ML20069L002

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures Qep 160-1 Re Administrative Director,Qep 530-0 Re Exercises & Drills & Qep 200-0 Re Emergency Conditions

ML20069L002
Person / Time
Site:	Quad Cities
Issue date:	04/04/1983
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20069K973	List: ML20069K983 ML20069L002
References
PROC-830404-01, NUDOCS 8304270405
Download: ML20069L002 (36)

Text

,.

QEP 160-0

'I '

R:visien 2 l

,

• March 1983 I ID/2X,2L ADMINISTRATIVE DIRECTOR l

f. .

k 100-0

, Administrative Director Kriv. 2 03-31-83 160-1 Administrative Director Implementing Procedure Rev. 2 03-31-83 t

e I

aPPROvF.D

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MAR 31 BB3 i

Q.C.O.i n V'O 8304270405 030422 PDR ADOCK 05000254 F PDR. (final)

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/ ' QEP 160-1 e Revision 2

( -! ADMINISTRATIVE DIRECTOR March 1983 IMPLEMENTING PROCEDURE ID/20 A. PURPOSE The purpose of this procedure is to outline the method used to implement the Administrative Director duties.

B. REFERENCES

1. QEP 700-T2, Employee List.

2. GSEP Table 4.2-6.

C. PREREQUISITES

1. None.

D. PRECAUTIONS

1. None.

E. LIMITATIONS AND ACTIONS

(' ' ', 1. Responsibilities: _

v

a. To provide administrative services during a GSEP condition including food and lodging services as required.

b. To direct a clerical staff as needed during the course of an emergency.

2. Notification:

a. Initial notification by:

(1) Acting Station Director.

(a) Shift Supervisor.

(b) Senior NSO.

1 (2) Station Director.

F. PROCEDURE l 1. Coordinate'with the Station Director and the Operations Director in arranging for relief and continual manning of the station eme rgency j crews, i

' r. ,

g APPROVED V

MAR 311983 Q. C. O. S. h. 1 1

s

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QEP 160-1~ - s Revision 2 f 2. Arrange for food and sleeping facilities for the onsite employees.

3. Direct a staff in the typing of emergency procedures and interim reports during an emergency.

4. Coordinate recordkeeping efforts of the station during an emergency.

l S. Maintain a record of the GSEP related activities.

f

6. Arrange to relocate duplicator and telecopier-from service building j to the TSC.

4 G. CHECKI,ISTS -

l

1. None.

H. TECHNICAL SPECIFICATION REFERENCES i

1

1. None.

I i

i l

l

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i -

i APPROVED MAR.311983

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Q. C. O. $. M.

2-(final)

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QEP 530-0 Revision 15 March 1983 ID/2W,2X EXERCISES ~ AND DRIIIS

- 530-0 Exercises and Drills Rev. 15 03-31-83 530-1 -

Emergency Exercise Rev. 1 12-16-80 530-2.

Emergency Drills Rev. 8 12-23-82 530-3 Off-Shift Augmentation Drill Rev. 2 06-21-82 530-S1

~

Monthly NARS (ISDA) Drill ,

Quad-Cities Station Rev. 5 02-07-83 530-S2

Monthly Test of the NRC Health Physics .

Network Rev. 1 01-05-82 530-S3 Monthly Test of the NRC Emergency Notification System Rev. 3 03-31-83 f.

\ .

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,- APPROVED MAR 311983

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q- QEP 530-S3 j Revision 3 MONTHLY TEST OF THE NRC March 1983 EMERGENCY NOTIFICATION SYSTEM ID/4Z Date:

Time:

Phone I,ocation: ,

NRC Emergency Notification System Telephones to be tested are located in the Technical Support Center, the Emergency Operations Facility, the Control Room, '

and the on-site NRC office. Each of these phones is to be tested every month.

The test shall consist of the following:

Pick up the receiver and wait. The phone should automatically reach the NRC Operations Center in Bethesda, Maryland.

The test message should consist of:

This is (NAME) from the Quad-Cities Nuclear Power Station. I'm calling from our (FACILITY NAME) to test the Emergency Notification System. Please k . ', acknowledge the receipt of this message by stating your i:.itials.

INITIALS Should a test be unsuccessful, the NRC Operations Center shall be .2otified so that the appropriate actions may be taken.

SUCCESSFUL COMMUNICATIONS YES NO Signature COMMENTS i

l APPROVED MAR 311983 a

(final) i a i s

_., _ ~

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QEP 800-0

~

Revision 23 April 1983 ID/1K,1L EMERGENCY CONDITIONS l l "

^

200-0 Emergency Conditions Rev. 13 04-04-83 200-1 Classification of GSEP Conditions Rev. 3 05-05-82 200-2 Classification of an Incident Involving Hazardous Materials Rev. 2 01-22-82 200-T1 Quad-Cities Emergency Action Ievels Rev. 9 04-04-83 200-T2 .

Emergency Action Levels - Procedure Cross Reference Rev. 2 03-07-83 200-T3 Kazardous Substances Rev. 2 10-29-82 j -

1

?

APPROVED .

APR 041983

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Revision 9 QUAD-CITIES EMERGENCY ACTION LEVELS March 1983 ID/23 CONDITION UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMERGENCY Class Events in progress Events in progress Events in progress or Events in progress or l

! Description or have occurred or have occurred have occurred which have occurred which

• which indicate a which involved involved actual or involve actual or potential degradation an actual or likely major failures imminent substantial

.I of the level of potential substantial of plant functions core degradation or safety of the plant. degradation of the needed for protection melting with potential level of safety of the public. for loss of containment of the plar.t. integrity.

r f

~

i

1. Aircraft lepacted on-site (1) Impacted on-site' ,

" ' Impacted on-site ,

, crash or and equipment and_ equipment described /, ,

missiles described,in the ..-  ; in ,the jechnical / f, from Technical S liecifi- ' Specifications is ,  ;

whatever cations is affected degraded such that source. such that it is

'an immediate shutdown

-  ! operated in a ~is required.

• ' ' degraded mode APPROVED

~

', permitted by a '

I

' 1,PR 04 283 4.,

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y Limiting Condition for operation. ,g '

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2. Contro1 s v < Evacuaiion is Evacuation is required /

, Room C ' [] /

j (' anticipated or and control is not '

[ ~' established from

^l Evacudrion "i

-. c aiquired with control

" + established,from local stations within

, , y rj .

e, local ytations. 15 minutes. ,

,> t + ,

c.

