiting Conditions for Operation.

2) Personnel error or procedural inadequacy

s which, ouring normal operations, anticipated g operational occurrences, or accident conditions, prevents or could prevent, by I itself, the fulfillment of the safety function of those structures, systems, and components important to safety tnat are needed to (i) shutdown tne reactor I saf el y ano maintain it in a safe snutdown I

l _

l LZP-1310-1 Revision 1 I January 19, 1982 4

I condition, or (ii) remove residual neat f ollowing reactor shutdown, or (iii) limit the release of radioactive material to acceptable level s or reduce the potential j I .

for such release.

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

Notification is required for unplannea I unit or reactor trips resulting from valid Reactor Protection System (RPS) actuation.

Excluded from notification are:

a) Partial actuation of safeguaras or RPS (i.e. -nalf scrams).

4) Any accidental, unplanned, or uncontrolled radioactive release (normal or expectec releases from maintenance or otner operationai activities are not iac'ucea)-

E Gaseous or liquid releases require 3

notification if:

a) A minor release which escapes the plant, is detectanie either tnrough sampl ing or ooservation of a (recording) moni tor, or reaches a moni tor alarr setpoint, and is associatec witn ac unplannea or accidental event.

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

c) Excluaed from notification are increases in ef fluent monitor from sampl i ng, inventory changes in rented tanks or equipment, and increases attributaole to operating processes wherein racioactive water moves

tnrougn systems witn minor leakage

sucn that activity will be released to ventea ouildings. (i.e. - start E, or pu=Ps witn contro11eo ieaka9e

..5 . seals)

5) Any fatality or serious injury occurring on tne site and requiring transport to an

LLP-1310-1 Revision 1 I January 19, 1982 5

off-site medical facility for treatment.

Serious injury'is considereo to De any injury that in the judgement of the licensee representative will require acmission of the injurea individual to a nospital tor treatment or observation for an extenaec period of time (greater than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ).

I Injuries that only require treatment anc/or medical observation at a nospital or off-site medical facility, out do not meet the conaitions satisfied aoove, are not required to oe reported.

a) Notification should also De made for less severe injuries if contamination complications also exist or if an i

ambulance service is used to transport I the victim to an of f-si te medical facility.

6) Any serious personnel radioactive contamination requiring extensive on-site cecontamination or outside assistance.

1

7) Any incident i nvol ving by-product, source, or special nuclear material which, in accordance with 10CFR section 20.403, may have caused or tnreatens to cause:

a) Exposure of the whole bocy of any indivicual to 25 rems or more of radiation; exposure of the skin of

~~Lhe whole nocy of any indivicual of 150 rems or more of raciation; or exposure of the feet, ankles, hands or forearms of any incividual to 375 rems or more of radiation; or o) The release of radioactive material in concentrations which, if averagea over a period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , would exceed 5,000 times the limits specifica for such materials in 10CFR 20 Appendix B, Taole II (see Attachment B); or

.I c) The loss of one worxing week or more of the operation of any f acil i ti es affected; or

m -

l a

m u LZP-1310-1 Revision 1 r

January 19, 1982

b

{

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 employees.

d. In accordance with Reference 3, notification

{ shall be made within one hour, oy commercial telephone or relayed message, to the NRC Operations Center, when cne or more extensions l E of the Emergency Notification System (ENS) is j L found to De inoperaole for any reason. <

3. Notification of reportaole Oil or Hazardous Suostances.

a. Oil spills shall De reported as requireo per Reference 14.

F o. Hazardous mater ial s shall be rGported in accordance with Reference 13.

l 4. A requirement to notify the NRC within twenty-four I

(

(24) hours applies to the following events wnich should be reported on the Control Room phone. These events should be confirmed by telegraph, mailgram, or facsimile transmission by no later than the first working day following the event, with a written followup report within two weeks.

I I

l

a. In accordance witn Reference 7, any incicent involving licensed material wnich may nave causes or threatens to cause:

1) Exposure of the whole oody of any individual to 5 rems of more or radiation; exposure l of the skin of the wnole body of any individual to 30 rems or more of raoiation; or exposure of the feet, ankles, hanas, or forearms to 75 rems or more of raciation;

.I

2) The release of radioactive material in concentration which, if averageo over a period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , would exceed 500 times the limits specified for such material s in 10CFR20 Appendix B, Taole II (see Attachment B); or 1 ___ ----_

LZP-1310-1 Ig Revision 1 January 19, 1982 5 7

3) A loss of one day or more of the operation of any facilities affected; or

! 4) Damage to property in excess of s2,000 00.

O. In accordance with Reference 10, notification shall oe made as expedi tiousl y as possiole, but within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months oy tel ephone for the following events:

1) Failure of the reactor protection system or other systems subject to limiting safety-system settings to initiate tne required protective function by the time a monitored parameter reacnes the setpoint specified as the limiting safety-system setting in tne tecnnical specifications or failure to complete the requirea protective function.

2) Errors discovereo in the transient or accident analyses or in the methoas useo for such analyses as described in tne 1g safety analyses report or in tne cases 1

3 for the technical specifications tnat nave or could have permitted reactor operation 4

in a manner less conservative than assumed in the anal yses.

