ML20032B119

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Public Version of Original & Revision a to Emergency Plan Implementing Procedure EP-AD-2 Re Emergency Class Determination.Original Procedure Was Misdated,Through Administrative Error,As 810822
ML20032B119
Person / Time
Site: Kewaunee Dominion icon.png
Issue date: 10/21/1981
From:
WISCONSIN PUBLIC SERVICE CORP.
To:
Shared Package
ML111671010 List:
References
EP-AD-2-01, EP-AD-2-1, NUDOCS 8111040522
Download: ML20032B119 (50)
v • d • e


Text

S t k.n m e. d l WISC0tlSIfl PUBLIC SERVICE CORPORAfl0tl NO.

EP-AD-2

.Kewaunee lluclear Power Plant I

TITLE:

Emergency Class Determination EMERGEflCY PLAN IMPLE!iEllIlliG PROCEDURE DATE O2 I98)

PAGE 1

0F 25 REVIEWED BY 6I i

APPROVED BY MM 1.0 APPLICABILITY 1his procedure is to be used as guidance in determining the proper emergency classification listed below in order to activate the appropriate level of response from the Kewaunee fluclear Power Plant (KflPP) emergency response

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organization and offsite response organization.

1.1 Unusual Event - Events in process or have occurred which indicate a iiotential degradation of the level of safety of the plant.

No releases of radioactive material requiring offsite response or monitoring are expected.

1.2 Alert - Events in progress or having occurred which involve an actual

'or potential substantial degradation of the level of safety'of the plant. Any releases expected to be limited to small fractions of the EPA Protective Action Guideline (MG) exposure level.

1.3 _ Site Eccrgency - Events in progress or having occurred which involve actuar or ITkely major plant functions needed for protection of the public. Any release not expected to exceed EPA PAG exposure levels except near site boundary.

14 General EmerSency

' involve actual or - Events in progress or having occurred which imminent substantial core degradation or melting

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with potential for loss of containment integrity. Releases can be reasonably expected to cxceed EPA PAG exposure levels offsite.

2.0 PRECAUTIONS 2.1 All plant monitors ir.dicating emergency classification levels being exceeded, should be verified prior to declaring an emergency class.

3.0 REFERENCES

3.1 KilPP Emergency Plra 3.2 EP-AD-1, Plant Emergency Organization 8111040522 811028 PDR ADGCK 05000305 F

PDR i

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WISCONSIN PUBLIC SERVICE CORPORATION 1

NO.

EP-AD-2 Kewaunee Nuclear Power Plant TITLE:

Emergency Class Determination EMERGENCY PLAN IMPLEMENflNG PROCEDUPE AUG 2 2 ?]G PAGE 2

0F 25 DATE 4.0 INSTRUCTIONS 4.1 During abnormal plant conditions, refer to Table EP-AD-1.1, Emergency Classifications, and the applicable chart to determine if a plant emergency exists.

4.2 If a plant emergency exists, perform the required actions of the respective emergency action level procedures listed below:

4.2.1 EP-AD-3, Unusual Event 4.2.2 EP-AD-4, Alert 4.2.3 EP-AD-5, Site Emergency 4.2.4 EP-AD-6, General Emergency 4.3 As plant conditions change, or the emergency condition is stabilized,

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continue to refer to the Emergency Classification tables to determine' if the emergency should be reclassified.

4.4 If the plant has been brought to a condition below the emergency classification level, the emergency can be terminated.

4.5 If plant conditions are stabilized and no further degradation is inminent, however, conditions reaain above the emergency action level, plant recovery operations can be initiated.

See EP-AD-15.

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EP-AD-2 Page 3 of 25 Mjr; 991981 TABLE I:P-AJ 2.1 EPERGENCY CL'cSIFICATI0fiS, The following charts are separated into different abnormal operating conditions which may, depending upon their severity, be classified as an Unusual Event, Alert, Site Emergency, or General Errergency.

CHART PAGE Abnormal Radiological Effluent A

4 Fuel Damage Indication 11 8

Primary Leak C

9 Primary / Secondary Leak D

10 Loss of Power E

11

t. qineerd Safety Feature Anomaly F

12 Fiac and Fire Protection G

13 Loss of Indication 11 14 Security Contingency 1

15 Primary System Anomaly J

16 Secondary Side Anomaly rs 17 Miscellaneous Abnormal Plant Conditions L

18 Personnel Injury M

20 Earthquake H

21 '

Flood, Low Water or Seiche 0

22 Tornado or liigh Winds P

23 External Events Q

24 Auxiliary Building Stack High Range Monitor Reading versus Release Duration assuming most adverse meterology for Emergency Class determination Fig.

EP-AD 2.1 9

9 p

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4-%

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--.%.w.

L TABLE EP-AD 2.1 CHART A 1

f ASNORMAL RADIOLOGICAL EFFLUENT EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP-INDICATION I

EE Radiological Effluent Technical Specification UNUSUAL Instantaneous Releases NO limits exceeded.