In addition to the Unusual Event, Alert ? Site Emergency, and General Emergency, a Transportation Accident class exists.

~

[ A Transportation Accident condition shall exist if any vehicle transporting radioactive materials or nonradioaca ive ~ >

han rdous materials from a generating station is involved in a situation which could possibly breach or has, breached-the integrity of a shipping container (s). <

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, QUAD-CITIES EMERGENCY ACTION LEVELS Revision 9 I CONDITION UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMERGENCY 1

3. Earthquake Earthquake felt in plant Equipment described Equipment described had occurr- or detected on in the Technical in the Technical j

1 3

ed or Station seismic Specifications is Specifications is I is degraded such is being instrumentation. affected such experienced that it is operated that an immediate l in a degraded shutdown is f mode permitted by required.

1 a Limiting Condition

-j for Operation.

2 1

4. Unplanned On-site and equipment On-site and equipment i explosion. described in the described in the Technical Specifications Technical Specifications i  ! is affected such that it is degraded such that an i is operated in a degraded immediate shutdown is mode permitted by a required.

Limiting Condition for Operation.

5. Fire. Requiring off-site Equipment described in Equipment described in assistance. the Technical Specifi- the Technical Specifi-cations is affected cations is degraded such that it is operated such that an immediate in a degraded mode shutdown is required.

permitted by a Limiting Condition for Operation.

6. Flood Mississippi River Hississippi River level > 588 ft. HSL. level > 589 f t. MSL.

APPROVED APR 0 41983 0.c.o s.g

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, QEP 200-Tl Revision 9 9 QUAD-CITIES EMERGENCY ACTION LEVELS i

> CONDITION UNUSilAL EVENT ALERT SITE EMERGENCY GENERAL EMERGENCY i

{ 7. Security Security threat An ongoing security Security threat Security threat (event)

{ threat (event) which also threat (event) of (event) involving involving a loss of

' poses a radiological increasing severity, an imminent loss physical control of j threat, or has the or a different of physical co,ntrol the facility. ,

potential for threat, which of the facility.

-j substantial degrada- involves actual

.j tion of the level or potential l of physical security substantial degrada-at the station. , Lion of the level

! (See generic GSEP of safety of the j Section 9.3.2.) station from either

! the radiological or i physical security

< view point.

l

-l 8. Tornado or (1) Tornado near (1) Tornado strikes (1) Sustained winds i severe winds facility. facility. of > 110 mph and being (a) Control Room (2) Sustained winds both unite not .

experienced. informed by Load of > 95 mph. in cold shutdown.

Dispatcher or (b) Control Room informed by station personnel who have made visual sighting or (c) Shift Supervisor informed by Weather Alert, or I

(2) Sustained winds ,

of > 80 mph.

APPROVED APR 0 41983 Q.0LOl.S.k.

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-j QEP 200-71 .

t QUAD-CITIES EMERGENCY ACTION LEVELS Revision 9

-1

+

CONDITION UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMERGENCY i

] 9. Toxic or Uncontrolled release Uncontrolled release Uncontrolled release uncontrol- of toxic or uncontrolled of toxic or uncontrolled of toxic or uncontrolled

}

i led flam- flammable gas at life flammable. gas at life flammable gas at life' mable gas threatening levels threatening levels threatening levels (Chlorine, near or on-site. within the protected within the vital areas.

l Ammonia, area.

Methane, etc.)

10. Loss of Loss of all of f-site Loss of all off-site Loss of all off-site j AC power. power to a unit og loss power to a unit and power to a unit and

of all Diesel Generators loss of all diesel loss of all diesel

'1 associated with a unit. generators associated generators associated I with that unit. for with that unit for l . I 15 minutes. > 15 minutes.

i

~!

11. Loss of DC power sources Loss of both Loss of both 125 VDC l DC power. as described in the 125 VDC and 250 VDC and 250 VDC battery Technical Specifica- battery $ 15 minutes. systems > 15 minutes.  !

tions are degraded such that a Limiting Condition for Operation requires a shutdown.

.f I

APPROVED APR 0 41983 .

Q. c. O. s. R. ,

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b QEP 200-Tl s QUAD-CITIES ENERGENCY ACTION LEVELS Revision 9 CONDITION UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL ENERGENCY

12. Plant Shutdown (1) Loss of all (1) Loss of all systems i i Functions. systems capable capable of maintain-of maintaining ing hot shutdown or cold shutdown. (2) A transient requiring

- (2) Failure of the Reactor operation of ECCS with Protection System failure to SCRAM. ,

j Instrumentation to 1 initiate and complete l a SCRAM which brings

'l i the reactor suberitical once a limiting safety system setting, as 1 1

specified in

' the Technical Specifications,

'. has been exceeded.

(ATWS)

13. Other (1) Equipment described (1)' Equipment described Unplanned loss of most conditions in the Technical in the Technical or all annunciators on .

either panel 901-3(90'-3)

~

Specifications is 2  !

or systems Specifications is or 901-5(902-5) for '

I required by degraded such that a degraded beyond Technical Limiting Condit' ion the Limiting Conditions greater than 30 minutes, Specifi- for Operation requires for Operation (as and a plant transient cations (such .a shutdown. specified that require has initiated or is in as ECCS, (2) Loss of communi- a shutdown). progress.

fire pro- cations or instru- (2) Technical i.

tection mentation such that Specificatioe il system, . accident assessment Safety Limit etc.) or off-site dose exceeded. .

assessment cannot (3) Unplannned loss of be made. most or all annunciators on either panel 901-3 AP PRCn/E D (902-3) or or 901-5 (902-5) for greater than , ,

3 "ia"'*S-APR 041983 Q.c.o. s. a i

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i QEP 200-Tl .

+

QUAD-CITIES EMERGENCY ACTION LEVELS Revision 9  !

b CONDITION UNUSUAL EVENT ALERT SITE ENERGENCY GENERAL EHERGENCY __

j 14. Loss or' (1) ECCS Initiation (1) A 1 50 gpm . (1) A 1 500 gpm Imminent core melt.

