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Public Version of Revised Radiological Emergency Plan Implementing Procedures,Including Procedures IP-1 Re Emergency Plan Classification logic,IP-3 Re Alert & IP-4 Re Site Area Emergency
	ML20071E125
Person / Time
Site:	Sequoyah
Issue date:	02/09/1983
From:	Harding M, Kitts R, Jacqwan Walker; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML20071E082	List: ML20071E110; ML20071E125;
References
	PROC-830209-02, NUDOCS 8303100053
	Download: ML20071E125 (73)
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REVISION LOG SHEET l'

Revision Date: PORC December 29,1982 (Issned February 9,1983)

This log sheet must be retained as the last page of the Sequoyah Implementing Procedure Document.

Inserted by: Data Inserted:

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Pages to be Removed New'Pages to be Inserted Part Page Number Revision Part Page Number Revision

. IP-1 Cover Page Rev. 3 IP-1 ' Cover Page Rev.'4 I thru 40 Various . P. I thru 40 Rev.'4

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'IP-3 Cover Page Rev.'4 IP-3 . Cover Page 'Rev. 5 ^

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Sequoyah Nuclear Plant ~ DISTRIBUTION IC 81 Plant Master File 1C 83 Asst. Power Plant Supt. (Oper.)

SQN REP - IMPLEMENTING 1C 84 Asst. Power Plant Supt.~(Maint.) !

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PROCEDURES DOCUMENT 1C 86 Maintenance Supervisor (M) I 87 Maintenance Supervisor (E) 1C lc 88 Maintenance Supervisor (I)

SQN, IP-1 1C 89 Results Supervisor EMERGENCY PLAN CLASSIFICATION LOGIC 1C 90 Operations Supervisor

_1C 92 Health Physics Supervisor 1C 93 Public Safety Services Supv.

! a 1C 95 Outage Director -

1 1C 96 Emergency Cabinet Control Roon j

1C 97 Emergency Cabinet Communications Room IC 98 Emergency Van 4 14 102 Shift Engineer's Office Prepared By: J. R. Walker 1C 103 Unit Control Room

} 1C 105 Health Physics Laboratory i Revised By: M. R. Harding IC 106 Medical Office i ! 1C 107 Resident NRC Inspector - SNP j

i Submitted By: b 3upervisor k ~

1C 1C 108 Technical Support Center 109 Assistant HP Supervisor l

T 110 Plant Duty Supervisor j / IC 111 Asst. Power Plant Supt. (H&S) j ,

PORC Review: /M/42f/M T EP&P Sliger, Et.': K., 1470 CST 2-C i

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Apptoved By: k[-

r Plt Superintendent Date Approved: /c?.f! Af d ,

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Rev. No. Date Revised Paaes Rev. No. Date Revised Pages

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1 ) '2 6/8/81 All h. '

4 Revised 2, Added 32A,

) 3 8/26/81 32B and 32C 1

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Page 1 of 40 Rev. 4-EMERGENCY PLAN CLASSIFICATION LOGIC 1.0 PURPOSE This procedure guides the shift engineer in determing the class of an accident based on plant conditions.

2.0 GENERAL The TVA radiologicai emergency plan will be activated when any one of the conditions listed in this logic is detected. The shift engineer is responsible l for declaring the emergency and providing-the initial activation of the emer-gency plan.

s To determine the classification of the emergency, enter the logic with the known or suspected conditions and carry out the notification referenced. If there is any reason to doubt whether a given condition has actually occurred, the shift engineer or Site Emergency Director will proceed with the required notification without waiting for formal confirmation. If followup investi-gations show that a suspected condition has not occurred, is less severe, or more severe than originally suspected, the classification will be cancelled, downgraded, or upgraded as required.

The following actions are given for guidance only: knowledge of actual plant conditions or the extent of the emergency may require that additional steps be taken. In all cases,.this logic procedure should be combined with the sound

, judgement of the shift engineer and/or the Site Emergency Director to arrive at a classification for a particular set of circumstances, i

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( Rev. 4 TABLE OF CONTENTS Engineered Safety Features Page 3 Reactor Protection System Page 4 Emergency Core Cooling System Page. 5 Annunciators, Instrument and Controls Page 6 Control Room Evacuation j Page 7 Medical Page 8 Plant Physical Security Page 9 Aircraft Page 10 Train Page 11 I Explosions . Page 12 Missiles -Page 13 Fire Page 14 Gases: Toxic of Flammable Page 15 Earthquake '

Page 16 Tornado Page 17 High Winds Page 18 Flood Page 19 Low Water Page 20 Electrical: D.C. Problem Page 21 Electrical: A.C. Problem Page 22

. Page 23 Turbine Failure Steam Line Break Page 24 Steam Generator Tube Leakage Page 25 f Loss of Cooldown Capabilities ' Page 26

't Fuel.(core) Damage ~ Page 27 i Primary Coolant Leakage : Page 28 Failed Fuel Monitor Page 29

) Containment Integrity Page 30 Area Radiation Levels Page 31 Offsite Dose Assessment Page 32A, 32B, 32C Fuel Handling Incident .Page 33 q Abnormal Plant Conditions Page 34 Safety Limits Page 35 Reactor Control Rod Problem Page 36 Inactive Reactor Coolant Loop ~"

,. ;:Page 37 Baron Dilution >

^ 'Page 38

. Feedwater (Normal and Auxiliary) . .- :- Page 39 Waste Gas Decay Tanks p g ? Page 40 h; ': ,

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ENGINEERED SAFETY FEATURES Reactivity YlowPaths-Operating LCO 3.1.2.2 3

Control Charging Pumps - Operating LCO 3.1.2.4

Systems Borated Water Sources - LCO-3.1.2.6

0,,perating Instrumentation ISFActuationSystem LCO 3.3.2.1 Justrumentation- ,

. Reactor Pressurizer Safety Valves - LCO 3.4.3

, I Coolant Operating l 8 System RCS Leakage Detection System LCO 3.4.6.1 I Emergency Told Leg Accumulators LCO 3.5.1.1 4

Core UHI Accumulators LCO 3.5.1.2

Cooling ECCS Subsystems Tavg 2,350*F LCO 3.5.2 4 System Baron Injection Tank LC0 3.5.4.1 Heat Tracing LCO 3.5.4.2 Refueling Water Storage Tank LCO 3.5.5 Primary Containment LCO 3.6.1.1 1 Integrity .

[ EGTS Cleanup Subsystem LCO 3.6.1.8

Containment Spray System LCO 3.6.2.1

, Containment Hydrogen Analyzers LCO 3.6.4.1 i Systems Electric Hydrogen Recombiners LCO 3.6.4.2 Loss of ESF -

4 Ice Condenser LCO 3.6.5.1 function that. YES Ice Bed Temp. Monitoring LCO 3.6.5.2 b requires shutdown y

), System by Tech Specs j

Ice Condenser Doors Inlet Door Position MonitoringLCO 3.6.5.4 LCO 3.6.5.3 Fotification h

System of Unusual

? Containment Air Return Fans LCO 3.6.5.6 -

Evenc 1

Floor Drains LCO 3.6.5.7 NO

Vacuum Relief Valves LCO 3.6.6.1 y l Auxiliary Feedwater LCO 3.7.1.2 (N0 ACTION)

Condensate Storage Tank LCO 3.7.1.3 Main Steam Isolation Valves LCO 3.7.1.5 i Plant Component Cooling' Water Sys LCO 3.7.3.1

{ Systems Essential Raw Cooling Water LCO 3.7.4.1 ' ~

j Auxiliary ERCW~ <

~ LCO 3.7.4.2 f Control Room Emergency Vent LCO 3.7.7.1 System Auxiliary Building' Gas LCO 3.7.8.1 Treatment System

- Electrical Diesel Generators LCO 3.8.1.1 Power Onsite Power Distribution LCO 3.8.2.1 .

A-- System System LCO 3.8.2.3 125 VDC Vital _

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Rev. 4 l W ENGINEERED SAFETY FEATURES g ,

(Continued)

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Failure of reactor protection q

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system to initiate a trip,both manual and automatic, which could result in core damage, or add. failure YES

)d General Emergency l

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Transient requiring operation of shutdown systems with a YES (IP-4) id failure to trip (continued Site Area Emergency i I power generation but no core '

' damage eminent) , '

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v I Failure of reactor protection system to initiate and. complete a trip which brings the Reactor YES IP-3) t Suberitical ,

)(Alert ,

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EMERGENCY CORE COOLING SYSTEM i

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ECCS I Initiated YES m

( IP-2 )

! and dis- Notificatica charpp to of Unusual

. vessel Event j . . NO.