EVENT

'd e 1 SV Exhaust Fan R-13 > 50,000 CPM R-14 > 125,000 CPM e

i5%

,i 2 SV Exhaust Fans R-13 > 25,000 CPM R-14 > 60,000 CPM.

l Batch Release 4

I See TS Section 3.9 Radiation levels or airborne contamination Containment R-2 > 6 R/hr l

which indicate a severe degradation in the ALERT R-llZSE6 CPM

!(ontrol or radioactive materials.e.g. radiation levels jump Sy factor of 1000) id R-12 > 4E5 CPM l

Charging Pump Area P.-4 > A00 mR/hr i

i Fuel liandling Area -

R-5 > 8 R/hr Radiological effluents greater than 10 times

'l SV Exhaust Fan R-13 > 500,000 CPM

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Technical Specification instantaneous limits.

ALERT R-14 > 0FF SCALE 2 SV Exhaust Fans R-13 > 250,000 CPM R-14 > 600,000 CPM l

Effluent monitors detect levels corresponding SITE 1 SV Exhaust Fan Refer to Figure to greater than 50 mr/hr for 1/2 hour or -

EMERGENCY EP-AD 2.1 greater than 500 mr/hr W.B. for two miiiutes at the site boundary for " adverse meteorology".

2 Exhaust Fans Refer to Figure EP-AD 2.2.

Obtain average monitor reading and actual or projected release time. The intersec-tion is the Emergency Classification.

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1

TABLE EP-AD 2.1 CHART A (cont'd) l E5 ABNORMAL RADIOLOGICAL EFFLUENT C$

or

,m et

!5 to l] gjj EFERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION

a m

Projected or measured in the environs SITE Projected or measured dose rates to be provided by dose rates greater than 50 mr/hr W.B.

EMERGENCY the onshift ilP, Rad. Protection Director or Environ for two minutes at the site boundary.

mental Monitoring Teams.

Effluent monitors detect levels cor-Establish worst case projected dose rates by:

responding to greater than I rea/hr GENERAL W.B. cr 5 rea/hr thyroid at the site EMERGENCY l SV. Exhaust Fan - refer to figure EP-AD 2.1

. boundary under " actual ceteorological" 2 SV Exhaust Fans - refer to figure EP-AD 2.2 Co r.di tio ns.

Determine dose levels for actual meteorological conditions by correcting for wind direction.

Dose Level = (Worst case dose) (Wind Dir. factor)

Wind Dir. Factor = 0 if wind is frcm 225* to 315*

= 1 if wind is fran any other direction NOTE: No Protective Action Recommendations are to be made unless the projected dose is 10 greater than Gen. Emergency level indicated on figures EP-AD 2.1 and EP-AD 2.2; then recommend Sheltering for sector (22.5*) in olume oath.

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TABLE EP-AD 2.1 CHART 3

!l FUEL DAMAGE INDICATION h co

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3p,,

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CLASSIFICATION KMPP INDICATION i

52 '

. EMERGENCY CLASSIFICATION CRITERIA a

N EE U" USUAL Exceed Technical Specification 3.1.c.

fjaximum A

High ceactor coolant activity saraple EVENT.

, Coolant Activity determined by reactor coolant sample analysis. Activity greater than 91/E.

j l

i Failed' Fuel monitor indicates greater R-9 reads grea arr than 10 R/hr and is verified by than 0.1% equivalent fuel failures UNUSUAL portable instrument mea'surament.

i lwithin 30 minutes.

i EVENT i

R-9 indication is off scale, and laboratory Severe Loss of Fuel Cladding

~

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a. Very high coolant activity sample ALERT l~ equivalent.
5. Failed fuel monitor indicates greater than 1% fuel failures

[

within 30 minutes or 5% total fuel failures.

Fuel damage accident with release of Containment R-ll > SE6 CPM radioactivity to containment or ALERT R-12 > 4E5 CPM auxiliary building.

Aux Bldg R-13 > 2.5E5 CPM R-14 > 6ES CPM

' Major damage to spent fuel in SITE Same monitor readings as above plus large object containment or auxiliary buildi. 3 EMERGENCY dropped in Ractor Core or Spent Fuel Pool or loss of water level below spent.'uel level,

  • 1 ~~

.s TABLE EP-AD 2.1 C.! ART C b

PRIMARY LEAX TO LOCA

'S EMERGENCY CLASSIFICATION CRITERIA CLASS UICATION XNPP INDICATION u m T f

' Exceeding Reactor.taclant System UNUSUAL' Any reactor shutdown required by Technical

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7 leak rato Technical Specifications EVENT Specification, Section T.S. 3.1.d.

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requiring reactor shutdown.

'a.

c Reactor Coolant System leak ra'e Reactor Coolant System mass bala. ice calculations greater than.50 -GPM.

ALERT performed by SP-36-082 indicate leakage greater than 50 GPM.

4 Reactor Coolant system leakage SITE Large Break greater than make-up pump capacity EMERGENCY SI system is acti/ated and indications are verified per Emergency Operatins Procedure E-0-07.

Small Break

_RCS system pressur e can be stabilized above 1000

)

l psig and SI pump flow is greater than 200 GPM as indicated by flow meter or RWST level decreasc.