, Primary (not spurious). leakage rate leakage rate Coolant (2) Failure of a increase as increase as

Primary System indicated by indicated by Safety or Relief surveillance. surveillance.

'l (2) A main steam.line Valve to close. (2) A main steam line '

j (3). Total leakage rate break outside break outside' ,

, , to primary containment containment with containment without is greater than 25 gpa. automatic the capability of

- isolation. (FSAR effecting

, section 14.2.3) isolation.

(3) Circumferential i . break of a reactor .

coolant recircu-

lation line.

' (LOCA; FSAR t Section 14.2.4.)

i i

15. Fuel Handling Standby gas treatment Standby gas treatment j Accident. system operational system not operational i (Fuel Handlers and secondary contain- or secondary contain- ,

report damage to ment isolation ment isolation irradiated fuel effective or capable incapable of being assemblies and of being effected. effected.

Refuel Floor ARM (Refueling accident;

, reads 100 mr/hr.) FSAR Section 14.2.2) l l

l l APPROVED l

APR 041983 Q.C.O.S H d i

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QEP 200-71 t I QUAD-CITIES ENERGENCY ACTION LEVELS Revision 9 1

t CONDITION UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMERGENCY t

j 16. Loss of Coolant activity A. > 2 x 102 R/hr A. > 4 x 102 R/hr A. >2xlos R/hr fission sample > 5 uCi of primary contain- primary contain- primary contain-product I-131 dose equi- ment. activity, or ment activity, or ment activity, and j

barriers. valent per gram B. Loss of I of the B. Loss of 2 of the potential loss of l

' of water, following 3 fission following 3 fission primary containment, i product barriers: product barriers: or i

(1) Cladding: grab (1) Cladding grab B. Loss of 2 of the

{

sample > 300 pCi/cc sample > 300 pCi/cc following 3 fission

) equivalent of equivalent of product barriers,

• I-131. (Control I-131. with an imminent

. Rod Drop Accident; (2) Reactor coolant loss of the 3rd

.' FSAR Section sys: > +2 psig fission product

, , 14.2.1) drywell pressure barrier:

l (2) Reactor coolant & < -59 inches (1) Cladding: grab sys: > +2 psig vessel level. sample > 300 pCi/cc drywell pressure (3) Primary Containment: equivalent of I-131.

& < -59 inches (a) > 56 psig (2) Reactor coolant vessel level. ment pressure, or sys: > +2 psig (3) Primary (b) > 281*F contain- drywell pressure Containment: ment temperature. & < -59 inches (a) > 56 psig (c) Loss of primary vessel level.

containment containment. (3) Primary i pressure, or integrity when Containment: h (b) > 281 F required. (a) > 56 psig containment containment temperature. pressure, or ,

(c) Loss of pr', mary (b) > 281*F containment contaitunent integrity when temperature.

required. (c) Loss of primary containment integrity APPROVED when re9uired.

APR 041983 Q.C.O. S H __

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l QEP 200-T1 s l ,

QUAD-CITIES EHERGENCY ACTION LEVELS Revision 9  !>

CONDITION UNUSUAL EVENT ALERT SITE EHERGENCY GENERAL EMERGENCY

17. Radio- A. Gaseous Effluents: A. Gaseous Effluents: A. Gaseous Effluent: A. Gaseous Effluent:

i activity Technical Specifi- Effluent release Effluent monitors Monitors detect Effluent cation instantaneous > 10 times the detect levels levels corresponding-release release limits Technical Specifi- corresponding to to > 1 ren/hr whole from the exceeded as cation > 50 nr/hr (1.3 x body at the site

{ plant. measured by instantaneous 107 pci/sec) for 1/2 boundary. This i effluent radiation release limits as hour or > 500 mR/hr condition exists

! monitoring and measured by (1.3 x los pci/sec) when:

7 counting radiation for 2 minutes at the Q/U > 4.5 x 10 instrumentation. monitoring and site boundary, where l counting' instrumentation (Adverse Heteorology.) Q = release rate in i

j' (1) Noble Gases - (1) Noble Gases - pci/sec (a) Hain Chimney: (a) Hain Chimney: U = mean wind speed Unit I or Unit 2 Unit 1 or Unit 2 in sph (not both) (not both) OR 3 Release rate Release rate Q/U > 1.0 x lo s

! > 2.1 x 105 pC1/sec '> 21 x 105 pCi/sec where i

Ey EY Q = release rate in Both Units 1 and 2 Both Units 1 and 2 pci/sec

. . Release rate Release rate U = mean wind speed 2

> 2.6 x 105 pCi/sec > 26 x 105 pCi/sec in meters per second Ey Ey

' (b) Reactor Bldg (b) Reactor Bldg Vent Stack: Vent Stack:

Release rate Release rate

> 2.3'x 104 pCi/sec > 23 x 104 pCi/sec i 1.3Ey

• Ep 1.3Ey + Ep where: Ey = average gamma energy per disintegration (HeV/ dis).

EP = average beta energy per disintegration (HeV/ dis).

These quantities are determined monthly and are prominently posted in the Control Room. ,

AFR 041993 Q. C. O. h e

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I QEP 200-71 QllAD-CITIES EMERGENCY ACTION LEVELS Revision 9  !,

4 I i 1 CONDITION UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMERGENCY i -

2

- 17. (Cont.) (2) Iodine and (2) Iodine and Particulates - Particulates - f l Summation of Summation of 3-release rate for release rate for halogens and halogens and particulates with particulates with half-lives > 8 days: half-lives > 8 days:

7.3Qv + 2.6Qc > 10 2

} 7.3Qv + 2.6Qc > 10 1 .

where

Qv = release rate frca the reactor i building vent stack in pCi/sec.

3 Qc = release rate from the main chimeny in pCi/sec.

f I

B. Liquid effluents B Liquid effluents: B. Liquid effluents: B. Liquid effluents:

I concentration of: (1) Concentration of Estimated activity Estimated activity

.j (1) Gross beta activity gross beta activity of liquid release of liquid release l' (above background) in the discharge is > 2000 Ci but is > 2.4 x 104 ci.

in the discharge bay > 10 times the $ 20,000 Ci.

i bay in excess of Technical Specifi-i , the Technical cation Limit f Specification (> 1 x 10 s peif,g)

'i' limit (> 1 x 10 ~7 unless discharge is i pci/ml) unless controlled on a discharge is radionuclide basis controlled on a in accordance with f radionuclide basis Appendix B Table II in accordance with Column 2 of 10 CFR Appendix B, Table II, 20,and note I thereto.