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- Failure of a safety or relief valve in the ECCS to YES i close following reduction > IP-2

? of applicable pressure Notification of Unusual u Event NO ACTION 8

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Page 6 of 40 l Rev. 4 )

ANNUNCIATORS, INSTRUMENTS AND CONTROLS All Alarms (annunciators) lost for more than 15 minutes and plant transient initiated or..

in progress while all alarms '

YES ( IP-4 )

Site Area lost Emergency 4 _

! NO

! V Most or All Alarms (annunciators) lost YES(IP-3 )

for more than 15 minutes' and plant is in mode 4 or

) Alert above.

NO V

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l Loss of Indication or Alarms On {

! (1)?rocess er effluent parameters f to extent requiring shutdown i per Tech Spec ACTION or, 9 (2)PAMs to extent requiring shutdown per Tech Spec ACTION OR Loss of AsseEment On YES (1) Process computers to extent requiring shutdown per

% (lE=2.)

shift supervisor (SRO) Notification of decision or, Unusual Event

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. (2) A loss of ALL Meteorological i Instrumentation, Local and

- Remote, listed in Instrumen-

, tation section of the Tech

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. NO ACTION 4

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SQN, IP-1 Page 7 of 40 Rev. 4 CONTROL ROOM EVACUATION YESi Control established Q YES Evacuation of Control within 15 minutes Room anticipated or required with control ,

( IP-3 )

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Alert of shutdown systems to to NO i established from local

.' systems '

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.. ( IP-4 7 Site' Area Emergency

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SQN, IP-1 Page 8 of 40 1 Env. 4 l 3 MEDICAL i j <

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Transportation of contaminated injured individual from site to YES IP-2 )

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offsite hospital

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{ SQN, IP-1 Pga 9 of 40 i

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1 PLANT PHYSICAL SECURITY I Loss of Physical )

Control of the Facility ~YES)(IP-5

' General Emergency i -

NO 1

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Imminent Loss of l

! Physical Control of Yes IP-4 )

i the Plant Site Area Emergency i

NO Ongoing Security )

Compromise '

YES)(IP-3 Alert NO V

Security Threat or Attempted entry or YES ( IP-2 )

, Attempted Sabotage- Notification of

! Unusual Event NO (NOACTION) i 4

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Page 10 of 40 Rev.y .

AIRCRAFI .

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YES (IP-4 )

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Site Area Emergency plant not in cold shutan i NO 4

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l Aircraft crash on facility YES (IP-3 )

, Alert i

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\ Aircraft crash on-site or l

unusual aircraft activity over facility '

YES q ( IP-2 )

j / Notification of Unusual Event 1 .

NO

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i (NOACTION)

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s SQN-IPD SQN, IP-1 Page 11 of 40 Env. y TRAIN Train Derailment )

l On-Site -

YES)(IP-2 Notification of 3

Unusual Event

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NO V

(NOACTION)

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Rev. 4 I EXPLOSIONS f

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A Severe Damage to Safe k

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Shutdown Equipment From 1

Explosions gYES ) ( site

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plant operation.

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YES (IP-*, )

/ Site Area Emergency 4 -

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FIRE

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Site Area Emergency 4

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' Bav. 4 l j GASES: T0XIC OR TLAMMABLE

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Entry of*uncontrolleditoxic or flanzable gases into YES ( IP-4 )

vital areas.where lack of I Site Area Emergency h Access "to the area c6nstitutes-i a safety problem i NO .

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V Entry into facility environs of uncontrolled YES IP-3 )

l l-toxic or flammable, gas '

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EARTHQUAKE Earthquake > SSE w/ pit not in Cold S stdn N (~> .18G Horizontal YES (IP-4 )

> .12G Vertical) ~

Site Area Eme:gency N0 s

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> .09G horizontal and (F .06G vertical but YES IP-3 )

{ .18G horizontal and < .12G vertical)

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Any earthquake 1

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YES)(IP-2 Notification of Unusual Event i

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TORNADO 4

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Any tornado striking )

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facility YES)(IP-3Alert

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, SQN-IPD SQN, IP-1 j Page 18 of 40 Rev. 4-f i

HIGH WINDS t

! Winds in excess of

, design levels with )

j plant not in cold shutilown (7 95 mph)

YES)(_IP-4 Site ' Area Emergency

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NO V

Hurricane winds near 4

design basis level YES IP-3 )

(> 85 mph but < 95 mph) '

h(Alert 4 : _

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' Rev. 4 FLOOD i

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!- ;.. Failure of a flood barrier for protection of vital YES IP-4 )

equipment during flood ' )(Site Area Emergency l ; conditions with plant not j in cold shutdown 4

NO V

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Flood greater than design levels (> el. 723.1)

YES ( IP-4 )

l Site Area E ergency

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I Date is Oct. 1 - Apr. 15 YES IP-3 )

J river level > el.697 but < 723.1

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Flood near design levels

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1 l Date is Apr. 16 - Sept. 30 river level > el. 703 -

but < 723.1 YES)(IP-3 Alert i

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- LOW WATER 1

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1 l

River level less than -

desian levels with plant not in cold i YES (IP-4 )

shutdown -

Site Area Emergency 4 .

i NO

! V Los river level near design level )

(> el. 665 but

< el. 670) -

YES)(IP-3 Alert

> NO 4

V Low river level )

r ~

i

(> el. 670 but < el. 673) i YES)(IP-2 Notification of Unusual Event NO 4 V (NOACTION) -

3

( &

I~ <

-- ' I I'

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' E' I

l lf' ,

i

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l I -

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. . . _ - .. . .+ -- -

-, , - , , , - . , . - , - ,. , , - - - - - _ , - - .-,,--,-.,,,--.n .--w

SQN-IPD

SQN, IP-1 Page 21 of 40 Rev. 4 i .

ELECTRICAL: DC PROBLEM Loss of all 125 VDC vital-battery boards for > 15 minutes YES IP-4 )

3

)(Emergency Site Area 4 .

NO V

Loss of all 125 VDC YES ( IP-3 )

battery E rds '

Alert V "o (NOACTION)

b 4 .I i

) .

i .

I 4

1- 21 i

l.

- . n =** % = e- -.m. -

y

, , , . , . , - - - , - - , - , - - - ,-9-.--m 7 -w, ---m , - , , , . . _ , _ _ _ ,,,y ,, ,, , -.,n- ,,,,,g--- we,-.,. ,--em&,--.y,.--,----yw-

l SQN-IPD

. SQN, IP-1 Page 22 of 40 Eev. 4 1

ELECTRICAL: AC PROBLEM l

Loss of all onsite and offsite power with total loss of aux '

YES ( IP-5 )

General Emergency

, feedwater'/ 15 minutes ,

1 N0 f4 -

I i Loss of offsite power and loss of onsite AC power for 15 minutes '

YES IP-4

)(SiteAreaEmergency

)

l l

t NO y

Loss of offsite power and )

loss of all onsite AC power YES ( IP-3 i

~

i. .,

NO

! Loss of offsite power or 4 loss of onsite AC powe T capability i YES ( IP-2 )

4 Notification of

; Unusua'. Event NO l v .

! , (NOACTION)

. l S

i; l

i I

+

l l

22 l

l

! l I

c: . . .

SQN-IPD

SQN, IP-1 Page 23 of 40 Eav. 4 J

TURBINE FAILURE i

Turbine failure causing )

{

1 casing penetration ' YES)(IP-3 Alert NO v.

1 p(hW h) h d Turbine rotating component YES IP-2 failure canaine ranid clant '

1 shutdown l nusud Went NO (NOACTION) i y .

i .

i 1 .

e*

1 .

4

k. 23 -

l

. . . ~ , -

.*w,ne

_.. - , _ - 4y- --- --w .---g ,,, __p. - -- ,_--- - , ._g. - . - emm-.--..--.r_,y--9 .,

4

, SQN-IPD SQN, IP-1

, Page 24 of 40

. Rev. 4 STEAMLINE BREAK-Steam line break with > 50 gpm primary to secondary leakage YES IP-4 )

and indication of fuel damage i )( Site Area E:narge l

i V" -

I ! Steam line break with > 10 gym primary to secondary leak YES IP-3 )

rate ...-

. .an '

)(Alert i

e

, y NO 2

~ Failure of a safety or relief valve to close resulting in a C 10 "" '

YES ( IP-2 )

1 Notification of 1

3

, Unusual Event i

l NO I

y.

{

Rapid depressurization of secondary plant i Yes ( IP-2 )

Notification of,,,

, 4 Unusua1 Event y NO (NOA,CTION)

I t

es, 24

~

I . ,

1 I l

. . . ~ . . . . _ . ...._. .

L _ _ . . . .. . . . - - . - . . . ..

k

- - . - , - - - - . - - - - . - . - , - - - . , _ - _ . . . . . --,.,__._.,,,,.-,,-,,n.- , , . , . , - . , , , ,

6

" .' SQN-IPD

, SQN, IP-1 Page 25 of 40 Rev. 4 STEAM GENERATOR TUBE I.EAKAGE

' Failure of steam generator -)

YES)(IP-4 i

tubes, resulting in 7 1000 . Site Area Emergency gPm leakage, with loss of offsite power , ,,,

4 5

NO 1 V i.