(1) Less of Coolant Accident with (1) LOCA is ver',fied per Emergency Operating (2) Initial or subsequent failure Procedure E-0-10.

of ECCS, and (2) ECCS failure is indicated by:

(3) Containment failure or potential GENERAL

- SI and RHR pumps not running or no flow to EMERGENCY the reactor vessel indicated.

failure exists

- Incore thermocouples indicate greater than 1800 F (I&C resistance measurements).

or

~

- Subcooling meter is zero or negative.

Loss of 2 of 3 fission product barriers with a potential loss of (3) Failure or potential failure of containment is 3rd barrier, indicated by:

- physical evidence of containment structure damage.

- Loss of all Fan Coil un its and both trains of Containment Spray.

- Containment pressure exceeds 46 psig.

TABLE EP-AD 2.1 CHART 0 PRIMARY T0 SECONDARY LEAK

$g El

't; a N

4 o

- c:

i aa EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION XNPP INDICATION r? <

Exceeding Primary to Secondsry lea'K Any reactor shutdown required by T.S. 3.1.d.2.

rate Technical Specification placing UNUSUAL

' the plant under a limiting ccr.dition EVENT

'j for operat. ion.

.j Rapid gross failure of one steam R-15 goes off scale high within 30 minutes, con-generator tube with loss of offsite ALERT firmed by R-19 increasing by a factor of 1000, or

. power.

verified by S/G cheraistry gross beta /gama sample a nalysis.

-olus-

~ All three transformers: Main Aux., Reserve Aux.,

and Tertiary, are de-eargized.

Rapid failure of multiple steam ALERT R-15 goes off scale high within 30 minutes, con-9:ncrator tubes.

firmed by R-19 increasirg by a factor of 1000, or verified by S/G chemistry gross beta / gamma sample analysis.

- pl us-Primary to Secondary leak rate greater than 800 GPM

_ as indicated by SI pump flow or RKST level change.

Rapid fallaure of steam generator SITE All 3 above indicators are present:

tubes with loss of offsite pover.

EMERGENCY (1) Secondary side activity increase (2) Primary to Secondary flow > 800 GPM (3) All three tranformers are de-energized

~...

-.g, t,

z

.i 0

, ~,

TABLE EP-AD 2.1-C]4

- _f

~

~'

CHA'F E

~ t

' 0SS OF POWER y

c - en s.. -

,- n - en we o.

~. '.t.

vw r-s 5 ' F4 E EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION y pc UNUSUAL All three' transformers: Main Aux, Reserve Aux, Loss cf offsite power

- o r-EVENT and. Tertiary are de-energized.

L$ss of onsite AC power capability.

~~

- o r-Both Emergency Diesel, Generators are inoperable.,.

x.

Buses 1 througi11-6 are 'de-energized, inclu' ding.

Loss of'offsite power

-and-(short term)

ALERT the D/G supplies to buses 1-5 and 1-6.. AC power. -

~.

Loss of onsite AC power is' restored to bus 1-5 or 1-6 within ;15 minutes._ -

Loss of offsite ;iower l

SITE Buses.1-1: through 1-6' are 'de-energized ; including --

- a nd-.

(long term)

EMERGENCY the D/G supplies-to buses 1-5 and.1-6 for longer Loss of onsite AC power than 15 minutes.. -

Loss of all vital onsite DC power for SITE Low voltage iockout or'de-energized condition on-more than 15 minutes.

EMERGENCY all four DC distribution ~ cabinets:

BRA-113.~c BRB-ll3

~

BRA-ll4 BRB-ll4 -

~

~

Failure of offsite and onsite AC power

  • uses l'-f through I d are.de-energized. including J

-and-

~ '

GENERAL tiie D/G~ supplies to buses 1-5-and 1-6~.,

Total loss of Auxiliary Fcedvater EMERGENCY

.-and-.

z.

=akeup capability for:

Loss of the iurbine driven 4 AW pu=p. '

Greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

~

^

~~

~

Conditions exist for '. great' r tha:tz 2 thours.

e (Loss cf powcr plus loss of AFW S

~

would lead to fuel clad failure-

.13 and potential containment. failure) a 9

e,[

y

=

c "

}*

R

~,

F TABLE EP-AD 2.1 l

CHART F E5 CNGINEERED SAFETY FEATURE ANOMALY m

CD m

T c9

  • a u

m 4

to T

h if-

$s 2

EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION l

Safety Injection Sequence has been initiated, and Emergency core cooling initiated UNUSUAL and discharged to the reactor vessel.

EVENT either the SI pumps or RHR pumps have caused an unplanned injection of core cooling water into reactor vessel. This should be verified by system flows, comparison of discharge pressure versus RCS pressure, and/or BA/RWST level changes.

Loss of engineered safety feature UNUSUAL Any shutdown required by T.S. Limiting Conditions

. function requiring shutdown by EVENT for Operation, Section 3.3, Engineered Safety Technical Specifications.

Features and Auxiliary Systems.

Complete loss of any fuention required ALERT Loss of operability of both trains of RHR for core cooling if the steam generators are unable l

for cold shutdown.

to be utilized.

1 l

i

-! Failure of the Reactor Protection Failure of the reactor protection system to initiate 4

System to initiate and complete a ALERT and complete a reactor trip when required.

(e.g. A i

scram which brings the reactor turbine trip from full power without reactor trip.

t Indication would be increasing reactor coolant subcritical.

system pressure leading to lifting of pressurizer relief valves.)