Column 2 of 10 CFR 20 OR and note I thereto. (2) Estimated activity

, of liquid release APPROVED

> 40 Curies but

$ 2000 Curies.

APR 041983 Q.C.O.S.R 3

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l QUAD-CITIES EMERGENCY ACTION LEVELS Revision 9 CONDITION UNUSUAL EVENT ALENT SITE EMERGENCY GENERAL EMERGENCY

, 18. Personnel Transportation of l Inj u ry radioactivity contami- ,

1 nated injured person 1 to hospital.

19. Hazardous As a direct result of (1) Warrants Warrants activation i-

, Materials hazardous materials a precautionary of emergency centers person is killed or activation of the and monitoring teams,

' TSC and placing or a precautionary hospitalized or estimated property the, EOF and other notification to the damage exceeds $50,000. key emergency public near the site.  !

personnel on l standby.

(2) ARM readings (s) indicate a severe degradation in the '

control of radio-active material.

I 20. Any other Imminent core melt.

Warrants increased conditions awareness on the of equivalent part of the state -

and/or local of f-site magnitude to

, the criteria officials.

used to define the accident as ~

I determined by APPROVED Station Director *

• Other emergency conditions that require an emergency response are those involving: APR04F1983

a. Incident reporting per 10 CFR 50.72. .

b. Hazardous material incident reporting per P.A. 79-1442. V CL OL S. g ,

c. Oil discharges to waterways per *the SPCC Plan.

2 d. Security contingency events per the Station Security Plan.

The Station Director may, at his discretion, categorize the,above situations as GSEP emergencies, depending upon the seriousness of the situation. (Refer to Section 9.3 of the generic plan for additional informaCion.)

(final)

J

" ^

QEP 310-0 Revision 12 March 1983 ID/2Q,2R NOTIFICATION OF

. , . RESPONSIBLE AUTHORITIES 310-0 Notification of Responsible Authorities Rev. 12 03-31-83 310-1 Initial Notification Rev. 5 03-31-83 310-T1 Guidance for Augmentation of the On-Site Emergency Organization within 30 Minutes Rev. 5 05-26-82 310-T2 State of Illinois Nuclear Accident Reporting System Form Rev. 1 04-01-81 310-T3 Prioritized Notification Listing Rev. 6 03-07-83 3

e A P P RCh/ED MAR 311983

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( QEP 310-1 1

) \

INITIAL NOTIFICATION Revision 5 March 1983 i ID/2R A. PURPOSE The purpose of this procedure is to outline GSEP responses and the initial-notification of offsite authorities for emergency conditions.

B. REFERENCES -

1. 10 CFR 20.403.

2. 10 CFR 50.72.

3. ED-17.

4. QEP 310-TI.

5. QEP 320-1. \i i

"\

6. QEP 440-1.

7. QEP 310-T2.

C. PREREQUISITES s .

.) 1. None. .

\ _ _ _

D. PRECAUTIONS

1. When making initial notifications to any agency or control center for purposes of classifying, upgrading or downgrading an event, the following should h used as a list of minimum information that should be transmitted.

a. Naeeandtitleofthereportingperson.\

b. I,ocation and type of incident (i.e. , the emergency classification).-

c. Date and time of incident.

d. Whether a release of radioactive material is taking place.

e. Potentially affected population and areas.

i

f. Whether protective measures may be necessary.

i i

i i APPROVED

, MAR 311983 i i

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QEP 3'o0-1 l Revision 5 f' 2. If verification of the authenticity of a notification is requested by outside agencies, suggest a call back using outside phone lines but do #

not provide outside phone number information.

NOTE APPROVED 4 Once the NRC is notified of a GSEP condition, Nb4R 311983 a continuous communication channel with the-i NRC Operations Center shall be maintained Q C* 0 O* "-

, open and shall close only when notified and i

concurred with by the NRC.

E. LIMITATIONS AND ACTIONS

1. Forward completed Nuclear Accident Reporting System (NARS) form to the GSEP Coordinator upon termination of GSEP condition.

I F. PROCEDURE '/

H

1. GSEP responses. [

i

a. Transportation accident.

(1) Declare transportation accident condition.

(2) Notify the System Power Dispatcher, using the Nuclear Accident Reporting NARS Form shown in QEP 310-T2. Instructions on the .,, l use of this form are contained in F.2.b.(2) of this procedure  :

. and ED-17!

(3) Notify GSEP station group in accordance with QEP 310-T1 and QEP 320-1. o1 (4) Notify the NRC Operations Center. If call is made on the ENS (red) pho'ne, FRC Region III may also answer. If NRC Region III does not' answer, NRC Operations Center will contact NRC Region III.

(5) Dispakch personnel for evaluation if deemed necessary.

(6) Notify appropriate local agencies as needed (i.e., fire departments, hospitals, etc.)

b. Unusual event.

(1) Declare an unusual event condition.

(2) Notify the System Power Dispatcher, using the Nuclear Accident

- Reporting (NARS) Form shown in QEP 310-T2. Instructions on the l use of this form are contained in F.2.b.(2) of this procedure j and ED-17.

s (3) / Notify GSEP station group in accordance with QEP 310-T1.

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. QEP 310-1 R1 vision 5

'(4) Notify the NRC-Operations Center. If call is made on ENS p)-

phone, NRC Region III may also answer. If NRC Region III does not answer, NRC Operations Center will contact NRC Region III.

(5) Notify appropriate local agencies as needed (i.e. , fire departments, hospitals, etc.)

c. Alert.

(1) Declare alert condition.

(2) Notify the System Power Dispatcher if Corporate Command Center is not manned. Otherwise, notify Corporate Command Center. Use the Nuclear Accident Reporting (NARS) Form shown (

in QEP 310-T2 for this notification. Instructions on the use

of this form are contained in F.2.b.(2) of this procedure and ED-17.

(3) Notify the NRC Operations Center. If call is made on the ENS (red) phone, NRC Region III any also answer. If NRC Region III does not answer, NRC Operations Center will contact NRC Region III.