Failure of steam generator tubes resulting in > 1000 )

gpm leakage i YES)(IP-3 -n,g NO i -

V i

l Failure of steam generator tubes, resulting in > 400 IP-3 )

gpm leakage, with loss of..

offsite power i

YES)(g, 4

J NO i V -

i Exceeding primary to secondary

{ 1eak rate. tech spec i

YES ( IP-2 )

(1 gPm total primary to Notification of secondary leakage through Unusual Event all steam generators and 500 gal / day through any one stearr. generator) -

! (NOACTION) s 25 1

i I

. . + . .

y .-,, - --- ,, ,-- -

w- ,-,- ,.,y- - . - , - - - - - - - - - . - w,,w,-,-- w.,,w , , - , , ,- ,-,,-------e,

. SQN-IPD i SQN, IP-1 l Page 26 of 40 Bav. 4 LOSS OF C00LDOWN CAPABILITIES Loss of functions needed for plant hot shutdown for more thac 15 minutes i YES (IP-5 )

General Emergency NO i V .

1 Complete loss of any

~~

YES .

IP-4 )

function needed for i

)( Site Area Emergen plant hot shu'tTown ---- -

- ~

NO

( Complete loss of any i

function needed for plant

- - ~

YES ( IP-3 1 '

cold'shutdum i Alert

. V "o (NOACTION) i s .

,=

e I

e 4

6 l

l t

s 26 d S

- * * * ^ #

e ,w e---v, ~- , ,-- ~w- --- - - - - -w- - - - - - - - , , -- - ----,-,----,-w -,--v-- -w---w-mr--w-wr-,,nw---, e- --a,-we+,w ,,- ++w~ =--

f, .

SQN-IPD

- SQN, . IP-1 Page 27 of 40 Rev. 4

! FUEL'(CORE) DAMAGE Loss of core geometry and primary coolant boundary '

YES IP-5

)(GeneralEmergency-

)

{

l with high potential for 1

loss of containment j 4 .

j j NO

Degraded core with possible

loss of coolable geometry- YES ( IT-4 )

4 (Indtcators shoald include i Site . Area Emergency instrtunent ation for core

. cooling, caolant activity, i containment radioactivity levels)'

1

~

i j NO i i V l ,

Fuel failure resulting from YES ( IP-3 )

coolant pump seizure ~ i Alert 1

NO

^

V .

Very high coolant activity sample (> 300 pei/cc equivalent ) l of I-131) '

YES)(_IP-3 Alert j .

I NO _

4 J

High coolant activity sample l i

(such.as, exceeding coolant ) l i

'. tech specs for iodine spike) '

YES ) ( IP-2 Notification of Unusual Event N .. NO 27 (NOACTION]

w.

. ._ . . _ . . . - . - -. - ._=_ - _. _ _ - - - .- . .. .. _-- . - _.-

1 JB e

SQNP I IP-1 PRIMARY COOI. ANT LEAXAGE Page 28 of 40 Rev. 4 Known loss of coolant accident with failure

~o f ECCS to perfonn leading to severe core YES ( IP-5 )

(Inadequate core cooling) General Emergency degradation. l NO Small loss of. coolant with initially successful ECCS operation. Subsequent YES ( IP-5 )

General Emergency failure or degradation of ECCS and l containment heat removal systems which could lead to core melt and containment

_ failure .

NO I Known loss of coolant accident YES ( IP-4 )

Site Area Emergency 4

greater than makeup pump capacity [

NO 1 Primary coolant leak rate E, 50 gpm YES .( IP-3 )

- l Alert No gj Primary leak rate greater than YES ( IP2 )

tech spec l Notification of

> 1 gpm unidentified Unusual Event

> 10 gpm identified y 40 gym controlled s

i 50 $7 d Failure of a safety or relief valve to close resulting in pressurization YES ( IP-2 )

or heatup of pressurizer relief tank [ Notification of

- Unusual Event NO V

NO ACTION k

I 0- .

es as , , . ,

, ~ m , --we -- wy -m -

p,- ~ w y

' SQN-IPD SQN,,IP-1

, Page 29 of 40 '

. Env. 4 j j

e A

FAILED FUEL MONITOR l e

f f

1 % 105 cpm increase

)

i

q .

YES)(IP-3Alert 1

NO V

i 2 X 10' cpm increase YES ( IP-2 )

Notification of Unusual Event V"o

) (NOACTION) 4 -

i

! i

4

.i

l i .

l i l k i

d

.)

I i

}

29 1,

d

- + , . . - -

4

SQN-IPD

'. SQN, IP-1 Page 30 of 40 Rev. 4 CONTAINMENT INTEGRITY s

Loss of core geometry and i primary coolant boundary )

with high potential for loss of containment (i.e.,

YES ) ( IP-5 General Emergency j hydrogen concentration > 4%,

, containment: over pressure) ~

t 1

NO V

Tech Spec violation Loss of I

containment integrity requiring YES ( IP-2 )

shutdown Notification of Unusual Event (L

+

~

NO

]

V -

(NOACTION) 4 i

i i

C 30 t .

-v -- - . , , ,-_

. SQN-IPD SQN, IP-1 Pg e 31 of 40 Sav. 1]

t AREA RADIATION LEVELS -

1 4

i a

j High Radiation levels or high airborne contaminatiod which )

indicates a severe degradation in the control of radioactive i

YES)(IP-3 g,3

. materials. (such as, an j increase of a factor of 1000 1 in direct radiation readings j within. facility) 1 gu NO

, V (NOACTION) m, 1

a i

f I

1 1

4

! - l I

i s

31 f _ _

% e 9pu* --

, - - - - , a-.-wr- w %

l

(* SQN-IPD SQN, IP-1 Page 32 of 40

'Rev. 4

.<*'~ .

RAD 10I.0GICAL EFFLUENTS 1 Rem /hr whole body or. 5 Rem /hr.

thyroid at site boundary with actual )

metrological conditions. These dose rates are projected based on other r

YES)(IP-5 General Emergency parar.eters (e.g. radiation levels in- '

containment wi~th leak rate appro-priate for existing containment pres-4 sure with some conformhtion from effluent monitors) or are messGred in the environa-.

5 .- w .-

['

'500 MR/hr whole body or 2500 HR/hr thyroid at site boundary for 2 mins. ,

YES (IPh )

in worst metrological condition. Site Area (Races projected on plant parameters l Emergency or measured in environni - - - -

NO 50 MR/hr whole body or 250 MR/hr thyroid at site"bcundary for br.

i' in worst metralogical condition.

(Rates projected on plant parameters i YES)(Ip_h )

, or measured in environs) Site Area

' Emergency NO 4

V 10 times tech spec instantaneous ..

limit, 2.6 curies /sec noble gas (an instantaneous rate which, j

if continued for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, would result in 1 MR at site boundary i YES (7p_3 )

under average metrological Alert conditions)

. NO V l Radiological effluent Tech. Spec. l i

limit exceed

_ i YES)(7p_g )

Notification o.'

{

Unusual Event y No

} hACTION) 32 i

= = = . - - . . . . . -

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

i

, l 4

SQN-IPD l SQN, IP-1 j

. Page 32A of 40

/. Rev. 4 0FFSITE DOSE ASSESSMENT

/ N Kacwn loss of coolant accident and shield building vent monitor, I YES RM90-260, indicates a radiation eneral Emergency ;

level of 154 mR/hr (corresponds to 1 R/hr dose at site boundary under worst c.mse conditions)-Sum of U1 and U2 monitors.

OR i Airborne release rate from all sources >: I YES Noble Gas 2.6 x 10 pCi/s, or neral Emergency Total Iodine 1.9 x 10 pCi/s, or Iodine-131 1.3 x 10 pC1/s (To be determined by grab sample)

N, #

NO

( '

Known loss of coolant accident and shield building vent monitor, l YES P RM90-100, indic9tes a radiation Area Emergenc' 1

level of 1 x 10 cpm for 1/2 hr.

j (Corresponds to 50 mR/hr dose at

, site boundary under worst case conditions)-Sum of U1 and U2 monitors.

OR Airborne release rate from all sources >: l YES P Area Emergency Noble Gas (2 min. rele9se) 1.3 x 10 pCi/s, or (1/2 hr. relgase) -

1.3 x 10 pCi/s, or Iodine-131 (2 min. relegse) c j 6.5 x 10 pCi/s, or

. (1/2 hr. release) 65 pCi/s (To be determined by grab sample)

% ~

s

..I '

e

NO L V

_[ 32A 4

, . . . ~

,r msW - y y r- - , - --

y. -, ,--p--eeWwt' w y y--9--w-+-te p-gre-** -We--?75 +-gf- w --+v-esi-gW--Nwww -t 'tY"

SQN-IPD

-SQN, IP-1

/ .

Page 32E of 40

'k Rev. .4

?