3) Performance of structures, systems, or components tnat requires remedial action or corrective measures to prevent operation in a manner less conservative than tnat assumed in the accident anal yses in the safety analyses report or technical specifications cases; or discovery curing plant life of conditions not specifically I considered in the safety analyses report or technical speci fications that require remedial action or corrective measures to prevent existence or development of an unsafe condition.

5. A requirement in accordance with Reference 16 to notify the NRC witnin twenty-four (24) hours applies whenever any of the following ATWS - mitigating ,

systems are not f ull y operational . tJotification (

should De on the Control Room telepnone. Aooitional ;

I

3 LZP-1310-1 Revision 1 January 19, 1982 8

~

notification shoulc be given to the NRC whenever any of these systems are restored to service.

i a. High Pressure Core Spray.

D. Reactor Core Isolation Cooling.

I

c. Standoy Liquid Control.

I. d. RPT circuitry.

i

e. RHR Suprression Pool Cool i ng.

f. Main Steam Bypass.

'4 G. CHECKLISTS

.' 1. None.

H. TECHNICAL SPECIFICATION REFERENCE 1 j 1. Section 6.6.

i i

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' ,)TTACHHENT A R I '

January 19,19625' i l LSCS D1ERCENCY ACTION LEVELS .

9 SITE CENERAL j ALERT EMERCENCY EHERGENCY i CONI 11 TION UNUSUAL EVENT .

I

! 8

' Events in progress Eventa in Events in progress ;

Class Description Events in progress or have occurred which or have occurred which progress or hade or have occurred which :

' indicate a potential involve'an actual or occurred which involve actual or I degradation of the potential substantial involve actual imminent substantial {

1evel of Safety of degradation of the or likely major core degradation or level of safety of failures of melting with potential !

the plant. :

the plant. plant functions for loss of contain- ' I need for pro- ment integrity.

tection of the public.

, 1) Aircraf t Crash Impa'cted on-site ' Impacted on-site and Impacted on-site or missiles from requiring unit shut- and requiring unit whatever cource. down due to-the shutdown due to implementation of the implementation I an ACTION statement of Technical of the Technical Specification Specifications Section 3.0.3.

Evacuation is antici- Evacuation is

2) Control Room Evacuation pated or required with required and control established control is not fras remote shutdown established panel from remote shutdown panet ,*

within 15 min.

I e

.e.

I I

! ATTACHMENT A -

- I LZP 1310-1 .

I '

LSCS EMERCENCY ACTION LEVELS Rsvision 1

- January 19, 1982 ;

in !

SITE CENERAL CONDITION. -

UNUSUAL EVENT , ALERT ENERCENCY EMERGENCY l-

1) Earthquaka Equipment activated At a level greater At a level j (Activation of at a level of > 0.Olg then an Operating greater than a ,

esismic monitoring Basis Earthquake Safe Shutdown i ola rm with level (0.1 g horizontal Earthquake with vartfication from d.066 g vertical) a unit not in the Aux. Electric ,

cold shutdown or Room) refueling (Not spurious or (0.2 g horizontal testing) 0.133 g vertical)

4) Explosion Causing Onsite, Requiring unit shut- Requiring unit ;

Dzmage down due to the shutdown due implementation of e to the imple-an ACTION statement mentation of ;

of-the Technical Technical i Specifications Specifications Section 3.0.3.

5) Fire Requiring offsite Requiring offsite Requiring offsite (Ongoing as . rasistance assistence and assistance and datected ,by requiring unit requiring unit observa tion or shutdown due to shutdown due to clarm, and verified the implementation the implemen- .

by the Fire brigade) of an ACTION state- tation of Tech- '

ment of the Teph- nical Specifi- ,

nical Specifications cation 3.0.3.

I 4

o i

f

LZP 1310-1

, Revision 1 ATTACHMENT A ,

January 19, 1982 11 LSCS EMERGENCY ACTION LEVELS SITE GENERAL CONDITION j UNUSUAL EVENT - ALERT EHERGENCY EHERGENCY 6

6) Flood Rupture of cooling 1) filinois River 1) lilinois River pond dike affecting 610' HSL (88 710' HSL (188 offsite property. feet above max feet above max probable flood) probable flood)

2) 25 inches of rain 2) 25 inches of rain in a 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period in a 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months period as determined from the National Weather Service.

7) FSAR Analyzed 1) Control Rod Drop 1) Pipe Breaks inside Accidents (FSAR 15.4.9) Primary Containment (FSAR 6.2, 6.3, 7.1, Note: For Fuel 7 3, 8.3, 15.6.5)

Handling Accident (FSAR 15 7.4), see 2) Pipe Dreaks Outside 2) Gaseous Radwaste condition no. 17 Primary Containment Adsorber Tank (FSAR Appendix C) Rupture (FSAR 15 7 1:

e O l m --

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M M M .. .

M .. . . . .-

LZP 1310-1 Revision 1 ATTACllMENT A Janua ry 19, 1982

'12 LSCS EMERGENCY ACTION LEVELS SITE GENERAL CONDITION UNUSUAL EVENT ALERT EMERGENCY EHERGENCY

8) Securi ty Threat. The following events Security Threat of Imminent loss of Loss of physical as described in the increasing severity physical control of control of facili ty Security Plan: that persists for facility.

more than 60 minutes.

1) Obvious attempt to sabotage.