Complete loss of any function needed SITE Tntal of all auxiliary and main feedwater systems for plant hot shutdown.

EMERGENCY (e.g. loss of both feedwater pumps and all three auxiliary feedwater pumps) when the primary system temperature is above 350*F.

l 1

s

l i

l

. ^

TABLE E?-AD 2.1 CHART G

[

FIRE AND FIRE Pf3TECTION I

6 L$hk j'

l e.

l ei

! g e2' EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION

., cc 5f53 Loss of Fire Protection System func-UNUSUAL Kewaunee has no Technical Specifications which l

tion requiring shutdown by Technical EVENT require shutdown with loss of a fire Protection S,cacifications.

System function.

l l

'l l

i A fire within the plant lasting mere UNUSUAL A fire within the Administration Building, Turbine than 10 ' minutes.

EVENT Building, Warehouse, Auxiliary Building, or i

Containment Building lasting more than 10 minutes, i

A fire potentially affecting safety ALERT A fire within the Auxiliary Bldg., Safeguards systems.

alley, D/G rocas or Screenhouse lasting more than-

-I 10 minutes that causes ESF equipment to be i

inoperable.

i A fire compromising the functions SITE A fire within the Auxiliary Bldg., Safeguards of safety systems.

EMERGENCY alley, D/G rooms or Screenhouse that has rendered both trains of ESF equipment that is needed to-bring the plant to ' hot shutdown inoperable.

e 4

f O

i

I TABLE EP-AD 2.1 CHART H NE LOSS OF INDICATION

,5D O ce N

Z" k,

ON

?

ac a

$i S

EMERGENCY CLASSIFICATION CRITERI A CLASSIFICATION KNPP INDICATION _

Indications or alarms on p'rocess or Refer to Technical Specification Sections 3.3, effluent parameters not functional UNUSUAL Engineered Safety Features and Auxiliary Systems, in' Control Room to an extent requir-EVENT 3.5, Instrumentation System, and 3.10, Control Rod t

ing plant shutdown or other signi-and Power Distribution Limits, to determine if plant i

I ficant loss of assessment shutdown is required.

capab il,i ty.

{

(ar.nur.ci ators)

ALER:

ictal loss of Annur.ciator System, Computer Alarms,

. ics..'r all alarms and Sequence of Events Recorder.

Mos' a

Most or all alarms (annunciators)

SITE Total loss of Annunciator System, Computer Alarms, lost and a plant transient initiated EMERGENCY and Sequence of Events Recorder with an uncontrol-l or in progress.

led plant transient in progress or initiated during the loss.

4 a

TABLE EP-AD 2.1 g 55 -

CHART I-

w. 50 SECURITY CONTINGENCY c. :q.

. 0 c4 o L3 5.55 j'

EMERGENCY CLASSIFICATION CRITERIA

' CLASSIFICATION

.KNPP INDICATION Security threat or attempted entry UNUSUAL Examples: - Bomb threat accompanied by interception or attempted sabotage.

EVENT of bomb' material s.

~

- Adversary intercepted in the protected

~

area.-

- Undetonated bonb found on premises.

L Ongoing security compromise.

ALERT 1 Examples: - Armed attack on plant.

,f

- Bomb detonated within the protected.

I area.

Imminent loss' of physical control SITE Example: - Armed' intruders within protected area j

of the plant.

. EMERGENCY-about to enter Control Room.

. l~

u 4

+

.i.

.l:

I

[

TABLE EP-AD 2.1

~

CHART J m '$

PRIMARY SYSTEM ANOMALY-N Q

L3 e

i eA

'b F

EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION Abnormal coolant temperatu're and/or Technical Specification section T.S. 2.1 limits.

pressure UNUSUAL exceeded.

Indications:

- o r-EVENT

- RCS pressure vs'Tave exceeds Figure T.S. 2.1-1 abnormal fuel temperatures exceeding

- Subcooling meter indicates zero or negative.

- o r- -

Technical Specification 1imits.

Technical Specification T.S.':3.10.b.

Limits

.I-exceeded.

Indications:

- delta flux indication exceeds Figure T.S. 3.10-6

- Control rod insertion limits ^ exceed l

Figure T.S. 3.10-4.

t Coolant pump seizure leading to ALERT Primary flow transient and subsequent fuel failure:

fuel failure.

indicated by:

- Zero' indication on one.RCS loop flow

- Overpressurization of RCS and relief valve lift-l ing causing PRT temp and pressure alarms

- R-9 indicates greater:than 10 R/hr, veri ied by -

RCS sample ' analysis b

n t

1 l

i l

i 1

TABLE EP-AD 2.1 CHART X SECONDARY SIDE ANOMALY _

c5 i

N Ch l

EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION

'u h

515$

' Turbine rotating component fv ture UNUSUAL A failure of the turbine resulting in an immediate i

i Si S*

causing rapid plant shutdown EVENT shutdown and/or overspeed condition and for which turbine repair requires major disassembly.

l l

iRapid Depressurization of the UNUSUAL The uncontrolled depressurization of the secondary t

EVENT system to the point where automatic safety injection t

. secondary side.

is initiated (less than 500 psig steam generator j

pressure).

l Ster.m line break with significant ALERT Main steamline break that causes ECCS actuation (greater than 10 GPM) primary to

. (less than 500 psig S/G pressure)

-and-secondary leakage.