0FFSITE DOSE ASSESSMENT (Continued)

/ N i

Shield building vent monitor, RM90-100, indicateg a radiation level of 7.6 x 10 cpm. (Corresponds to 0.5 l YES Or-Alert mR/hr under average meteorological

, conditions)-Sum of U1 and U2 monitors.

i i .

Airborne release rate from all j sources >:_

4 S

hP-3 Noble Gas 7.8 x 10 pCi/s, or Alert Tor.al Iodine 5.8 pCi/s, or Iodine-131 4.0 pCi/s (To be determined by grab sample) p NO

. - N Shield building vent monitor l YES hNotificition of

' - RE-90-100judicatesaradiation j level 7 10 cpm.-Sum of U1 and U2 monitors Unusual Event 4

} OR I

j Radiological effluent Tech. Spec.

exceeded.

l YES hNotification of

% j Unusual Event i

i

! V" NO ACTION 4

r i

% l l

32B

. 1 u

. l SQN-IPD e , ,

SQN, IP-1 Page 32C of 40

(~' Rev. 24 0FFSITE DOSE ASSESSMENT (Continued) 1 Rem /hr whole body or 2 Rem /hr thyroid at site boundary with actual meteorological conditions. (Rates

[ YES hGefieral Emergency projected on plant. parameters or ;

measured in environs.)

NO j

Q 500 MR/hr whole body or 1000 MR/hr i thyroid at site boundary for 2 minutes I YES P- -

in worst meteorological condition, e Area Emergenc f (Rates projected on plant parameters 1 or measured in environs.)

~

i NO j 50 MR/hr whole body or 100 MR/hr l, thyroid at site boundary for 1/2 hr [ YES P

' in worst nie'teorological condition. Are Area Emergency

{

<- (Rates projected on plant parameters or measured in environs.)

i 0.5 MR/hr whole body or 1.0 MR/hr thyroid at site boundary with l YES IP actual meteorological conditions. , A rt

-(Rates projected on plant parameters or measured in environs.)

1 NO ACTION l ,

j . ,

i 1

o' 32C l

I s

~~-

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

-- --- ~ ~n -- ---,-e n _, __,,_ , , . _ _ _ , ,_., ., ,. __g, .

i

+* ,

SQN-IPD

- SQN, [P-1 4

Page 33 of 40 Rev. 4

(- .

FUEL HANDLING INCIDENT

. Major damage to spent fuel in containment or auxiliary )'

building (large object. damages '

YES)(IP-4Site Area Emergency fuel or water loss below fuel q level, etc.) -

1 ,

5 NO

' V 4

Fuel damage accident with release of radioactivity to containment '

YES ( IP-3 )

or auxiliary building Alert

( ._

NO

Tech Spec violation that requires j no further core alterations and YES

' ( IP-2 ]

warrants increased awareness of Nctification of state and local authorities Unusual Event 1 ,.

t V "o gACTION)

~

-V 33 a

1 .

E , .. ._ ... ~~.. . . _. . s_

o SQN-IPD SQN, IP-1

- Page 34 of 40

,f -

Rev. 4

\

ABNORMAL PLANT CONDITIONS Plant conditions exist, from whatever source, that make release of large amounts )

of radioactivity in a short time period possible (such as, YES )( IP-5 Gene.ral Emergency any core melt situation) 4 .

1 NO V

Warranting activation of emergency centers and monitoring teams and a )

precautionary public notification i

YES)(IP-4 Site Area Emergency y

NO

('

V-Warranting precautionary activation of Technical )

Support Center and Emergency Control Center i

YES)(IP-3 Alert t

NO V -

Warranting awar'enes's. of plant operating staff or YES (.IP-2 )

state and/or local Notification of authorities or require plant -

Unusual Event shutdown under technical , j specification requirements '

-; or involve other than normal l controlled shutdown (e.g.,

s coldown rate exceeding tech-nical specifications, pipe cracking found during operation) .

i

' N0 4%.

NO A TION 34 e

. ma

- - - - - - - - - _ _ _ - - , ,,_w -- -- -s,- ,..,,-,--y..- _ -.m . -., , . . , .,y- w-

, s

, SQN-IPD i -

. SQN, IP-3 Page35 of 40 Rev. 4 '

/

4 SAFETY LIMITS I

1 i

4 j

Exceeding coolant temperature and/or pressure limits or )

( ;

exceeding core temperature limits.

YES)(IP-2 Notification of Unusual Event d -

f y NO (NO ACTION) 2 i

i II.

n.

?

4 1

1 ~

i k

i ,.

A -

?

I

's ,

l i

i 2,

1

, i . -

l _ _ . . _ _

1

~

SQN-IPD

$QN, I?-l

. . Page 36 of 40 Rev. 4 y

REACTOR CONTROL ROD PROBLEMS Rupture of a control rod drive

mechanism housing (ejected rod) YES

( IP-4 )

Site Area Emergency NO Single rod cluster control-assembly withdrawal at full power YES ( IP-3 )

j -

Alert

$ NO

] V i

( Uncontrolled rod cluster control I asseboly bank withdrawal at power YES ( IP-2 )

1 Notification of NO Unusual Event l

i V Uncontrolled rod cluster. control -

assembly bank withdrawal from a ,

YES ( IP-2 )

suberitical condition i Notifice. tion of

]

^Unususi Event i

NO 1 ._

j t_.

1 w

(NOACTION) 9.-

5 r

(. 36

SQN-IPD

- - SQN, IP-1

- Page 37 of 40

/ Rev. //

~

INACTIVE REACTOR COOLANT LOOP

> Startup of an inactive Reactor Coolant Loop YES ( IP-2 )

. > 10% power Notification of Unusual Event a V" -

3 (NOACTION) 4

+

0 e

t t

a.

9

> J 1

b 3

O 9 .

v j ,,-

.(. 37 .

d i

44 W M M

'. '- A M ,

w- - ,, ,--~-- ,,. w- , - - , , - - - + - , , , , , - , . . - m, -._ y.

9 -

__,--,,_y3,,,-,..y m,,g- ,-.,e.,.yw

l l

l

, , o

I

. 1

l

- SQN-IPD

. SQN, IP-1 Page 38 of 40 f- Rev. 4[

BORON DII.UtION

.9 %

Uncontrolled Boron Dilution YES (IP-2

- I Notificstion of

- Unusual Event G NO ,

l (NOACTION) d

('

5 1

3 e

e

'1 t

i s ./ 38 t l l

1

~ . . - - ~ * - . . ,

1

SQUP

.~ Ip_t FEEDWATER Page 39 of 40 (NORMAL AND AUXILIARY) Rev. 4

.f' Transient initiated by loss of f feedwater and condensate systems (principal heat removal YES IP-5

' General Emergency sys, tem) folicwed by failure of -

emergency feedwater system for extended period k

NO

(

$ Major rupture of a main feedwater pipe YES (IP-3 )

4 Alert NO V

Excessive heat removal due to feedwater system YES ( IP-2 )

malfunctions -

i 4 Notification of

~

Unusual Event f ,-

NO

(

V -

l

' s (N0'ACTIONJ i

t i

i .

I. '

I 4

4 m

sq

e J.

-.n - - -.

.s . -I.

SQN-IPD SQN, IP-1 Page 40 of 40 Rev. 4

/

l WASTE GAS DECAY TANKS l Waste Gas Decay Tank Rupture l I

YES ( IP-4 )

Site Area Emergency (NOACTION) t e

en

(

)

i

i. .

1 1 .

1 e

i b

40 h

e. e w-* . . . . . .+. ,, ,

y - w - - -, , , . - - - - - - sm-- -,~g.,, nr .-.-.7,,.-+---wg e - v,4s---ww-, ww

. v .

Sequoyah Nuclear Plant DISTRIBUTION 1C 81 Plant Master File ic 83 Asst. Power Plant Supt. (Ope r. )

[

_lc 84 Asst. Power Plant Supt. (Maint.)

SQN REP - IMPLEMENTING

PROCEDURES DOCUMENT 1C 86 Maintenance Supervisor (M)

IC 87 Maintenance Supervisor (E)

-1 i 1C 88 Maintenance Supervisor (I)

, SQN, IP-3 1C 89 Results Supervisor.

IC 90 Operations Supervisor ALERT j IC 92 Health Physics Supervisor i IC 93 Public Safety Services Supv.