2) Internal disturbance (disturbance which is not short Ilved or is not a harm-less outburst in-volving one or more individuals within the protected area).

3) Bomb device dis-covered.

4) flostage.

5) Civil distrubance

~

(spontaneous col-lective group gathering which disrupts normal operations).

6) Armed or forced protected area intrusion.

7) Armed or forced vital area intrusic a. -

. ATTACilHENT A LZP 1310-1 .

( Revision I LSCS EHERGENCY ACTION LEVELS January 19, 1982 ,

13 SITE CENERAL !

CONDITION UNUSUAL EVENT ALERT EMERGENCY EHERGENCY l l

l'

9) Tornado or Severe 1) Tornado near 1) Tornado strikes Sustained winds winds being facility facility of > 90 mph l experienced a) Control room (Designed Winds) ;

(Wind speed as informed by 2) Sustained winds ;

indica.ted in Load Dispatcher of > 75 mph j Control Room) or .

b) Informed by i Station per-sonnel who have made visual afghting. s

2) Sustained winds of > 60 mph. .

10) Toxic Cas Incident observed Detected by the Detected-by the (Chlorine, near or onsite Chlorine and 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 ppa '

Ammonia detected at 50 ppe ,

'l l ) Loss 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) l

t ATTACHMENT A LZP 1310-1

R: vision 1 3-I '

LSCS EHERCENCY ACTION LEVELS January 19, 1982 ~ '

14

SITE CENERAL ALERT EMERGENCY EMERCENCY.

COND[ TION -UNUSUAL EVENT

12) DC Power Unit shutdown due to Unit shutdown due to Loss of all the implementation of toplementation of following 125. VDC Technical Specification Technical Specification Distributtor.

ACTION statement Section 3.0.3 Panels for >15 3.8.2.3 minutes: 111y(211y), '

112y(212y), 113(213)

1) Loss of all systems' Loss of all .

'I3) Plant Shutdown i Functions capable of main- systems capable ,

taining cold shut- of maintaining dt.:en, or hot shutdown.

s

2) Failure of the l Reactor Protection

. System instrumen-tation to initiate and complete a SCRAM which brings the ,

reactor suberttical once a limiting Safety system setting, as speci-fled in Technical Specifications Section 2.2.1, has been exceeded.

14) 0ther Systems Unit shutdown due to Unit shutdown due to rsquired by any the implementation of implementation of Technical Specifi- a Technical Specifi- Technical Specifi-cation (such as . cations ACTION state- cations Section 3.0.3 ;

ECCS, fire pro- ment.

,tcetion systems, control room ven-tilation, etc.)

LZP 1310-1 ATTACtfrtthT A

Revision i .

". f January 19, 1992 *

~

i - LSCS EMERCENCY ACTION LEVELS 15 . ,

SITE CENERAL l CONDITION UHUSUAL EVENT ALERT ' EMERGENCY EMERCENCY

15) Loss of Fission A. Z2.0x10 R/hr A.? fi.0x10 R/hr A. 2 2.0x10 3R/hr r

Product Barriers Primary Contain- Primary Contain- Primary Contain-ment Activity, or ment Activity, or ment Activity, and B. Loss of 1 of the S. Loss of 2 of the 8. Loss of 2 of the .

' following 3 fission following 3 fission following 3 fission i product barrierst. product barriera: product barriera, ,

with an imminent loss j i ,

of the 3rd fission product barrier:

e 1) Cladding: 1) Claddings 1) Cladding:

grab sample >300 grab sample > 300 grab sample >300 uci/cc equivalent uci/cc equivalent uct/cc equivalent of 1-131 of I-131 of I-131 e

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

, 71.69 psig dry- >1.69 psig dry- >1.69 paig dry-well pressure and well pressure and well pressure and ,

<-129 inches <-129 inches <-129 inches ,

Reactor Vessel Level Reactor Veadel Level Reactor Vessel Level

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

a) > 45 paig Contain- a) >45 peig Contain- .a) >45 peig Contain-ment pressure-, or ment pressure, or ownt pressure, or b) >340*F drywell b) >340*F drywell b) >340*F drywell temoc ra tu re, or temperature, or temperature, or c) >275*F wetwell c) >275"F wetwell 'c) 7275*F wetwell air temp., or air temp. , or air temp. , or d) >200*F wetwell d) >200*F wetwell d) >200*F wetwell water temp. wa ter t emp. , or ' water temp., or e) Loss of Primary e) Loss of Primary Containment Containment integrity when integrity when Containment Containment integrity is integrity is required. required is. i l

6 mmn

ATTACllHENT A LZP 1310-1

K*VISIU" I

. f LSCS EHERCEh 3F ACTION LEVEI.S January 19, 1982

8 16 SITE CENERAL CONDITION UNUSUAL EVENT ALERT EMERCENCY EHERCENCY l.