R-15 or R-19 reading.a factor of 1000 above. normal, verified by S/G chemistry sample analysis

-or-RCS to S/G Icakage verified by mass inventory

>10 GPM.

i jMainsteamlinebreakthatcausesECCSactuation t

Steam line break SITE (less than 500 psig S/G pressure) with Primary to Secondary leak >50 GPM EMERGENCY

-and.

i

. R-15 or R-19 readings offscale, verified by S/G" and chemistry sample analysis i

Indication of Fuel-Damage

- o r-

. ~

" RCS to S/G leakage verified by mass inventory l

~

> 50 GPM

-and R-9 indication >10 R/hr and verified by RCS chemistry sample analysis.

+

l

(

l a_

_ TABLE EP-AD 2.1

~

N m E2 CHART L u

,'?

N Ii e

CD MISCELLANEOUS ABNORMAL PLANT CONDITIONS m@

af l4

a i.

I-EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION t

loss of containment integrity UNUSUAL-Refer to T.S. Section 3.6 to determine if shutdown

[.

requiring shutdown by Technical EVENT is required.

Specifications.

l a

l L

~ Conditions at-the discretion of the Emergency Other plant conditions that warrant increased awareness on the part of UNUSUAL Director or his designated alternate. Examples j.

plant staff or state and/or local EVENT include cooldown rate exceeding T.S. limits or

.t-authorities, and requires plant pipe crack found during operation.

shutdown under Tech. Specifications.

f 1

Evacuation of Control Room antici-Evacuation of Control Room.(E-0-06) with control pated or required with control of ALERT at shutdown panel.

4 shutdown system established from local stations.

t Evacuation of Control Room and control SITE Evacuation of Control ' Room (E-0.-06) and failure to of shutdown systems not established-EMERGENCY establish control at shutdown panel within 15 i

i from local stations.

minutes.

.j I

l

f

,i L

TABLE EP-AD 2.1

. L g._

CHART L (cont'd) 1 m ER c-g[

$ *j.

-MISCELLANE0US ABNORMAL PLANT CONDITIONS

- E-o c3 hh EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION i-Two fission product barriers are lost with the.

Other plant conditions th5t cake a release of large amounts of *adic-potential or probability of losing the third activity in a short time period GENERAL barrier. ( At least one verified indication in each pcssible, e.g. any core melt EMERGENCY category below.)

situction Indications:

Containment boundary potential failure Examples:

- pressure >46 psig

- Failure of Main FW and AFW systems

- loss of containment cooling systems for extended period without ECCS RCS boundary

' flow. Plus a. containment failure

- no-ECCS flow

- failed open relief or Safety valve with'no is imminent.

- Transient requiring the operation isolation. capability of shutdown systems with a failure

- RCS break cf these shutdown systems.

In Fuel Cladding addition failure of ECCS and

- R-9 >-10 R/hr containment failure is imminent.-

- RCS chemistry analysis 4

ye-M

)

~

'S e

r h-L_

m

t C

TABLE EP-AD 2.1 CHART M cn T

oN PERSONNEL INJURY y

5 o

~

c cJ

=

l4-w EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION Transportation of coni.aminated and UNUSUAL Sel f-explanatory seriously injured individual from EVENT site to an offsite: hospital.

- 1 I

r 1,

l j

l

. ;... y i

1

.f- ~

j.

I l

t

b I ;,

l TABLE EP-AD 2.1 E.S

~

CHART N p

O g: g j EARTHQUAKE jl I.

!@ '.jfEi

~

l c CD lf EMERGENCY CLASSIFICATION CRITERIA

. CLASSICICATION KNPP INDICATION j

Any earthquake felt in plant or UNUSUAL Activation of seismic recorder (Annunciator 1-45)

L detected.on station seismic EVENT with EVENT light lit in relay-room instrumentation.

-and-

.L,

l Verified by actual physical ground shaking or by _

contacting Dr. David Willis, U.' of W.;(Milwaukee) l seismic' center, at'l-414-963-4602.

l i.

An earthquake greater than OBE ALERT Activation of seismic ~ recorder (Ann.1-45) with l

Operational Basis Earthquake.

horizontal EVENT and LO. lights lit in relay room

..: - a nd-l 0.069 horizontal ground acceleration experienced at site. Verified by contacting Dr. David Willis, at 1-414-963-4602.

j.

LAn carthquake greater than'SSE Safe SITE Activation of seismic recorder (Ann.1-45)Lwith L

Shutdown Earthquake.

EMERGENCY EVENT, HUD and HI lights. lit in relay room

. -and.

0.129 horizontal ground acceleration experienced; at site.' Verified by contacting Dr.- David Willis at 1-414-953-4502.

_ ~,.

l l

l j-y n

4

9-

'V I

TABLE EP-AD 2.1

~

CHA?.T 0 d

p e-3 FLOOD, LOW WATER, OR SEICHE

'l j-t NN cc n

o

.f' CC O

- h.