IC 95 Outage Director 1C 96 Emergency Cabinet Control Room I IC 97 Emergency Cabinet Communications Room IC 98 Emergency Van j 1C 1C 102 Shift Engineer's Office 103 Unit Control Room i

Prepared By: J.R. Walker 1C 105 Health Physics Laboratory

Revised By: R.J. Kitts 1C 106 Medical Office 1C 107 Resident NRC Inspector - SNP I Submitted By: bc. hM Supervisor 1C 1C 108 Technical Support Center 109 Assistant HP Supervisor IC 110 Plant Duty Supervisor j IC 111 Asst. Power Plant Supt. (H&S) f j PORC Review: /d/G4/y > 1C EP&P - Eric Sliger - 1470 CST 2-C

, / Date Approved By: -

sr Plt Superintendent Date Approved: /S/94/h'G-

! /

4 4

Rev. No. Date Revised Pages Rev. No. Date Revised Pages t

0 8/5/80 All 4 10/26/82 2 1 10/10/80 2 5 /2.2'/f)- All 2 12/2/81 1 3 3/11/82 1 The last page of this instruction is Number 2 .

v -

1 l

. l SQNP

. . REP-IPD -

SQN, IP-3

/ '

Page 1 of 2 Rev. 5 ALERT 1.0 PURPOSE 1.1 To provide a method for timely notification of appropriate individuals when the Shift Engineer has determined by IP-1 that an incident has occurred which is classified as an ALERT.

1.2 To provide a method for periodic reanalysis of the current situation by I the Site Emergency Director to determine whether the Alert action should be canceled, continued, upgraded, or downgraded to another classification.

! 2.0 INSTRUCTION

^

2.1 Upon determining that. existing conditions are classified as an Alert according to IP-1, the Shift Engineer will:

(Initials)

1. Evaluate plant conditions and, if conditions warrant, activate emergency sirens for personnel assembly and initiate IP-8, 9,14 and 20 if needed.

9

( 2. Notify the Operations Duty Specialist direct by Dimension telephone a number 7-200 or alternate Chattanooga number 8-0200 and state the

following:

I a. Your name

b. Sequoyah Nuclear Plant

c. Alert

d. Time of incident

e. Brief description of incident

f. Plant condition (whether stable or deteriorating)

g. Unusual release of radioactivity (Yes or NO)

h. Direction wind is coming fromI and speed

i. Recommend initial protective actions for the public:

l (None)

I oN-

, , o SQNP I REP-IPD

- SQN, IP-3

/,

Page 2 of 2 Rev. 5

3. Notify the Plant Duty Supervisor and provide the same information given to Operations Duty Specialist (see duty list for telephone numbers).

4. Notify the Health Physics Laboratory.

5. Initiate IP The Shift Engineer's clerk will contact one 4 individual in each section of the call list (in IP-6) during off hours or any hour when an ALERT condition is declared

without initiation of the emergency evacuation alarm.

2.2 The Site Emergency Director will:

1. If there is an indication that any personnel are injured, initiate IP-10, Medical.

4

2. If there is an indication of a security threat, initiate IP-11,

3. Initiate IP-7 (Activiation of the Operations Support Center).

4. Notify the NRC by ring-down phone of plan activiation in

'( accordance with AI-18, File package 18.

i 5. At least every two hours or more frequently if conditions l warrant, reevaluate the event using IP-1.

}

1 a. If the situation no longer exists or should be down-graded, cancel or downgrade the Alert by informing the e

Operations Duty Specialist and the Plant Duty Supervisor.

4

b. If the condition warrants upgrading to a higher classifi-cation, intiate the appropriate steps in the procedure (IP-4 or IP-5) for the more serious conditions.

6. If a significant radiation release has occured in contain-ment as indicated by containment monitor (s) evaluate the need to implement TI-30 to determine the amount of Radio-activity being released through normal plant release points.

s

( ~

i 1 . . _ - _ _ .

, s .

o Sequoyah Nuclear Plant DISTRIBUTION 1C H1 Plant Master File

/ LC 83 Asst. Power Plant Supt. (Oper.)

1C 84 Asst. Power Plant Supt. (Maint.)

SQN REP - IMPLEMENTING PROCEDURES DOCUMENT 1C 86 Maintenance Supervisor (M) 1C 87 Maintenance Supervisor (E)

IC 88 Maintenance Supervisor (I)

. SQN, IP-4 1C 89 Results Supervisor

', 1C 90 Operations Supervisor SITE AREA EMERGENCY IC 92 Health Physics Supervisor 1C 93 Public Safety Services Supv.

1C 95 Outage Director 1C 96 Emergency Cabinet Control Room

$ 1C 97 Emergency Cabinet Communications Room IC 98 Emergency Van i 1C 102 Shift Engineer's Office 1C 103 Unit Control Room

Prepared By: J.R. Walker 8 1C 105 Health Physics Laboratory j Revised By: R.J. Kitts 1C 106 Medical Office t ,

1C 107 Resident NRC Inspector - SNP

Submitted By: 2.J . M eN IC 108 Technical Support Center SuperH s~or 1C 109 Assistant HP Supervisor l 1C 110 Plant Duty Supervisor 1C 111 Asst. Power Plant Supt. (H&S)

PORC Review: /S[df/f?

bate 1C EP&P - Eric Sliger, 1470 CST 2-C Approved By: e Plt Superintendent Date Approved: / df /A i / /

4*

Rev. No. Date Revised Pages Rev. No. Date Revised Pages i 0 8/5/80 All 4 10/26/82 2 i- 1 10/28/80 2 5 /3J/f2 All, Title Change 2 12/2/81 1 3 03/11/82 1 ,

l I The last page of this instruction is Number 2 .

I i

l A.

I 1

. o .

SQNP REP-IPD SQN, IP-4, I. Page I of 2 Rev. 5 SITE AREA EMERGENCY t

! 1.0 PURPOSE 1.1 To provide a method for-timely notification of appropriate individuals when the Shift Engineer has determined by IP-1 that an incident has occurred which is classified as a Site Area Emergency.

1.2 To provide a method for periodic reanalysis of the current situation by the Site Emergency Director to determine whether the Site Area Emergen:y 4 action should be canceled, continued, upgraded, or downgraded to another classification.

2.0 INSTRUCTIONS 2.1 Upon determining that existing conditions are classified as a Site Area Emergency according to IP-1, the shift engineer will:

(Initials)

1. Activate emergency sirens for personnel assembly and initiate IP-8 3

and IP-9.

4 i< 2. If conditions warrant, initiate IP-14 (Health Physics Procedures),

d IP-20 (Environmental Monitoring duri,ng a radiological emergency).

~

3. Notify the Operations Duty Specialist direct by Dimension telephone

' number 7-200 or alternate Chattanooga number 8-0200 and state the following: ,

a. Your name e b. Sequoyah Nuclear Plant

c. Site Area Emergency

d. Time of incident

e. Brief description of incident

f. Plant condition (whether stable or deteriorating)

g. Unusual release of radioactivity (Yes or No)

. h. Direction wind is coming froc and speed

i. Recommend initial protective actions for the public:

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. . REP-IPD SQN, IP-4

/ Page 2 of 2 Rev. 5

-(Initials) ,

4. Notify the health physics laboratory.

5. Notify the Plant Duty Supervisor and provide the same information given to Operations Duty Specialist (see duty list for telephone number).

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6. During off shifts the Shift Engineer Clerk will contact one individual in each section of the call list in IP-6.

2.2 The Site Emergency Director shall:

1. If there is an indication that any personnel are injured, -

initiate IP-10, Medical.

2. If there is an indication of a security threat, initiate IP-11.

3. Initiate IP-7 (activation of the operation support center).

4. Notify the NRC by ring-down phone of plan activation in accor-(. dance with AI-18, File Package 18.

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5. At least every two hours or more frequently if conditions warrant, reevaluate the event using IP-1.

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a. If the situation no longer exists or should be down-graded downgrade the Site Area Emergency by informing the Operations-Duty Specialist and the Plant Duty Supervisor.

4

b. If the condition warrants upgrading to a higher classifi-cation, initiate IP-5 for the more serious condition.

6. If a significant radiation release has occured in containment as indicated by containment monitor (s) evaluate the need to implement TI-30 to determine the amount of Radioactivity being released through normal plant release points.

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- 1C 81' Plant Master File 1C 83 Asst. Power Plant Supt. (Oper.)

1C 84 Asst. Power Plant Supt. (Maint.)

SQN REP - IMPLEMENTING PROCEDURES DOCUMENT 1C 36 Maintenance Supervisor (M) 1C 37 Maintenance Supervisor (E)

IC 88 Maintenance Supervisor (I)

< SQN, IP-5 lc 89 Results Supervisor 1C 90 Operations Supervisor l 92 Health Physics Director GENERAL EMERGENCY IC 1C 93 Public Safety Services Supv.

1C 95 Outage Director 1C 96 Emergency Cabinet Control Room lc 97 Emergency Cabinet Communications Room l IC 98 Emergency Van j 1C 102 Shift Engineer's Office Prepared By: J.R. Walker 1 1C 105 Health Physics Laboratory 106 Medical Office Revised By: R.J. Kitts 1C 1C 107 Resident NRC Inspector - SNP Submitted By: /2S'upervisor-

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1C 1C 108 Technical Support Center 109 Assistant HP Supervisor 1C 110 Plant Duty Supervisor 1C 111 Asst. Power Plant Supt. (H&S)

PORC Review: - /2. f 3- IC EP&P - Eric Sliger, 1470 CST 2-C f / Date ,

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Approved By: , ,-

dr Plt Superintendent i

Date Approved: /6L 9 <f'.>-

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4 Rev. No. Date Revised Pages Rev. No. Date Revised Pages j

4 10/26/82 2 0 8/5/80 All

' 2 5 /)-)1f) All 1 10/21/80

2 12/2/81 1 _ _ _ _

1 1 3 3/11/ 8.' 1 ,

The last page of this instruction is Number 2 .