16) loss of Primary 1) ECCS Initiation A > 50 gpm leakage 1) A > 500 gpm l Coolant (Not spurious) increase in a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months leakage increase {

examples: period as indicated in a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months !

a) Loss of F.W. by monitors

or period as ,

b) Loss of Con- totalizer. indicated by i densate monitors *

2) A Hain Steam i

2) Failure of a Line Break Primary System ,

Outside Con- q Safety Valve tainment without to close as isolation (HSIV

- indicated by closure) as po'aition in- indicated by dication. the following

. alarms: HS line area temp 111; Main steam i line flow high. - l

Honitors are: Primary Containment sump flow monitors; or air coolers condensate flow rate monitors -

17) Fuel llandling Standby gas treatment Standby gas treat-Accident system operable ment system not I

(Report of damage operable .,

to irradiated fuel .

assemblies and !

fuel pool exhaust l monitor >100 mR/hr) t i

'~

~

l ATTACilitENT A LZP 1310-1 f Revision 1 LSCS EMEttCENCY ACTION I.EVELS January 19, 1982 17 ,

I l ;

SITE CENERAL ,

CONDITION UNUSUAL EVENT ALERT EMERCENCY EMERCENCY I

f l

t

l 18) Radiation Releases 1) Caseous Effluents 1) Caseous Effluents l) Caseous Effluents 1) Caseous Effluenta l Froin the Plant 10CFR20 instantaneous > 10 times the Effluent monitors Effluent monitors l l

release limits 10CFR20 instantaneouo detect level cor- detect levels (10CFR20.105) are i release limits responding to corresponding to l exceeded as measured (10CFR20.105) as > 50 mRjhr >l Rem /hr whole by the vent stack measured by the (1.3x10 uC1/sec) body at the atte radiation monitor vent stack radia- for is hour or boundary. This and/or counting tion monitor.and/ >S00mRfhr condition exists ,

equipment. or counting equip- (1.3x10 uC1/sec) when: i 7

Q/u > 4.5 x 10 ment. for 2 minutes at l the site boundary where l (adverse meteor- Q= release rate j ology) in uC1/sec :

u=mean wind l ,

speed in sph or 8

Q/u >1x10 where .

Q-release rate in uC1/sec u-mean wind. j speed in meters /sec

2) Liqug Effluents 2) Liquid Effluents 2) Liquid Effluents 2)LiquidEfyluents

> l x 10 uCg/ml > 10 uC1/ml as Estimated liquid Estimated liquist,4 j but 5 1 x 10 measured by moni- release > 2000 Ci release > 2 x 10 ,

uci/mi as measured tors

and/or but 6 20,000 Ci Ci

~

I by monitors'and/or counting equipment counting equ1pment. or

~ ~ ~

Estimated 11guld j release >40 CL i but 52000 Ci i

ttonitors: Radioactive liquid waste ef tluent radiation monitors Service water ef fluent monitor i , I mus amt

LZP 1310-1,

ATTACllHENT A I Revision l' LSCS EMERCENCY ACTION I.EVELS

'l 18 l

SITE CENERAL UNUSUAL EVENT ALERT EMERGENCY EHERGENCY CONDITION l

19) Personnel injury Transportation of ,

I radioactivity con- .

taminated injured person to hospital 20)IIzzardous As a direct result of Haterials hazardous materials

a. person is killed or l t

hospitalized or esti-mated property damage exceed, $50,000.

21) Any other condi- Warrants increased Warrants activation 1) Warrants Imminent Core Helt tions of equiva- awareness on the part of Technical Support activation of Isnt magnitude to of the state and/or Center Nearsite EOF ,

thn criteria used local offsite to define the officials 2) Warrants accident category activation of as determined by environmental monitoring j Station Director.**

- . teams

Conditions that may.or may not warrant classification under CSEP include:

I

a. Incident reporting per 10CFR50.72 . ..

h. 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 contingency events per the Station Security Plan.

The Station Director may, at his discretion, categorize the above situations as CSEP emergencies, depending 9 upon the seriousness of the situation. (Refer to Section 10.3 of the generic plan for additional information).

I l

t M -- _ _. ._ . . . _ .

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m m

1 l

p ATTACt HEllT A ,yf~

January 19, 1982

. ; 19 . i i

1.SCS EHERGENCY ACTION LEVEL.S j l 22) Transportation Accident .j I

A. A vehicle transporting radioactive materials or non-radioactive llazardous t{

materiala from a Commonwealth Edison Generating station is involved in a situation in which: ,

}

1. Fire, breakage or suspected radioactive contamination occurs involving 8 a shipment of radioactive material or;

2. As a direct result of llazardous materials, !j I

- (a) A person is killed; or i

(b) A person receives injuries requiring hospitalization; or' (c) Estimated carrier or other property, damage exceeds $50,000. l 1

B. Any other condition involving flazardous material transportation j and equivalent to the criteria in Item A.

I e

S i

i 4

N m.

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PART 20

STANDARDS FOR PROTECTION AGAINST RADIATION E

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i LZP 1310-1 )

Revision 1 i

. ATTACHMENT C January 19, 1982 26 r N15 AGE IDENTIFICATION STATE Of ILLIN015 NJCLEAR ACCIDEh1 kEFOsIlhe 5YSTEM PORM

2. ACCIDENT CLA551FICAT10N 3. AEACTOR NUMBER (5) ,

1. T 5!,TE A ORESDEN F 3RA10WG00 A TRANSPORTATION ACCIDENT A DNE(1) *

(SEE ITEM #18) 8 QUA0 CITIES h 8 UNUSUAL EVENT TWO(2)

C ZION ALERT [THREE(3)

NOT APPL] CABLE 0 LA SALLE h$1TEARIAEMERGENCY E STRON GENERAL EMERGENCY TIME DATE .