(4) Activate the GSEP station group and augmentation personnel in accordance with QEP 310-T1 and QEP 320-1.

r] (5) Activate the On-Site Technical Support Center and the Opera-t/ ,

tional Supporti. Center.

(6) Notify appropriate local agencies as needed (i.e., fire departments, hospitals, etc.)

APPROVEO

d. Site emergency.

W 311983 f

(1) -Declare site emergency. pg (2) Notify the System Power Dispatcher if Corporate Command

! Center is not manned. Otherwise, notify Corporate Command

! Center. Use the Nuclear Accident Reporting (NARS) Form shown l l in QEP 310-T2 for this notification. Instructions on the use of this form are contained in F.2.b.(2) of this procedure and ED-17.

(3) Notify the NRC Operations Center. If call is made on the ENS l

j (red) phone, NRC Region III may also answer. If NRC Region III J does not answer, NRC Operations Center will contact NRC

! Region III.

(4) Activate the GSEP station group and augmentation personnel in i accordance with QEP 310-T1 and QEP 320-1.

l j ,

(5) Activate the On-Site Technical Support Center and the Opera-i i tional Support Center.

t .s

- _ - _ . . . - . . _ . . _2 ~ .

QEP 310-1 -

• Revision 5 l

(6) Dispatch personnel for environs monitoring, if required. .

I (7) Notify appropriate local agencies as needed (i.e., fire departments, hospitals, etc.)

e. General emergency.

(1) Declare a general emergency.

(2) Notify the System Power Dispatcher if Corporate Cormaand Center is not manned. Otherwise#-notify Corporate Conumand Center. Use the Nuclear Accident Reporting (NARS) Form shown in QEP 310-T2 l for this notification. Instructions on the use of this form are contained in F.2.b.(2) of this procedure and ED-17.

NOTE In the case of a General Emergency, the responsible state and local governmental agencies are to be notified within 15 minutes after declaring the condition as a General

,L Emergency. The necessary time should be taken to accurately determine the condition j of the emergency, and once the condition is officially declared, the Red Phone and,NARS Phone notifications must be completed within 15 minutes. It is not prudent, however, to use excessive amoun E of time to classify

. the emergency and to avoid the inevitable {

timely notifications that must be made for a General Emergency GSEP classification.

(3) Using the NARS phone, notify the Illinois ESDA and Rock Island l Comununications Center of the emergency situation and make recommendations consistent with Section 6.3 of the Generic GSEP.

Also notify the Iowa Office of Disaster Services, Clinton County EOC and Scott County EOC, and Whiteside County Sheriff and EOC.

Use the Nuclear Accident Reporting (NARS) Form for this notification. l l . NOTE e

\

The responsibility for' notifying state and local agencies of a general emergency condition is given to the Station Director. However, if the CCC or the nearsite EOF have already i been activated for a previous emergency declaration, this notification will normally

, be performed by the CCC Director or Recovery l Manager. In addition, if the state EOC is

! already activated at the time of the general i emergency declaration, the CCC Director or Recovery Manager may brief state officials APPROVED before protective action recosusendations are og 311983

! given to local authorities via the Nuclear l

Accident Reporting System. g ]

t i I

• I r7

~__ =-

, QEP 310-1

. Ravision S

-# (4) Notify tne NRC Operations Center. If call is made on the ENS

,/, (red) phone, NRC Region III say also answer. If NRC Region III does not answer, NRC Operations Center will contact NRC Region III.

(5) Activate the GSEP station group and augmentation personnel in accordance with QEP 310-Tl and QEP 320-1.

(6) Activate the On-Site Technical Support Center and Operational Support Center.

(7) Dispatch personnel for environs monitoring, if required.

QEP 310-T1 provides guidance for augmentation.

(8) Notify appropriate local agencies as needed (i.e., fire departments, hospitals, etc.)

(9) Provide plant status updates to the state and local authorities until these functions can be performed by the Command Center ,

Director.

2. Forward completed NARS form to GSEP Coordinator upon termination of -

GSEP condition.

3. Agency notifications.

4

a. Nuclear Regulatory Commission.

~ ~

'(1)' The conditions liste'd below say or may not require GSEP activation. However, any of these conditions require notifi-cation of the NRC Operations Center within one hour and identification that the report is being made pursuant to 10CFR Part 50.72.

NOTE APPROVED The Division Vice-President for Nuclear Stations or his designee and News Information h04R 311983 Services shall be notified any time the NRC e is notified pursuant to 10CFR Part 50.72. Q.C.O.s n t

(a) Any event requiring initiation of the licensee's emergency plan or any section of that plan.

(b) The exceeding of any Technical Specification Safety

'.; Limit. .

}

(c) Any event that resul'ts in the nuclear power plant not j l being in a controlled or expected condition while opera-l ting or shut down.

i

' + (d) Any act that threatens the safety of the nuclear power plant or site personnel, or the security of special nuclear material, including instances of sabotage or

attempted sabotage.

J i

j N

i .

1

_ _ . . . _ _ . _ . - _ . _ - . .__ m ,. _

, ,-. -, , , .r.. ,,---

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

QEP 310-1 '-

-'. i Revision 5 (e) Any event requiring in'itiation of shutdown of tL- nuclear

{

f~

power plant in accordance with Technical Specificatica f])

~

Limiting Conditions for Operation.

(f) Personnel error or procedural inadequacy which, during i nonmal operations, anticipated operational occurrences, j or accident conditions, prevents or could prevent, by itself, the. fulfillment of the safety function of those

' structures, systems, and components important to safety that are needed to (i) shutdown the reactor safely and l maintain it in a safe shutdown condition, or (ii) remove-residual heat following reactor shutdown, or (iii) llait the release of radioactive material to acceptable levels j or reduce the potential for such release.

)

j (3) Any event resulting in manual or automati'c actuation of 1 Engineered Safety Features, including the Reactor Protection System.

(h) Any accidental, unplanned or uncontrolled radioactive 2

' ~

release. (Normal or expected releases from maintenance or- other operational activities are not included.)

(i) Any fatality or serious injury occurring on the site and 4

requiring transport to an off-site medical facility for

treatment.

. (j) Any serious personnel radioactive contaminati_n requiring S

. IIh

. extensive on-site decontamination or outside assistance.