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SQNP

, . REP-IPD IP-5 Page 1 of 2

, , Rev. 5 GENERAL EMERGENCY 1.0 PURPOSE 1.1 To provide a method for timely notification of appropriate individuals when the shift engineer has determined by IP-1 that an incident has occurred which is classified as a General Emergency.

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1.2 To provide a method for periodic reanalysis of the current situation by 1 the Site Emergency Director to determine whether the General Emergency action should be canceled, continued, upgraded, or downgraded to another 1 classification.

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-i 2.0 INSTRUCTIONS 2.1 Upon determining that existing conditions are classified as a General Emergency according to IP-1, the shift engineer will:

(Initials) g

1. Activate emergency sirens for personnel assembly and initiate IP-8

( and IP-9.

2. If conditions warrant, initiate IP-14 (Heath Physics Procedures),

i IP-20, (environmental monitoring during radiological emergency).

3. Notify the Operations Duty Specialist direct by dimension telephone number 7-200 or alternate Chattanooga number 8-0200 and state the following:

4

a. Your name

b. Sequoyah Nuclear Plant

c. General Emergency

d. Time of incident

e. Brief description of incident,

f. Plant condition (whether stable or deteriorating)

g. Unusual release of radioactivity (Yes or No)

h. Direction wind is coming from and speed

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. SQNP REP-IPD SQN, IP-5' I Page 2 of 2 Rev. 5 4

1. Recommended initial protective actior.s for the public:

(Activate the warning system and advise the public to take shelter, tune radio or TV to a local station, and await torther instructions).

g (Initials)

3. Notify the health physics laboratory.

4

4. Notify Plant Duty Supervisor and provide the same information given to Operations Duty Specialist (see duty list for telephone number).

5. During off shifts the Shift Engineer Clerk will contact one individual in each section of the call list in IP-6.

2.2 The Site Emergency Director shall:

1. If there is an indication that any personnel are injured, initiate

. IP-10 (Medical).

A e' 2. Initiate IP-11. ,

3. Initiate IP-7 (Activation of the Operations Support Center).

1

! 4. Notify the NRC by ring-down phone of plan activiation in accordance with AI-18, File Package 18.

4 5. At least every two hours or more frequently if conditions warrant, reevaluate the event using IP-1.

- If the situation no longer exists or should be downgraded, cancel

. or downgrade the General Emergency by infroming the Operations Duty Specialist and the Plant Duty Supervisor.

6. If a significant radiation release has occured in containment, as indicated by containment monitor (s), evaluate the need to imple-ment TI-30 to determine the amount.of Radioactivity being released I through normal plant release points.

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This log sheet must be retained as the last page of the Sequoyah Implementing Procedures Document.

Inserted by: Date Inserted:

Pages to be Removed New Pages to be Inserted Part Page Number Revision Part Page Number Revision Table of Table of Contents 1 of 1 01/06/83 Contents 1 of 1 01/11/83 IP-18 Cover Page Rev. 3 IP-18 Cover Page Rev. 4 (Remove pages 1 through 53) r j " A 4 . w._ ,

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IMPLEMENTING PROCEDURES INDEX Instr. Revision Title

, SQN-IP-1 4 Emergency Plan Classification Logic SQN-IP-2 .3 Notification of Unusual Event SQN-IP-3 5 Alert

. . ~ ~ ' " Site Emergency . .. . .

SQN-IP-4 5

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SQN-IP-5 5 Emergency - General Eniergency SQN-IP-6 4 Activiation of the Technical Support Center SQN-IP-7 1 Activation of the Operations Support Center SQN-IP-8 6 Personnel Accountability and Evacuation SQN-IP-9 0 Accountability and Evacuation of the Power Operation Training Center SQN-IP-10 6 Medical Emergency Procedure

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SQN-IP-11 3 Security and Access Control SQN-IP-13 4 Call Lists SQN-IP-14'8 Health Physics Procedure SQN-IP-15 1 Emergency Exposurs Guidelines SQN-IP-16 0 Recovery Procedure 2 % ?SQN-IP-17.6.- Emergency Equitment i and Supplies.

, ::19.[SQN-IP18,4~ ' Plant Release Rate Calculations.

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SQN-IP-19 0 , Radiological Emergency Plan Training M ; M 0. .

' Environmental Monitoring During'A Radiological Emergency

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,Sequoyah Nuclear Plant DISTRIBUTION Cover Page 1 1C_ 81 Plant Master File IC 83 Asst Pwr Plant Supt., (Oper.)

f f.- IC 84 Asst Pwr Plant Supt., (Maint.)

b SQN REP - IMPLEMENTING PROCEDURES DOCUMENT IC _ 86 Maintenance Supervisor (M)

IC 87 Maintenance Supervisor (E) l IC 88 Maintenance Supervisor (I)

SQN, IP-18 1C_ 89 Results Supervisor IC 90 Operations Supervisor PI ANT RELEASE RATE IC 92 Health Physics Supervisor CALCULATIONS IC 93 Public Safety Services Supv.

IC_ 95 Outage Director IC 96 Emergency Cabinet Control Room

IC 97 Emergency Cabinet Communications Room IC 98 Emergency Cabinet Gatehouse

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' Prepared By: Walter Zabel IC 102 Shift Engineer's Office IC 103 Unit Control Room Revised By: R. J. Kitts IC_ 105 Health khysics Laboratory Submitted By: h3Supervisor %Cb'g' IC 106 Medical Office IC 107 Resident NRC Inspector - SNP IC- 108 Technical Support Center i IC 109 Assistant HP Supervisor

.PORC Review: /-//- 9 3 1C 110 Plant Duty Supervisor

'Date IC 111 Asst. Plant Supt. (H&S)

IC AC EP&P - Eric Sliger,1470 CST 2-C Approved By: [w _

E Plt Superintendent Date Approve : / //-F3 4

The current revision level of this instruction is: .

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t J. Reason for current revision (include all temporary change numbers) Canceled

.jentire instruction because Knoxville Emergency Center (KEC) has the respons-

~9.ibility l to perform calculations required in SQN-IP-18.

~ ;fiTheilast,page of,this instruction is number .

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Cover Sheet Page 2 SQN, IP-18 History of Revisions Rev. Level Date Revised Pages

( Rev. Level' 'Date Revised Pages 0 08/21/80 ALL 1 10/22,'20 1,Added 1A,49-51 1-3,7,9,10,12-14, 2 06/29/81 Added 1A Revised 1 & 6, 3 -12/21/81 Added 6A,14A,52,53 4 /-//-PJ Cancel Entire Inst. _

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REVISION LOG SHEET Revision Date: PORC' January 6.1983 (issued 2/2/83)

This log sheet must be retained as the last page of-the Sequoyah Implementing Procedures Document.

Inserted by: Date Inserted:

Pages to be Removed New Pages to be Inserted Part Page Number Revision Part Page Number Revision

' Table of Table of Contents 1 of 1 12/21/82 Contents 1 of 1 01/06/83 IP-17 Cover Page Rev. 5 IP-17 Cover Page Rev. 6 1 of 3 Rev. I 1 of 3 Rev. 6

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2 of 3 Rev. 1 2 of 3 Rev. 6 3 of 3 Rev. I 3 of 3 Rev. 6 ,

Att. 3 1 of 2 Rev. 5 Att. 3 1 of 2 Rev. 5 2 of 2 Rev. 5 2 of 2 Rev. 6 Att. 4 1 of 1 Rev. 4 Att. 4 1 of 1 Rev. 6 s Att. 5 1 of 2 Rev. 5 Att. 5 1 of 2 Rev. 6 2 of 2 Rev. 2 2 of 2 Rev. 2 Att. 6 1 of 1 Rev. 5 Att. 6 1 of 1 Rev. 6 Att. 9 1 of 2 Rev. 5 Att. 9 l'of 2 Rev. 6 2 of 2 Rev. 2 2 of 2 Rev. 6 l

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TABLE OF CONTENTS Page 1 of'1 IMPLEMENTING PROCEDURES INDEX Instr. Revision ' Title SQN-IP-1 l+ Emergency Plan Classification Logic SQN-IP-2 3 Notification of Unusual Event SQN-IP-3 5 Alert SQN-IP-4 5 Site Emergency SQN-IP-5 5 Emergency - General Emergency SQN-IP-6 4 Activiation of the Technical Support Center SQN-IP-7 1 Activation of the Operations Support Center SQN-IP-8 6 Personnel Accountability and Evacuation SQN-IP-9 0 Accountability and Evacuation of the Power Operation Training Center l ( SQN-IP-10 6 Medical Emergency Procedure -

SQN-1P-11 3 Security and Access Control ,

SQN-IP-13 4 Call Lists SQN-IP-14 8 Health Physics Procedure SQN-IP-15 1 Emergency Exposure Guidelines SQN-IP-16 0 Recovery Procedure

)(SQN-IP-176 Emergency Equipment and Supplies SQN-IP-18 3 Plant Release Rate Calculations

, SQN-IP-19 0 Radiological Emergency Plan Training SQN-IP-20 1 Environmental Monitoring During A Radiological Emergency Revised 01/06/83 i

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'Sequoyah Nuclear Plant DISTRIBUTION f-IC 81 Plant Master File lc 83 Asst. Power Plant Supt. (Oper.)