5#

EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION

.' h t:

~

50 year flced, icw water or seiche UNUSUAL High water level above 580 feet. Low forebay water

' N EVENT level condition that cannot be cleared by stopping the circulating water system. Wave greater than 18 feet.

p i

. l. '.

l Flood low water, or seiche near

-Design High Water Level = 582 feet design levels.

ALERT i

. f, -

. Design Low Water Level

= 575 feet.

Design Deep Water WAVE = 22.5 feet, i

. i.

.l, 4

,e h

l:

.~-

l

.V:

e-e t

E t

TABLE EP-AD 2.1 CHART P ERNADO OR HIGH WINDS n

n oa

~

f

" e2

. I I

NC s(

'c E E.MERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION c.

n x

. l j

(

UNUSUAL A tornado within sight of the plant which has caused.

(.

Any tornado on site the loss of at least one of the offsite transmission - ?

EVENT

'U lines.

r Any tornado striking #acilit.

ALERT A tornado which strikes the facility and'causes.

damage that affects the continued safe operation-gr *Hs punt.

h Sustained winds in excess of design SITE Winds in excess of 100 mph for greater than i hour, i levels with plant not in cold EMERGENCY l

i jshutdown

+,

d e

i j

' I-

.\\

f' F

l

! ' l l

l l

- l I

i,

' l

^

Y

TABLE EP-AD 2.1 CHART 0 6

EXTERNAL EVENTS N

l

$Y "c%

Q o2,

J f

[

EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION Aircraft crash onsite or unusual UNUSUAL An aircraft crash within the site boundary aircraft activity ~over facility.

EVENT or notification from the security force or i

A other source of higher than normal aircraft activity over the site.

l I

.1 Aircraft crash on facility ALERT An aircraft crash into plant buildings or switchyard which affects plant operation.

i-Missile impact from whatever source ALERT A missile strikes the facility which affects on facility.

plant operation..

Entry into facility environs of ALERT Release of toxic or flamable gas from ~a ruptured -

uncontrolled toxic or flamable gases, container such that the gases enter the plant protected area or buildings.

Known explosion damage to facility ALERT Self-explanatory affecting plant operation.

3 Aircraft crash affecting vital SITE An aircraft crash into plant buildings which causes structures by impact or fire.,

EMERGENCY the loss of Engineered Safety Features required to bring the plant to hot shutdown conditions.

4 l

~

s a

+>

TABLE EP-AD 2.1 CHART 0 (cont'd)

F:

.i; EXTERNAL EVENTS

'jf i

,i l!

c--

si neo uSE

li s

o s;

. c *'t.

no

=ca g

d

, j2 EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION b

1, Severe damage to safe shutdown equip-SITE A missile: strikes plant buildings'or. explosion ment fro:a missiles or explosion EMERGENCY occurs within a plant building which causes the loss of Engineered Safety-Features required to' bring the plant to hot shutdown conditions.

h.-

b J

Entry of uncontrolled flammable Release of. flammable or toxic gas from a ruptured gases into vital area, or entry of SITE container which enters. vital areas asidescribed 7

uncontrolled toxic gases into. vital EMERGENCY at left. Portable-Hg monitor detects explosive t' -

I areas where lack of access to the concentration of H2 in vital' area.

I l

area constitutes a safety. problem.

[

.c

'l l

NY i

+, " - j- ? '.' e r

~

E"

%.b,,

o

'k"-

~i". ",'

~

~

,i i

^. ';*

{!,

.ie 1

1; H-i' ; I' i

~

-. -.~-

7 rho.c.hmint A 4

W15C0riSIli >0BLIC SERVICE C0dP0 RATION I

NO.

EP-AD-2 REV. A Kewaunce Nuclear Power Plant TITLE:

Emergency Class Determiration EMERGENCY PLAN IMPLEMENTII;G PROCEDURE DATE OCT 2 1 1981 PAGE 1

0F 25' REVIEWEDI! NNb APPROVED P'!

1.0 APPLICABILITY This procedure is to be used as guidance in de'.ermining the proper e.nergency classification listed below in order to activate the appropriate levei of response from the Kewaunee Nuclear Power Plant (KNPP) emergency response organization and offsite response organization.

1.1 Unusual Event - Events in process or have occurred which indicate a potential degradation of the level of safety of the plant.

No releases of radioactive material requiring offsite response or monitoring are expected.

1.2 Alert - Events in progress or having occurred which involve an actual or potential substantial degradation of the level of safety of the plant. Any releases expected to be limited to siaall fractions of the EPA Protective Action Guideline (PAG) exposure level.

1.3 Site Emergency - Events in progress or having occurred which involve actual or imminent loss of major plant functions needed for protection of the public. Any major releases exceeding Technical Specification release limits but not expected to exceed EPA PAG exposure levels except near site boundary.

l.4 General Emergency - Events in progrest or having occurred which involve actual or imminent substantial core degradation or nelting with potential for loss of contain:nent integrity. Releases can be reasonably expected to exceed EPA PAG exposure levels offsite.

2.0 PRECAUTIONS 2.1 All plant monitors indicating emergency classification levels being exceeded should be verified as to their validity prior to declaring an emergency class.

3.0 REFERENCES

3.1 KNPP Emergency P1an 3.2 EP-AD-1, Plant Emergency Organization

I o

.4;

-WISCONSIN PUBLIC SERVICE COR'PORATI0tl I

NO.