3

(k) Strikes of operating employees or security guards, or honoring of picket l'ines by the employees. *

(1) Any event meeting the criteria of 10CFR Part 20.403 for notification.

i -NOTE

]

Even though the requirement for 20.403(b) 4pPROVED i events is 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to NRC Region III, a one hour requirement exists to the NRC

-' ~ " ' '

Operations Center.

" ~ MAR 311983 Q.C G1 A (2) 20.403 notification of incidents.

(a) Immediate notification of NRC Region III:

i j Each licensee shall immediately notify by telephone and telegraph, mailgram or facsimile, the Director of NRC

{

i Region III Office of any incident involving byproduct, ,

source or special nuclear material possessed by him and e which may have caused or threatens to cause:

f N. s'

~n

- s' 9

_ . . . ~ _ . , . _ -

_'.__,,_ ~ . . - . - ,

i

. QEP 310-1 Rsvision 5 (3 (i) Exposure of the whole body of any individual to

'.' _/ 25 ren or more of radiation; exposure of the skin.

of the whole body of any individual of 150 ren or more of radiation; or exposure of the feet, ankles,

, hands or forearms of any individual to 375 rem or more of radiation; or (ii) The release of radioactive material in concentraticas which, if averaged over a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, would exceed 5,000 times the Itaits specified for such materials in Appendix B, Table II; or (iii) A loss of one working week or more of the operation of any facilities affected; or (iv) Damage to property in excess of $200,000.

(b) Twenty-four hour notification of NRC Region III:

Each licensee shall within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notify by telephone

.and telegraph, mailgram or facsimile, the Director of the NRC. Region III Office of any incident involving licensed material possessed by him and which may have caused or threatens to cause:

(i) Exposure of the whole body of any individual to 5 ren or more of radiation; exposure of the skin of

<., the whole body of any individual to 30 rem or more

\- of radiation; or exposure of the feet, ankles, hands or forearms ~to 75 ren or more of radiation; or (ii) The release of radioactive material in concentrations which, if averaged over a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, would exceed 500 times the limits specified for such materials in Appendix B, Table II; or (iii) A loss of one day or more of the operation of any facilities affected; or j (iv) Damage to property-in excess of $2,000.

i b. Illinois Emergency Services and Disaster Agency.

(1) Using the NARS telephone, or its equivalent, report the i information required by the ESDA Nuclear Accident Report

, Form. (See Environmental Director Implementing Procedure

, ED-17 and QEP 310-T2.)

f I

APPROVED MAR 311983

.,' . Q.c.o. s. R.

1 t)u

._ _ . _ . . _ , ._ _ _ .._ _. _ . . . - - . _ . - . . . . .-m..

-. - - - . -, n

1 I

l- QEP 310-1 Revision 5

-4 r (2) NARS Form. Using the letter designations in each of the ' '

sections of the NARS form, describe the information as follows: ~[

(a) Section 1 - Name the site affected.

(b) Section 2 - Classify accident using GSEP, its annex, and I

QEP 200-T1.

'(c)' Section 3'- Name the reactor unit affected. For. a.

transportation accident, do not specify a unit.

(d) Sections 4, 5, 6 and 7 - Self-explanatory.

(e) Section 8 (1) Specify "A" if there is no action expected of governmental officials. This would most likely occur during an unusual event but could apply to the alert or transportation accident classes. (2) Specify "B" if you advise the gover' n mental officials to prepare for future action involving the public. This is most likely to occur during an alert or a site area emergency but could apply to a transportation accident. (3) Specify "C" and indicate the recommended protective action if the public is to be involved. This is most likely to occur for a site area or general emergency and transportatien accident.

Reference I will be especially useful for estimating the

< evacuation range for a site area or general emergency.

j .- (4) Specify "L" if use of potentially affected water 3 -should be discontinued. Recommend locations for this. t} ) -

(5) Specify "M" if cattle in downwind sectors should be j put on stored feed. Recommend number of miles.

(f) Section 9 and 10 - Describe the situation concerning the status of effluent releases. Elevated releases are those from the main chimney. All other release points l are considered ground level during an accident.

(g) Section 11 Self-explanatory.

(h) Completed NARS forms are filed with the GSEP Coordinator.

l

c. Illinois Department of Nuclear Safety.

4 (1) Immediate notification:

Each licensee or registrant shall immediately notify the Illinois Department of Nuclear Safety by telephone and tele-3 graph of any incident involving any source of radiation i possessed by him and which may have caused or threatens to cause:

(a) 44 dose to the 'whole body of any individual of 25 rem or

, more of radiation; a dose to the skin of the whole body s A P P RCD / ED of any individual of 150 rem or more of radiation; or a dose to the feet, ankles, hands or forearms of any

- hu4R 311983 individual of 375 rem or more of radiation; or,

~

Q.C. O. S. It . .

__.~.....-.s . - ~

..~.;.c.-.-

. s ... . . . .--.-: -

g

,- . ~. .- - . . .

... . QEP 310-1 Revision 5

'"'. (b) The release of radioactive material in concentrations

, - <k which, if averaged over a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, would

'J~* exceed 5,000 times the limits specified for such materials in Appendix A, Table II (Appendix B of 10CFR 20); or (c) A loss of one working week or more of the operation of t any facilities aff-cted; or, (d) Damage to property in excess of $100,000.

(2) Twenty-four hour notification:

Each licensee or registrant shall within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notify the Illinois Department of Nuclear Safety by telephone and telegraph of .any incident involving any source of radiation possessed

! by him and which may have caused or threatens to cause:

(a) A dose to the whole body of any individual of 5 ren or l

more of radiation; a dose to the skin of the whole body I

of any individual of 30 rem or more of radiation; or a dose to the feet, ankles, hands or forearms of 75 rem or i more of radiation; or,

, (b) The release of radioactive material in concentrations which, if averaged over a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, would exceed 500 times the limits specified for such materials in Appendix A, Table II (Appendix B of 10CFR 20); or,

(' , . .

(c) A loss of one day or more of the operation of any facilities affected; or, (d) Damage to property in excess of $1,000.