IC 84 Asst. Power Plant Supt. (Maint.)

SQN REP - IMPLEMENTING' PROCEDURES DOCUMENT 1C 86 Maintenance Supervisor (M)

IC 87 Maintenance Supervisor (E)

IC 88 Maintenance Supervisor (I) 1C 89 Resalts Supervisor SQN, IP-17 1C 90 Operations Supervisor 1C 92 Health Physics Supervisor EMERGENCY EQUIPMENT AND SUPPLIES 1C 93 'Public Safety Services Supv.

1C 95 Outage Director 1C 96 Emergency Cabinet Control Room IC 97 Emergency Cabinet Communications Room 1C 98 Emergency Van

- IC ,100 Emergency C4'uluci ;ic ic u m ulagi- = 1 R1A -

IC_ 102 Shift Engineer's Office 1C 103 Unit Control Room Prepared By: R. J. Prince 1C 105 Health Physics Laboratory Revised By: Jerry D. Osborne 1C 106 Medical Office 1C 107 Resident NRC Inspector - SNP Submitted By: h. b Supervisor' IC IC 108 Technical Support Center 109 Assistant HP Supervisor k

/ 1C 110 Plant Duty Supervisor 1

\. 1C ll( Asst. Power Plant Supt. (H&S) I PORC Review: /- dI - 2P25 1C CC ':00 - Eric Sliger, 1470 CST 2-C /m Date ~ 6F+f Approved By: e r Plt Superintendent Date Approved: MS-83

Rev. No. Date Revised Pages Rev. No. Date Revised Pages 0 8/5/80 ALL 4 10/28/81 10 1-9,11,17,20 Revise 4,5,6,8,9, 1 9/17/80 Add 11A,17A,21 5 11,13,16,17,19,20 Delete 11A,17A, 3/22/32~~ Revise 1,2,3,/,10,11,0 2 2/11/81 Revise 12,18 6 /-g-Jf3 13,17,&l8, Delete 21 3 7/30/81 Revise 21 The last page of this instruction is Number 20

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SQNP REP-IPD SQN, IP-17

/ Page 1 of 3 Rev. 6 EMERGENCY EQUIPMENT AND SUPPLIES 1.0 SCOPE This instruction is used to comply with the requirements of the Radiological Emergency Plan for periodic inspection and maintenance of equipment and supplies.

The emergency equipment, listed in attachments 1, 2, 3, and 5, is stored in cabinets provided with a plastic seal. These seals provide a means of deter-uining that the cabinet has not been opened. An inventory list of the equip-ment is posted on the outside and inside of the cabinet. The four cabinets are located in: (1) Main Control Room Corridor, (2) Comcunications Room, (3) Gatehouse, and (4) Meteorological Tower Building.

Equipment and supplies listed in attachment 11 are stored in the technical support center and are available for use during an emergency.

The Stokes splint stretchers are located adjacent to the cabinets.

The emergency equipment, listed in attachment 9, is located in the health physics emergency van. In the event of a radiological emergency that re-quires the emergency van to be used, a health physics technician will ob-( 4F tain the additional eqitipment listed in Attachment 1 of IP-20. This equip-(Fment will be placed in the emergency kit provided and transported to the van.

The emergency room supplies furnished by TVA for use at the Erlanger Medical Center in case of injury to personnel involving radioactive materials are listed in attachment 10.

The radiation monitoring instruments, which are in normal plant use, are lo-cated in the health physics labc ratory as listed in attachment 4. The self-contained respiratory devices are located as follows: Gatehouse, Health if Physics Laboratory, and Turbine Building, Elevation 685, near freight lift, jk(Attachment 6).

Eight (8) additional self contained breathing units (with an additional one-hour's reserve air capacity for each unit) are permanently stored in the con-trol room area for employees who must continuously man the control room.

These self-contained breathing units shall be labeled "For Control Room Use Only".

2.0 RESPONSIBILITIE3 2.1 The plant nurse shall be responsible for inventory and inspection of em-ergency medical supplies located in the medical treatment area, as listed l in attachment 7. The completed inventory sheet will be returned to the l health physics supervisor. l

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SQN, IP-17 f

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1 2.2 The individuals performing the inspection shall complete the data sheets and the health physics supervisor shall review the results and make arrangements to correct deficiencies, and file the data sheets in the health physics files.

3.0 FREQUENCY 3.1 Each cabinet and storage location, including the medical treatment area, i shall be inventoried and required equipment inspected and checked for op-eration and/or condition. The equipment listed in attachments 1, 2, 3, 5, 9 and 11 have been separated into two categories. Table A is a listing of all non perisable items stored in a small metal box within the cabinet it-self. This metal box is equipped with a security seal. These items will be inventoried annually. Additionally these items will be inventoried

- whenever a security seal has been found to be violated. Those items listed in Table B of these attachments are inventoried on a quarterly basis. This inventory is performed within the last two weeks of each calendar quarter.

3.2 The portable radiation monitoring instruments shall be inventoried and calibrated on a routine basis per RCI-5, " Calibration of Health Physics Instruments".

f- . Mf3.3 All self-contained breathing units in service shall be inventoried and

( inspected monthly by the health physics section. This inspection is performed per RCI-4, " Respiratory Protection Program".

4.0 PROCEDURES 4.1 Each cabinet shall be inventoried against the list of required items.

4.1.1 List any items missing and the disposition on the data sheet.

4.1.2 Deficient items shall be replaced.

4.2 Special checks of certain material in the cabinets shall be performed.

- The.following checks shall be made where applicable:

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'4.2.1 The copies of the TVA-REP and dEP Implementing Procedures

1. Document shall be checked to determine that all revisions have

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been inserted properly.

1 14.2.2 The self-contained breathing units shall be checked per RCI-4, J - ; f. " Respiratory Protection Program".

, l 4~.2.3 ' The prr,cective clothing shall be checked for deterioration.

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F 4 4.2.4 The smoke tubes and aspirator bulbs shall be checked for de-

/ terioration and that the tubes have not been broken or used.

[ '4.2.5 Replace all batteries with fresh batteries drawn from Power Stores. (Do not discard batteries. Return them to the tool

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SQN, IP-17 Page 3 of 3 Rev. 6 4.2.6 Check to determine that flashlights are operable.

. 4.2.7 Check first-aid kits to confirm they are stocked to current TVA specifications.

4.2.8 Rezero all emergency dosimeters to assure proper operation.

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4.3 Completion of Inventory Forms 4.3.1 If the parcicular items are present and in sufficient quantities and, when applicable, in good working condition, then check the yes column. ,

4.3.2 If a deficiency is noted, then check the no column.

4.3.3 Under the remarks column explain the corrective actions taken.

. NOTE: All comments in the remarks column should be detailed enough to leave no doubt as to the actions taken.

Comments to the effect. " batteries missing" will not suffice. A simple check in the no column will represent that a deficiency exists. Such comments do not allow a person to determine what, if any, action has been taken and'wil'. on 5 lead to confusion. Comments should read-for example: Batteries replaced on March 25, 1980.

All deficiencies must be corrected as soon as possible. If circumstances do not allow deficiencies to be corrected then the shift supervisor shall be notified.

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ATTACHMENT 3 EMERGENCY EQUIPMENT -

Location: Gatehouse Cabinet *

The following equipment-is stored in the Gatehouse.

1 TABLE A Quantity Description Yes No. Remarks

-12 Pencils 10 Gloves (rubber) 10 Gloves (canvas)

10 Rubber overshoes

1 Box air filters i 2 Extension cords - 100 volts, 3-prong 1

Roll radiation zone tape

3 Urine kits 20 Radiation and contamination -

4 zone tags 2 Rolls masking tape i

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Do=. plastic bags ___

1 Pkg Paper towels 1 Pkg ea. Emergency forms, TVA 17095,

' 1709'6, 17093, 17126, 17106, 17130

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1 3 Grease seencils ~~~

i .2 Pair scissors 1 .

2 Pocket knives l 2 Boxes smoke tubes

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2 Aspirator bulbs 1 Log book ___,

fx. -3 Boxes of smears ___

ay. . . with holders

- ~ 'le. Screwdriver, slotted and Phillips m'- . ...1 es. Pliers, regular and .