EP-AD-2 REV. A Kewaunee Nuclear Power Plant TITLE: Emergency Class Determination EMERGENCY PLAft IMPLEMENTING PROCEDURE DATE.00T 2 1 1981 PAGE- ~ 2 0F 25/ '

4.0 INSTRUC110!I5 4.1 During abnormal plant conditions, refer to Table EP-AD-2.1,. Emergency-Classifications, and the apolicable chart to determine if a plant-emergency exists.

4.2 If a plant emergency exists, perform the ' required actions of.the respective emergency action level procedures listed.bt-low!

4.2.1 -EP-AD-3, Unusual Event 4.2.2 EP-AD-4, Alert 4.2.3 EP-AD-5, Site Emergency 4.2.4 EP-AD-6, General Emergency 4.3 As plant conditions change, or the emergency condition is stab!!ized,-

continue to refer to the. Emergency Classification tables to determine if the emergency should be reclassified.

4.4 If the plant has been brought to a condition below all the emergency classification levels, the emergency can be terminated.

4.5 If plant conditions are stabilized and no further degradation is imminent, however, conditions remain above the emergency action level, plant recovery operations should be initiated, per EP-AD-15.

l t

i

EP-AD-2 OCT 911981 Page T of zu

-. TABLE EP-AD-2.1-EMERGENCY CLASSIFICATIONS

- The following charts are separated into dif ferent' abnormal operating conditions l

which may, depending-upon their severity, Hbe classified as an Unusual Event -

Alert,- Site Emergency, or General Emergency.

CHART PAGE Abnormal Radiological Effluent A

4 Fuel Damage Indication B

8 Primary Leak to LOCA C-9 Primary / Secondary Leak D

10-Loss of Power E

11 Engineered Safety Feature Anomaly F

12 Fire and Fire Protection G

13

[

L'oss of Indication H

14 Security Contingency I

15 4

- Primary System Anomaly J

16 Secondary Side Ananaly K

17 1

Miscellaneous Abnonnal Plant Conditions L

18

- Personnel Injury M

20 Earthquake N

21 Flood, Low Water or Seiche 0

22 Tornado or High Winds P

23 External Events Q

24 Auxiliary Building Stack High Fig. EP-AD-2.1 6

Range Monitor Reading versus and Release Duration assuming most Fig. EP-AD-2.2 7

adverse meterology for Emergency Class detennination

4 3

TABLE EP-AD-2.1 CHART A

~ ABNORMAL RADIOLOGICAL EFFLUENT E!ERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION i

! Radiological Ef fluent Technical Specification UNUSUAt.

Instantaneous Releases

limits exceeded.

EVENT i

1 SV Exhaust Fan R-13 > 50,000 CPM l

-R-14 > 125,000 CPM 2 SV Exhaust Fans R-13 > 25,000 CPM j

.R-14 J. 60,000 CPM Batch Release See Tech Specs Section 3.9

) Radiation levels or airborne contamination Containment R-2 > 6 R/hr iwhich indicate a severe degradation in the ALERT R-ll i 5,000,000 CPM

! control or radioactive materials.

R-12 I 400,000 CPM l(e.g. radiation levels suddenly increase iby a factor of 1000)

Charging Pump Area

'R-4 >'600 mR/hr 3

Fuel H'andling Area R-5 J 8 R/hr

?

Q Radiological effluents greater the i 10 times 1 SV Exhaust Fan R-13 J_ 500,000 CPM

! Technical Specification instantaneous limits.

ALERT R-14 > 0FF SCALE-4

~,

2 SV Exhaust Fans R-13 >'250,000 CPM

'"5 R-14 J_ 600,000 CPM 58

~

1

~

TABLE EP-AD-2.1-CHART A (cont'd),

ABNORMAL RADIOLOGICAL EFFLUENT EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION Effluent monitors detect-levels corresponding SITE l SY Exhaust Fan Refer to Figure EP-AD-2.1 to greater than 50 mr/hr for 1/2 hour In:

EMERGENCY greater than 500 mr/hr whole body for two 2 Exhaust Fans Refer to Figurc EP-AD-2.2 minutes at the site boundary for " adverse meteorology."

Obtain average monitor reading and actual or projected release duration. The intersec-tion is the Emergency Classification.

Projected or measured in the environs SITE Projected or measured dose rates to be provid2d by dose rates greater than 50 mr/hr whole body EMERGENCY the.onshif t HP,. Rad. Protection Director or Environ for two minutes at the site boundary.

mental Monitoring Tea:ns.

Effluent monitors detect levels cor-Establish worst case projected dose ' rates by:

responding to greater than 1 rem /hr whole GENERAL body or 5 rem /hr thyroid at the site EMERGENCY l SV Exhaust Fan - refer to figure EP-AD-2.1.

boundary under " actual meteorological" 2 SV Exhaust Fans - refer to figure EP-AD-2.2 conditions.

Determine dose levels for actual meteorological condit. ions by correcting:for wind direction.