4. TIME AND DATE OF INCIDENT / EVENT: ,

5. INCIDENT INVOLVES:

6. 51TUAT10N INVOLVES: 7. TYPE OF RELEASE 15 A RA010 ACTIVE G'5E(115

@NORELEASE B N0h-RADIDACTIVE GASEOUS h POTENTIAL (PC551BLE) RELEASE E hIPft]NENT(PROBABLE) RELEASE @RA010ACTIVELIQUID NON RAD]0 ACTIVE LIQUID

@ARELEASE15 OCCURRING E NON.APPLICA8LE

@ARELEASETHATOCCURRID.BUTSTOPPED.

8. RECOMMENDED PROTECT!YE ACTIONS:

h FOR INF0 MAT!DN ONLY - (UW50AL [ VENT. ALERT OR TRANSPORTATION ACCIDENT)

B PREPARE FOR P05518tE ACTION INVOLVING Tdt PUBLlt. TO INCLUDE NOTIFICATIOh, (ALERT OR SITE EMERGENCY OR TRANSPORTATION ACCIDENT)

C NOTIFY PU8LIC TO TAKE THE FOLLOWING PROTECT!vE ACTIONS. (SITE OR GENERAL [PIRGENCY OR TRANSPORTATION ACCIDENT.)

SHELTER EVACUATE 0 2 MILE RADIUS (GASEOUS RELEASE)

E I 2 5 MILES FOR THREE (3) 00WNWIN3 SECTOC (GASEQU5 RELEASE)

F J 5-10 MILES FOR THREE (3) DOWNWIND SECTORS (GASIOUS RELEASE) h I K h 0!$ CONTINUE USE OF PDTENTIALLY AFFICTED MILES (TRANSPORTATION ACCIDENT OR OTHER)

WATER IN LouuGNp)

I I PUT CATTLE UN STORED FEED IN 00WNWIND SECTOR $ OUT TO MILES.

9. RELEASE 15:

I A CONTIWING - EXPECTED OURATION OR MAGNITUDE

[ T[RMINATED - APPR01 MATE DURATION OR MAGNITUDI

20. Em or GA5tous RtuASE is. g GROUND um (i) EuvATED

11. WIND SPEED PETERS PER 5 ECONO I 2 = MILES PER HOUR NOTE: USE NOT APPLICABLE (N/A) WHERE APPROPRI ATE.

PAGE 10F 2 f

l LZP 1310-1 '

Revision 1 I

ATTACIMENT C January 19, 1982 27 (FINAL)

I 12. W1hD O!RECTION CATA (CHECK ONE. RE AD ACR055)

WIND TNARD SECT 09s AFFtcTfD WIND FROM 0(GRE($

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@... .ENE-........ 57 78-~.-~ ~~.-~W5W--.. .~.L M N

@ .. .E. ... 79 101 - -- - - . m .. ~ . ~ W m .- ~ . . M N P

-N P Q

@..- E5E ...- 102 123.---~~~~----WW..

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.. 14 7. is 8. ............. ... Nw ........ ..Q R A g .- . 55E .

@ -...- 5 .-....-.16 9 191~.-- ~~ -~ ~- .-- N -. --- -- . R A 8

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..... 25 9

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@. . Nw.. ..... 327 34 8.-.~.~.--~~ ~15E-.~v-G H J

'C

13. CURRENT OUTSIDE TEMPERATURI:'T@

8

14. WEATHER CONDITIONS (RAIN. 5NOW. 5 LEET. ETC.):

15. TEMPERATURE DIFFERENCE ( AT): A F' [ C' or f C'/100M

-I

@ ELEVATION OF TEMP. 01FFERENCE MEASUREMENT:

- 16. RELEASE DETECTED BY:

h V15bAL h SAPPLE RESULT 5 ARI:

.....-...Rf A0!NG

[ INSTRUMENTATION--...-.-..10E NTIFICAT! 0N...........

I 17 . ACCIDENT RELATED INJURIE5: A NO 8 YES @ NUPeER OF INJURIES

18. A. LOCATION OF TRANSPORTATION ACCIDENT:

.I TYPE OF $NIPMENT (NEW FUEL. SPENT FUEL. LOW WASTE. ETC.):

B.

C. TYPE OF YENICLE OR CONTAINER D. FCM OF MTERIAL BEIPG SNIPPED ( 50L10. LIQUID. GASE0us):

8 TES T it;MBER E. CECO. PEkSONNEL DISPATolED TO TRANSPORTATION ACCIDENT SCENE: A N0 w I 19. CT",ER IkFORhATION:

20. MESSAGE REPORTED ST: ittimat wt was4At aa (OUTSIDE d)

21. N.A.R.5. MESSAGE RECEIVED BY Mit Tuun MAN Hnc l

A NO 8 TES

22. MESSAGE VERIFIED:

i IF YE1, BY WHOM:

ms ciG!!Al!QF -

l

(

PAGE 2 0F 2

l LZP-1330-30 f Revision 0 i Novemoer 16, 1981 l

l TRANSFER OF WASTES FROM THE HRSS WASTE TANK AND WASTE SUMP I

i L

I l

A. PURPOSE ,

The purpose of this procedure is to delineate tne methods of transferring liquid waste from tne Hign Radiation Sampling System (HRSS) Waste Tank ana Waste Sump to eitner unit's waste collector tank or crywell equipment sump and of transferring gaseous wastes from tne HRSS Waste Gas Hold-up Tank.