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. s ' 10 ea .' Fifteen minute-red highway flares

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' 1 ea.- 10" adjustable wrench

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18" adjustable wrench

> ^ j e. ;j .p. i U ea. Wire cutters'(side

' - ' - W:%g cutter pliers)

, 7, 7 11 ea. Hammer (carpenters)

, : Aj _ / 1 es. Hatchet ___

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. SQN, IP-17 Page 2 of 2 V Rev. 6 ATTACHMENT 3 EMERGENCY EQUIPMENT TABLE A Quantity- Description Yes o N_o Remarks 1

1 ea. 12" pipe wrench _

1 Assorted nails _

1 Black iron wire - roll _

2' Electrical tape - roll _

t 1 Hacksaw _

1 Nap of area surrounding the plant _

Security seal intact (Yes or No):

i TABLE B Quantity Description Yes & Remarks

, 1 Copies of TVA-REP and REP _

Implenting Procedures Document 1 First-aid kit -

3 MSA 401 self-contained breathing apparatus '

3 air bottles -

20 Coveralls -

10 Hoods 5 Emergency dosimeters and charger, with spare _

batteries 1 High volume air sampler _ _

.2 Flashlights w/ batteries ,_ _

i , 3, Fu11 face respirators with a cartridges _

a. v 1 Roll radiation rope

. I es. -Shovel f" l,,

.1 ea. 8# sledge hammer [

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~ Rope - 100' long _

2- ' One gallon polyethylene

' 2* *

-.d - bottles for drinking water _

7. l' Stretcher, stokes splint _

, % y l, . Plant personnel roster _

..n 37

'Vc(.Allequipmenthasbeeninventoriedwithdeficienciesnoted.

,~ ' n , . ,2 , -

+ '" Inspection Performed By:

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~ "- s: - ' Health Physics Represenative Date j :9 . ' , .

1 4 -Review and Approval:

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Health Physics Supervisor

~

, 9 Date dc

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,e SQNP j REP-IPD i SQN, IP-17

[_. Page 1 of'l

s. Rev. 6 ATTACHMENT 4 s EMERGENCY EQUIPMENT Date 1

[ ,

Location: Health Physics Laboratory - Service Building 4

Quantity Description Yes No Remarks-1 Alpha Survey Meter (500,000 cpm) _

Neutron dose rate survey meter

~~-'~'1

(.025 eV - 10 MeV)

(5,000 mR/hr) _

l [1 Teletector (1,000 R/hr with 13-foot extendible probe) _ _

4 Cutie Pie (10 R/hr) _

-1 Cutie Pie, high range 4

.(100 R/hr) 3 1 Cutie Pie (2.5 R/hr) 1 High Volume Air Sampler 4 RM-14 Survey Meters (0-50,000 cPa)

~

-1 -Low-volume air sampler _

~'

Inspection Performed By: -

Health Physics Representative Date i

Review and Approval:

I Health Physics Supervisor Date f

.' 't u 7

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.* . SQNP REP-IPD SQN, IP-17

(

Page 1 of 2 Rev. 6 ATTACHMENT 5 EMERGENCY EQUIPMENT Location: Meteorological Building The following equipment is stored in the meteorological building adjacent to the tower.

TABLE A Quantity Description Yes No Remarks 3 Clipboards with paper ___

L2 Pencils ___

2 Boxes of Smears with holders 1 Scissors __,

25 Soil sample bags ___

50 Paper bags ___ ___

50 Plastic bags ___ ___

1 Roll masking tape ___ ___

1 Roll of radiation and contamiation tape ___

20 Radiation and contamination tags 3 Pairs gauntlet gloves ___

5 Pairs short rubber gloves -

C-. 5 Canvas gloves Rubber overshoes 5 ___

-1 Map of area surrounding the plant ___

TABLE B Quantity Description Yes No Remarks NW 2 Flashlights with batteries _ _ _ ___

3 Pairs hip boots

.20 Sample bottles ___

First aid kit

- -.g-

,-31 .a tFull face masks 6 Canisters S Coveralls ___

. 5 Hoods

"; #; 1 :1; [ Roll radiation rope ___

t' ,1

_ . Plant personnel roster ___

?- 1 Dosimeter charger with batteries ___

~~

'10 _

High range dosimeters 1 (0-500 mrem) ___

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

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. v REP-IPD SQN, !P-17

y. Page 2 of 2

( Rev. 2

%- i ATTACHMENT 5 EMERGENCY EQUIPMENT NOTE; 1. Functionally test generator ~ ' ~ ~~

ReplSce dosimeter chgr batteries

~

2.

i

~~

Recharge dosimeters

~

..- _~

All equipment has been inventoried and deficiencies noted.

' Jespect!9n Performed By;

. Health Physics Representative Date

- Review and Approval:

Health Physics Supervisor __ Date N

e 9

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." . SQNP REP-IPD SQN, IP-17 Page 1 of 1

' ~. Rev. 6 Attachment 6 ADDITIONAL EQUIPMENT AVAILABLE FOR EMERGENCY USE Equipment in addition to that included in Attachments I through 5 and 8 is not specifically designated as emergency equipment, but is available for use in case of an emergency.

The following tabulation lists the equipment, the location, and quani.ity:

s

' Quantity Description Location 1 P.SA-401 Self conntained breathing apparatus Health Physics Lab, Service Building

20 MSA-401 Self contained breathing apparatus Turbine Building,

- El. 685, near Freight Lift.

- Inspection Performed By:

Health Physics Representative Date

- . Review and Approval:

. Health Physics Supervisor Date

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SQNP

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REP-IPD SQN, IP-17 Page 1 of 2 Rev. 6 ATTACHMENT 9 EMERGENCY EQUIPMENT

.Locatio':n ' Health .*hysics Emergency Vehicle - Van-The following equipment is stored in the health physics emergency van: ~

TABLE A -

' Quantity Desuiption Yes No, Remarks 20 Radiation tags _

20 Contamination tags _

I box 4" dia. air filters l' box 2" dia. air filters

' M 15 . Charcoal cartridges ($ Z)

Radiological survey fa'rms

[

4G 14 Airborne radiation survey _

forms

'7 Pencils _

3 Grease pencils 2 Log Books _ _

.2- Masking tape - roll _

1 Sample cutter _

'20- Plastic bags _

, 1 Mini-Scaler cable ~

2 pr. Rubber overshoes _

2 pr. Coveralls 4 6 pr. Canvas gloves-Rubber gloves

[

1 box _

_.1 pr. Scissors

, 6 ft. Syphon hose _

350 4" x 4" air filters for - -

monitors 30 Charcoal filters for environmentalmonitors _

. L. - Map of area surrounding plant _

-1' .

Plant boundary map

_+;< JL box: . Saran wrap _ j

^ ' f 1. , HP 260 probe and cable '

j

' -y~ _

L- g ,,;' ,

j s

7,'~ ,- S.ecurity seal' intact (Yes or No):

, )

y- ,

n W . -

TABLE B Quantity' l Description Yes No Remarks y?^[Q,f@k b[ g];,2 , ,

0 4m

., ' ,' Radiation tape - rolls _ . .

?C f? c;fe.

, c,.;Ngy.5C0.each 4 Smears and holders _

Flashlights w/ batteries i

..m.,. . ses, - - ' #ap.g2-s . - t 3C . - . Paper bags 1

j (Nb haN/ik 15 each. Sample bottles & boxes _

Extension cord

', ' N ., , .w cf100.ft.

! 1- Trouble' light _

l

! Self-contained breathing f . - JP) 2 -

j. :, . JC : capparatus

,.. g.m ._

, 4.

'cYy 1. q , , - .

17

, 1*. s g'; ,., ' ~. : s

c. ...

i. A , u.

. .y}$ N -

e -

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+ - . . . . ., w,,-,,,, , , , , - r. --,v.-y-- -,-. ,-y.

i

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g. . %

~ *. . . .-.

SQNP REP-IPD SQN, IP-17 Page 2 of 2 Rev. 6 ATTACliMENT 9 EMERGENCY EQUIPMENT TABLE B -

. Quantity Description Yes No Remarks M 20 Plastic Planchets ___.,

2 -Full face masks with canisters _

1 Portable gasoline powered generato. ___.

Functional test generator __

Y 4 Respirator canisters f (part. charcoal) __ ___

w F E%-

- .e

. - c

'.c 2, .

z.

.O'

,;m . y s -lI ,

,dyf':InspectionPerNrmedBy:

,w.- -

i 9 A, , . . .- .

? .

-Health Physics Representative Date ec,% cp.,

, j s ; 3_ . . . - .u- . -i 4.,r,6: ) ;. -' Revf ew'r and Approval:

. c.y ;, . s.

4,.. v m J, - . y y. ..

Date d.*J tre. "f ) - Health* .Physics .

Supervisor _

l i

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

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