G. CHECKLISTS

1. QEP 310-T2, NARS Form.

i H. TECHNICAL SPECIFICATION REFERENCES

1. None.

l i

l .

i

, AAPROVED 1

j f. MAR 311983 I N.l -

Q. c. o. s. n.

!(2) i ] (final) e s

_,ww va + r +=- p - + ~**~H- w- **: * *mser 'w=- ~

eu9 <m= w+sm -- e e- e rw p-y

't

_- u QEP 420-0 Rivisien 5 Msrch 1983 ID/1W,1% ONSITE TECHNICAL

,f - . SUPPORT CENTER o

1 420-0

'Onsite Technical Support Center Rev. 5 03-31-83 420-1 Onsite Technical Support Center Rev. 5 03-31-83

(

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< APPROVED 3

s. MAR 311983 C). .

i acasa (final) g 9

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h

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QEP 420-1

< ) Revision 5

1. ON-SITE TECHNICAL SUPPORT CENTER March 1983 ID/IX

~

A. PURPOSE The purpose of this procedure is to outline the method to activate and utilize the On-Site Technical Support Center during emergencies. ,

B. REFERENCES

1. GSEP Section 7.1.2. and GSEP-QCA Section 7.1.

2. NUREG 0578.

C. PREREQUISITES

1. None.

D. PRECAUTIONS

1. None.

E. LIMITATIONS AND ACTIONS

1. None. ~

F. PROCEDURE

1. The Control Room is the primary on-site location from which initial actions are taken to identify, assess, and cope with an emergency.

Once an emergency has been declared, the On-Site Technical Support Center may be activated as necessary to support the Control Room.

2. The TSC may be activated for any emergency as necessary, but must be activated for a GSEP Alert, site emergency, and general emergency.

3. The TSC is maintained for use by plant administration, technical staff, and engineering support personnel during emergencies.

4. The TSC is utilized for assessment of plant status and potential off-site impact in support of the Control Room comunand and control function, and for implementation of on-site and off-site emergency actions.

5. The TSC is located in the Southeast corner of the protected area (old

guardhouse).

{

i

, 1 i! . m. .

APPROVED l!

i V k) MAR 311983 I

Q. C. o. s. x.

l ,

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_ __7 _ _ _ . _ . _.

QEP 420-l' ' , , ' ,

Revision 3

! - 6. Plant- drawings, design information, procedures *, etc. are readily- r$

3 available in the TSC. s./

a. In accordance with NUREG-0696, the following documents are located in the TSC:

(1) Technical Specifications APPROVED (2)~ Complete set'of' Station Procedures h!AR 311983 (3) Original and Updated FSAR Q.CL O. :i K (4) Iowa and Illinois Emergency Plans (5) Current year NRC Monthly Operations Reports (plant operating

, records)

(6) Current year On-Site Review Reports (7) As built M, B, and 4E drawings (a drawing index microfiche is located in the clerk's desk)

, b. A SYFA terminal is located in the TSC that may be utilized to retrieve exposure records and environs data.

7. Adequate staffing and access control of the TSC will be as directed by the Station Director. The Station Director will direct those necessary 7' technical and management personnel to man the TSC depending on the nature and extent of the emergency. He will assure adequate technical expertise is available in the TSC to provide the necessary technical support. The Technical Director would normally report to the TSC, and would assist the. Station Director in directing the manning and access control of the TSC. The Thermal Engineer and Lead Nuclear Engineer would also report to the TSC, if available. Off-Site and NRC personnel may be directed to report to the TSC as required.

!, 8. Dedicated communications exist to the Control Room, the NRC, the EOF,

the OSC, and the CICo GSEP Command Center in Chicago, and to state and local authorities (via the NARS phone).

9. Portable direct and airborne radiation monitors are available in the TSC.' If the TSC becomes_ airborne, or if the radiation level in the TSC becomes excessive in the judgement of the Station, Director or Environs Director, the accident assessment. function of the TSC will be performed from the Control Room. Air packs or masks from the respiratory equipment issue room should be utilized as conditions dictate.

10. If the TSC is relocated to Ehe Control Room, only a limited number of persons should relocate, due to the need to control access to the Control Room. Including the Station Director and Technical Director, this number should not exceed ten. ,

11. Upoc. activation of the TSC, turn on the Eberline PING-2 monitor located -

j J

in the HVAC room. ,)

,* =~

% .,_p.m.. . - - - .--w e%++ o-w- ee v c ,s-

• g "*we,,s wm e-.. .- m w , e-+ ~~

~ - -

d . QEP 420-1 Rsvisica 5 r 12. Activate.- emergency mode of. HVAC. .

i

(-)

_,/ a. Activate handswitch HS-2 on control panel,

{

b. Activate handswitch HS-3 to stop'outside air to AHU.

13. If it is determined that the TSC must be isolated from the environment, activate the recirculation mode of operation.

a. Activate handswitches HS-2 and HS-4.

14. The charcoal adsorber is protected by a local alarm heat sensor and a manually activated deluge system.

G. CHECKLISTS

. 1. None.

H. TECHNICAL SPECIFICATION REFERENCES

1. None, f

/

m

/

f i

i 1

1 .

APPROVED I ; MAR 31 E83 i

Q. C. O. s rt 4

l w

!U

,l (final) j i 9

$ ^

i'

.. . .. - . .. ..~--.-- ~. -- .- - ,

..-m...~,..._. ._x.,,_.., . , . . . .

. . . - . - ~ ...:...-. . . . - . ~ .u.

- QEP 430-0 R2 vision 4 March 19f3

. ID/2Y,2Z ON-SITE OPERATIONAL. .

! (N SUPPORT CENTER 1 430-0 On-Site Opera'tional Support Center Rev. 4 03-31-83 I. 430-1

! On-Site Operatio'nal Support Center Rev. 4 03-31-E3 I

i 1

i 4

t i

a, . _

i 1

i I

.i i

.i t

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i c.

I I

I

_ APPROVED

. MAR 31283  !

l Q.C.O.S. it.

, (final) w .. , = . ,w.' .e ,, ..mo i. -=e e *e, ,43 e+ 9s-is**~vw^*+= e *--*- * -  %-=* m-*ev*m*' .

% *s

• ye -- m r-'

• l

. . l l

s

,/ " QEP 430-1

, Revision 4 ON-SITE OPERATIONAL SUPPORT CENTER March 1983 ID/3Q A. PURPOSE The purpose of this procedure is to outline the method to activate and utilize the On-Site Operational Support Center during emergencies.