B. $EFERENCES_

l. LZP 1330-29, " Sampling at the High Radiation Sampling System (Valve Operations at the HRSS Valve Control Panel)."

C. PRERECUISITES

1. The waste tank or sump must nave oeen recirculateo ano sampled in accordance with Reference 1, Step F.3, prior to transferring the liquid waste to anotner tank or sump.

2. Estaolisn communications witn the Unit Nuclear Station Operator (NS0) ana inform nim of all valves opened or closed from the HRSS Valve Control Panel, OPLC9J.

3. Prior to transferring wastes, the station Radwaste Foreman and Shift Engineer snould oe contactea to I determine where to transfer the waste and the amount to transfer.

D. PRECAUTIONS

1. A Regulatory Guide 1.3 or 1.4 release of fission I products implies extremely hign levels of

, radioactivity. Dose rates may oe high enougn to prevent entry into many areas of the plant that are normally habitaole. Rad / Chem Supervision snoulo be I contacted prior to entry into any area wnen such a release of fission prooucts is suspectec.

l l

f I LLP-1330-30 Revision 0 Novemoer 16, 1981 I

l 2

l

2. near radiation dosimetry as recommended Dy Rac/Cnem Supervision.

l 3. Wear protective clothing anc respiratory protection as recommenced oy Rac/ Chem Supervision.

l 4. Appropriate survey instruments snould oe availaole for monitoring curing this procecure.

5. The HRSS Waste Room and associated piping runs snoulo l be secured to personnel curing tne performance of enis procecure and not re-entered prior to contacting

!I Rad / Chem.

E. LIMITATIONS AND AgTIONS

1. A sample of the HRSS Waste Tank must ce analyzea prior to sending waste fluid to the Waste Collector Tank of either unit. The source inventcry of tne liquid in the HRSS haste Tank must ce made since each haste Collector Tank must ce KCpt celow 30,000 curies and the Chemical Waste Collector Tank must ce Kept oelow 100,000 curies.

2. This procedure, though intenced for use under post-accident conditions can De useo during normal operating conditions curing which the precautions listed may or may not appl y. However, normal routine sampling precautions shoula De ooservec.

F. PROCEDURE

1. At tne HRSS Valve Control Panel, OPLC9J, place the UNIT 1(2) POWER switch in tne OPERATE position.

2. To transfer the liquia naste from the HRSS waste Sump to the waste Collector Tank, proceed to SteD F.4. To transfer gaseous wastes from the HRSS waste Gas Hola-up Tank to tne Suppression Chamoer, proceea to Step F.5.

3. To transfer the liquio waste from the HRSS waste Tank to either tne Waste Collector Tank or the Drywell Equipment Drain Sump, proceed in accoraance with the following at tne valve Control Panel, OPLC9J:

a. Open the HRSS WASTE TK OUT VLV, OPS 012, anc verify the inoication snows CPEN.

O F l LZP-1330-30 l Revision 0 NovemDer 16, 1981 3 ,

b. Start an HRSS WASTE PUMP, OPS 0lPA(8), ano verify ;

the indication shows ON. l

' l' l c. Open the HRSS WASTE TK SAMPLE VLV, OPS 016, ano verify the indication snows OPEN.

f d. Allow the HRSS Waste Tank to recirculata for 10 minutes to promote mixing.

e. To transfer the liquid waste to a waste collector !

tank, open the HRSS WASTE TK TO WASTE COLL TK VLV, 1(2)PS-003. To transfer tne liquio waste to a crywell equipment orain sump, open tne HRSS WASTE TK TO U-1(2) CRYWELL EQ SUMP VLV, 1(2)PS-001. Verify tne inoication snows GPEN.'

f. Close tne HRSS WASTE TANK SAMPLE VLV, OPS 01o, and verify the inoication snows CLOSED.

g. Allow the pump to run until tne low level alarm sounds or for the duration specified oy Cnemistry Supervision or Operations, wnicnever occurs first.

h. Secure the transfer oy stopping tne HRSS WASTE PUMP, OPS 0lPA(B), and verify the indication snows STOP.

i. Close the valve openeo in Step F.3.e. Verify the inoication snows CLOSED.

Close the HRSS WASTE TK OUT VLV, OPS 012, ano I J.

verify the indication shows CLOSED.

4 To transfer the liquio waste from the HRSS Waste I Sump to the naste Collector Tank, proceea in accordance witn tne following at ene Valve Control Panel, OPLL9J:

a. Start tne HRSS WASTE ROOM SUMP PUMP, OPSO2P, anc verify the indication snows ON.

o. Open the HRSS SUMP TO U-1(2) WASTF COLL TA VLV, 1(2)PS-007, ano varify the inoication snows OPEN.

c. When the low level al ar m > sounds , secure tne liquic transfer oy stopping tne HRSS WASTE ROUM

~

11 .

LZP-1330-30 Revision 0 Novemoer 16, 1981 SUMP PUMP, OP502P, and verify tne indication shows STOP.

c. Close the HRSS SUMP TO U-1(2) WASTE COLL TK l

VLV, 1(2)PS-007, ano verify tne indication shows CLOSED.

5. To transfer the gaseous waste from tne HRSS Waste Gas Holo-up Tank to the Suppression Chamoer, proceed in accordance with the following at the Valve Control Panel, OPLC9J:

a. Request the Unit NSO to OPEN the POST LOCA CNMT MONITOR B ISOL VALVES, 1(2)CM-0218, 1(2)CM-023B, and 1(2)CM-0268, located on panel PM13J.

D. Request the Unit NSO to place the PC CNMT AIR /N MONITORING SAMPLE PUMP, 1(2)CM-03PB, control

switen located on panel PM13J in the GFF position.

c. At the Valve Control Panel, OPLC9J, CPEN the following valves:

l 1) HRSS SYSTEM AIR RETURN TO SUPPRESSION

! POOL, 1(2)CM-090.

2) HRSS SYSTEM AIR RETURN TO SUPPRESSI0a ll POOL, 1(2)CM-088, 1(2)CM-089.

E

. 3) HRSS AIR TANK TO CONTAINMENT, OCM-020.

c. Allow the Waste Gas Holdup Tank to vent to the

suppression pool until no further pressure crop ,

is noticed. I i

e. At the Valve Control P anel , OPLC9J, CLOSE rne !

following valves:

i 1) HRSS AIR TANK TO CONTAINMENT, OCM-020.

2) HRSS SYSTEM AIR RETURN TO SUPPRESSICN POOL, 1(2)CM-088, 1(2)CM-089.

3) nRSS SYSTEM AIR RETURN TO SUPPRESSION l POOL, 1(2)CM-C90. (

Inform the Unit NSO tnat the transfer of gaseous I

f.

wastes has Deen compl eteo and request tne

E . a. -

1-i' LZP-1330-30 Revision 0 Novemoer 16, 1981 5 itinaQ equipment listed in steps F.5.a and F.5.0 oe I returned to normal as required for monitoring.

6. Place the UNIT 1(2) POWER switch on the Valve Control Panel, OPLC9J, in the DFF position.

G. CHECKLISTS

1. None.

H. TECHNTCAt. SPELJMQTION REFERMCJ S,

l. None.

I I

i I

I I

I ll .

L l

l

~

"- Revision 3

' .0ctober 23,'1979 '

I' 5 AC.ACECC A LSOS ??.0CC C?2 En C 2i;T SEI C

??.CCCC15 9: [9 /33d d/ FJ nS;0N:

il ?;;;CCli?.I t CITO SCL'?.CI I l 2 E CUICAI!CNl ?dS0kk'UON !

DENC!riCT I IMOTf /DA~~E I ~NITI)l lO AU !

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! I I- I . i COL ^CCS :

I 'sN I SCC CI CODE: C.I.

S&L G.E.

By testi:g 0 hor ,

No::: ' I: dica:e by title a:d/or zu=be: the specified docv.sent eeded :: resolve deficie :7 if ;cssible.

(

I ee

t i

i LZP-1330-31 Revision 0 j

'l5 Decemcer 7, 1981

> 1 POST-ACCIDENT PLANT SAMPLE MOVEMENT i

- . . .A . PURPOSE The_ purpose of this procedure is to delineate general steps to be taken in the movement -of-all post-acci oent t_. __ _..high. radiation samples from the sample location to a

sample preparation or analysis area.~

B. REFERENCES

~ ~ ~ ~ ~ ~ ~ ~ ~ ~

1. Action Item Record (AIR), 1- 8T;3 5 8 F ----- ~ ~

"g

2. P_Ost Accident Raciation Lgvel}, Revision 1, August,

-1980. Sargent and Lundy Project 6094-00.__.__ _ . . . _. __

3. Action Item Record (AIR), 1- 8_1-4 9_S . , . _. . . _ .- - --

4- General Arrangement, P r i n t M-7..... _ -

C. PREREQUISITES

~

1. Prior to using the gantry crane for the raising and lowering of sample casks and carts, it is necessary ' - - -

to disconnect the battery charger and connect- the battery leads. Following gantry crane use, disconnect --

the battery leads and connect- the oattery charger.

~~ -

E -~ ~~~2. erior to using tne gantry crane, ensure-tne crane is operational by lowering and raising the attacheo -

~

g .

lead weight the entire oistance the sample will travel.

! 0. PRECAUTIONS

1. A regulatory Guide 1.3 or 14 release of fission

. products impl ies extremel y higr levels of radioactivity. Oose rates may be high enougn to

!g prevent entry into many areas of the plant that are

g normally habitable. Rad / Chem Supervision shoulo De (

contacted prior to entry into any area when such a releasa of fission products is suspected.

l 1

1 LZP-1330-31 ig

g Revision 0 DecemDer 7, 1981 2

2. Wear raalation cosimetry as recommended Dy Rad /Cnem Supervision.

3. Wear protective clotning and respiratory protection as recommended by Rao/ Chem Supervision.

4. Appropriate survey instruments should De availaDie for monitoring during this procedure.

5. The areas associated with the movement of nign radiation samples should be secured to non-essential personnel during the transferal of samples.

6. Novement of personnel and equipment in the pl ant under post accident conoitions should De accompanied by radiation dose rate surveys to describe a route of acceptanie dose rates.