, B. REFERENCES

1. GSEP Section 7.1.3 and GSEP-QCA Section 7.1.

2. NUREG 0578.

C. PREREQUISITES

1. None.

D. PRECAUTIONS

1. None. -

E. LIMITATIONS AND ACTIONS

[% 1. None. _.

(d ' . -

.F. PROCEDURE

1. The Control Room is the primary on-site location from which initial

• actions are taken to identify, assess, and cope with an emergency.

Once an emergency has been declared, the On-Site Operational Support Center may be activated as necessary to support the Control Room.

2. The OSC may be activated for any emergency as necessary,'but must be activated for a GSEP alert, site emergency, and general emergency.

3. The OSC at Quad-Cities Station is the meeting room , adjacent to the TSC.

4 Operations; support personnel report to the OSC during an emergency, from where they are dispatched for assignments or duties in support of emergency operations.

5. Dedicated communications exist between the OSC, the Control Room and

,to the TSC.

6. The Operations Director or his designee (Operating Engineer) will assume command of the OSC when activated. Operations personnel will man the OSC to the extent necessary, depending on the nature and scope of the emergency. Rad-Chem technicians will also report to the OSC.

. APPROVED U MAR 311983 1

Q.C 0 S.It i

\

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,y. ~- ---

~

QEP 430 [

Rsvisica 4 ' ' e'

~

7. The OSC should remain in close -communication. with the Control Room, 3

such that actions taken are coordinated and carried out properly. j

8. The OSC supervisor should coordinate the dispatching of operators and should serve as the primary consnunicator in the OSC as his prime i functions. It is his function to assure that the necessary manpower is assembled at the OSC and accounted for. He should also make use of the status board to inform all OSC personnel of the status of the emergency.

9. If the OSC becomes uninhabitable, the Operations Director or his designee will designate and activate an alternate OSC. The choice will be based on habitability and space consideration. Areas to be considered, but not limited to, are the shop area, service building meeting room, lunch room, lift station, crib house, boiler house, and filter building.

G. CHECKLISTS

1. None.

H. TECHNICAL SPECIFICATION REFERENCES

1. None.

4B GJ c

& P

, , 1 1

f' 48 PROVED ,

V MAR 311983 2-(final)

...-sw--e +=.-e -- mse --- * =

s=~~'*-s -w% ~ - ~ "- ~ -w'

-.e.. oo - ,

_ _ . . . _ -- 3

- . QEP 460-0 )

/ Rsvisien 4 l

, , . . 11:rch 1983 ID/3G,3H EMERGENCY OPERATIONS FACII.ITY

. [~.

I h.. 460-0 Emergency Operations Facility Rev. 4 03-31-83 460-1 Emergency Operations Facility Set-Up Rev. 4 03-31-83 i.

f 460-T1 Procedure Deleted Rev. 2 12-15-82 t

t t

t I

t 1

i APPROVED

\ r ~.

MAR 311983 d( )

I

,  : gaask f .r-t j (final)

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I; _ -

~

- ". 33; s

p .

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)

s. i' 4 I EMERGENCY OPV'!ATIONS harch 1983 FACII.ITY SET-UP k

i{ g ID/4X P A. PURPOSE ,

u 9

The purpose of this procedure is to aid the environs staff personnel in setting up the Emergercy Operations Facility for initial use during an emergency. s, B. REFERENCES

1. QEP 550-T4, Emergency Operations Facility Supplies. .

2. QEP 440-1, Emergency Communications Facilitics., u- .

1. 9 & g C. PREREQUISITES s ,,

1. The Emergency Operations Facility will'be initiated when deemed necessax7 's by the Station Director. ,

,( ;

+..

e

2. Upon the decision to initiate the EOF, the Environs, Director will .

, s instruct the Environs Staff to set up the. EOF.to accomodate the Enytrens ,

~

Staff's needs. The Environs Staff W111'insnediately relocate to the' ' ' k.

~

s

~

Is EOF. + t u Q 3. The Environs Director will instruct the Environs Field Teams to gather

..-

• i .

N ,

the appropriate supplies for Field Team duties, relocate 2..s directed, and await further instructions.

, '; (;.; ,

, D. PRECAUTIONS ,

1. This procedure is meant as a guide to the .Znv' irons Staff and may be . . ,

' 'g deviated from upon approval of the Environs ? irs: tor or the Rad-Chem -

Director. s.

. 2. A' key for the EOF may be obtained from the Shift Engineer. . ;w

} E. LIMITATIONS AND ACTIONS '

~ .,

,- k-

1. None. s r %,

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1 < .

i .. APPROVED i , MAR 311983

', )

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k <

1

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QEP 400-1 .

1 Revision 4 '

l l '

l

!a

', e'

F. PROCEDURE

]

1. Upon relocation to the EOF, comunuaications with the TSC should be verified using the yellow phone. A regular telephone may be used, if the yellow phone is not functioning.

, _ 2. After verifying communications with the TSC, set up the GSEP radio by- .._

connecting it with the appropriate phone jack and plugging it into an outle t'. Verify that the radio is in the " SCRAMBLE" mode, and test communications by contacting the TSC. At this time, the Environs Director may relocate to the EOF.

3. Upon arrival of the Environs Teams at the EOF, test conununications with their portable radios in the " SCRAMBLE" mode. Notify the TSC that the Environs Teams are ready to be dispatched. '

I, _- 4. Instruct one of the field teams to travel toward Iowa on a route dictated by the wind direction.

5. Tape one film dosimeter and one zeroed pencil dosimeter outside the EOF, above the main doors. Verify presence of sampling supplies and dosimetry as described in QEP 550-T4.

6. Conduct periodic dose rate and contamination surveys in the EOF and immediately surrounding area as deemed necessary by the Environs Director.

( D

7. Assist the Environs Director as necessarf. . -

(U G. CHECKLISTS y . 1. None.

, 1,  !

H. TECHNICAL SPECIFICATION REFERENCES

1. None.

y l

1

_ APPROVED l l MAR 311983 .

l N. . t)

SCGER (fina1)

_ m e ., ; .m,..~m., ;

p.m.. w.. .w.< -

- * - + -. ,

i-. +

__.