7. The gantry crane is designed to lift onl y one (1) of the components mentioned in Step E.3. at a time.

E. L_I_MITATIONS AND_ ACTIONS

, 1. Contact Rad / Chem Supervision if any problems are

. encountered in the performance of this procedure.

i ; 2. In the event of a hostile radiological environment i in the chemistry labs, the TURB. BLOG. SAMPLE PANEL 1(2)PL13J or the FEEDWATER SAMPLE PANEL 1(2)PL40J, st.ould be used to perform the necessary sample g dilutions and sample preparation, as necessary.

l3 2

(Reference 1).

3. There are three different types of HRSS equipment I that will be li f ted by the gantry crane:

a. The HRSS Containment Air Sampling Panel (CASP) cart / cask unit, approximately 250 lbs.

b. The HRSS Liquia Sampling Panel (LSP) cask unit, approximately 1400 1Ds.

c. The HRSS Liquid Sampling Panel (LSP) cart unit, approximately 500 los.

4. This procedure is intended to provide alternate areas for sample preparation under post accident conditions, and is predicated on the criteria of Reference 2. Other areas may be used if in keeping I

11 :

e LZP-1330-31 I Revision 0 December 7, 3

1981 l

with the guidance of References 1 and 2, anc witn the approval of the Rac/ Chem Supervisor or a Healtn Physicist.

, 5. The routes referred to in this procedure nave oeen ;

checked against Reference 2 to ootain the lowest t

possible cose rates to personnel in the performance '

of this procedure.

6. The steps in Section F. of this procecure need not be followed in order, however steps within the step -

must be followed in proper sequence.

F. PROCEDURE

1. Move the samples f rom the sampilng location to the .

Auxiliary Building elevator area, 710' elevation, in accordance with the following:

5915 If the elevators are inoperable for sample movement, refer to Attachment A for alternate instructions.

CAUTION Movement of personnel and equipment in the plant llE l under post accident conditions should oe accompaniea Dy radiation dose surveys to describe a route of

g acceptable dose rates.

E '

a. Raise the samples obtained at the High Raciation Sampling System (HRSS), 692'6" el evation, to ll the 710' elevation via the spare duct space 1

5 located near col umn 15, row R on the 710' elevation utilizing the HRSS gantry crane.

o. Move the samples obtainea at a Wide Range Gas Monitor, 786'6" elevation of the Auxiliary Building, to the 710' elevation via the Aux.

Bldg. elevator.

2. Hove the samples f rom F.1 to one of the following sample preparation areas in accordance with tne ll

!m following:

!Il

L4P-1330-31 Revision O Decemoer 7, 1981 4

CAUTION Movement of- personnel and equipment in the plant under post accident conditions shoulo De accompanied by radiation dose rate surveys to descrioe a route of acceptaDie dose rates.

N9EE If sample preparation is not required, or is aole to be done at the analysis location in accordance with acceptable work practices, proceed to Step F.3.

a. Chemistry Labs, 710' elevation; most preferred.

However, the dose projections of Reference 2 show this area to present a hostile radiological I environment under post accident conditions.

If such is the case, consider an alternate area.

b. Turoine Building Process Sample Panel, 1(2)PL13J; primary alternate. Access is via the Turo.

Bldg. elevator from tne 710' elevation to tne 687' elevation. The dose projections of Reference 2 show this area to De at normal shutdown raalation levels under a post accident condition.

c. Feedwater Samplo Panel, 1(2)PL40J; secondary al ternate. Access is via the Turo. Blog.

elevator from the 710' elevation to the co3' elevation. The dose projections of Reference 2 show this area to be at normal shutdown radiation level s under a post accicent condition.

3. Transport the required samples from Step F.1 or Step F.2 to an area of low contamination, low background for radionuclide analysis in accordance with airections providea by the Rad / Chem Director or Health Physics Supervision.

CAUTION Movement of personnel and equipment in the plant under post accident conditions shoula De accompanied Dy raciation dose surveys to descrine a route of acceptacle cose rates.

E

I. -

I LZP-1330-31 I Revision 0 Decemoer 7, 5 (finall 1981 3015 If the laboratory was not able to De used for sample preparation in Step F.2, the Counting Room will also oe inaccessable for radionuclide analysis. Use tne Auxiliary Counting Room in this case.

a. Notify the Shift Engineer if a radioactive l sample is to be transported to the Auxiliary Counting Room for gamma isotopic analysis.

l b. Move any sample to De counted from the 687' or the 663' elevation to the 710' elevation using.

the Turoine Bulloing elevator. Samples from

the 786' elevation may oe transported using I the Auxiliary Building elevator.

c. Transport the sample to the 710' elevation Counting Room if tne radiological environment i s acceptabl e. If the Counting Room cannot be used, transport the sample to the 768' elevation l

Auxiliary Counting Room using the Auxiliary Building Elevator.

NOTE The Auxiliary Counting Room is located in the southeast corner of the hallway near the Unit 2 Control Room, column R-18 on General Arrangement Print M-7.

d. Notify the Shift Engineer of any radiological concerns due to the presence of the radioactive samples in the Aux il iary Counting Room.

G. CHECKLISTS

1. None.

H. TECHNICAL SPECIFICATION _REFEREN(g1 I 1. None.

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ML20041C026

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ML20041C026

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F. PROCEDURE

F. PROCEDURE

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