Dose Level = (Worst case dose) (Wind.Dir. factor)

Wind Dir.. Factor = 0 if wind is fraa 225* to 315*

= 1 if wind is fran any other

%pj.

direction s

H01E:

Evacuation reconnendations should not geo be made unless the projegted dose is 10 ra o

times greater tnan.2en. tmergency levei l m __.

c=

indicated on Figures EP-AD-2.1 and EP-AD-2.2,-

. DOE; then recommend Sheltering for the Sector

.l 4

U p! w p?th.

EP-AD-2 Pags 6 of'25 0CT' 211981 FIGURE ~EP-AD-2.1 ENERCENCY CLASS DETERMINATION VITH 1 ZONE SV EXHAUST FAN OPERATING 10,000

'*"*m 5 - ' ***

"~r*-'-'

E 7

i, t iii. i m s i n 6

,.p..,,

. j n ;,n p.,

2,..-

5 CENERAL EMERCENCY

_ +.... -

0

?-. N,.

' W WJ-

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.H EP-AD-2 OCT 2 1 1981

^

Page 7 of 25 FIGURE EP-AD-2.2.

..c DERGENCY CLASS DETERMINATION WITH 2 ZONE SV EXI!AUST FANSEPERATING.

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TABLE EP-AD-2.1 CHART B FUEL DAMAGE INDICATION EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION High reactor coolant activity sample UNUSUAL Exceed Technical Specification 3.1.c.

Maximum EVENT Coolant Activity determined by reactor coolant sample analysis. Activity greater than 91/E.

Failed Fuel monitor indicates greater R-9 reads greater than 10 R/hr and is verified by than 0.1% equivalent fuel failures UNUSUAL portable instrument measurement.

within 30 minutes.

EVENT Severe loss of Fuel Cladding R-9 indication is off scale, and laboratory analysis confirms greater than 300 uCi/ml of I-131

a. Very high coolant activity sample A'iRT

_ equivalent.

b. Failed fuel monitor indicates greater than 1% fuel failures within 30 minutes or 5% total fuel failures.

Fuel damage accident with release of Contain.nent R-11 > SE6 CPM radioactivity to containment or ALERT R-12 i 4E5 CPM cuxiliary building.

$ c3m e

co?

Aux Bldg R-13 > 2.5ES CPM R-14 i 6E5 CPM

Major damage to spent fuel in SITE Same monitor readings as above plus large object

"[$

containment or auxiliary building EMERGENCY dropped in Reactor Core or Spent Fuel Pool or loss of water level below spant fuel level.

(more than 1 spent fuel ele:nent denaged)

,w-...

a-

=

\\

1 TABLE EP-AD-2.1 CHART C PRIMARY LEAK TO LOCA i

i : EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION Exceeding Reactor Coolant System UNUSUAL Any reactor shutdown required by Technical leak rate. Technical Specifications EVENT Specification, Section T.S. 3.1.d. Indicated requiring reactor shutdown.

leakage may be deternined using Reactor Coolant System mass balance calculations performed by SP-36-082.

Reacto' Coolant System leak rate Charging versus letdown indications indicate an r

greater than 50 GPM.

ALERT unidentified leakage > 50 GPM.

1 Reactor Coolant system leakage SITE Large Break

. greater than make-up pump capacity EMERGENCY SI system is activated and indications are verified per Emergency Operating Procedure E-0-07.

Small Break RCS system pressure stabilizes above 750 psig and SI pump flow is indicated by flow meter or RWST level decrease.

(1) Loss of Coolant Accident with (1) LOCA is verified per Emergency Operating (2) Ini'tial or subsequent failure of

-Procedure E-0-10, -and-ECCS, and (2) ECCS failure is indicated'by:

(3) Containment failure or potential

-SI and R!iR pumps not running or no-flow to failure exists, EMERGENCY the reactor vessel indicated.

- Incore thennoccuples indicate greater than or 1800 F (I&C resistance measurecents).

g c=> g ~

- Subcooling meter is zero or negative, j fj s Loss of 2 of 3 fission product

-and-

?

ee3 barriers with a potential : loss of (3) Failure or potential failure of containment is e s. " -

3rd barrier.

indicated by:

- physical evidence of containment structure -

NES.

damage, or

- Loss of all Fan Coil units and both trains of Containment Spray, or

_ rantairment prc';sure exceeds 4,6 psig.

4 4

TABLE EP-AD-2.1 CHART D PRIMARY TO SECONDARY LEAK EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION Exceeding Primary to Secondary leak

~ Any reactor. shutdown requ' red by Tech Specs rate Technical Specification placing UNUSUAL 3.1.d.2.

the plant under a limiting condition EVENT for operation.

Rapid gross failure of one steam R-15 goes off scale high within JO minutes, con-generator tube.with loss of offsite ALERT firmed by R 19 increasing by a factor of :1000, 'or.

power.

verified by S/G chemistry gross beta /ganina sample analysis.

- pl us-

_ All three transformers: Main Aux., Reserve Aux.,

and Tertlary, are 'de-energized.

Rapid failure of multiple steam ALERT R-15 goes off scale high within 30 minutes, con-generator tubes.

firmed by R-19 increasing.by.a. factor of 1000,;or verified by $/G chemistry gros's beta /gama sample analysis.

- pl us-p Primary to Secondary leak rate greater!than 80,0 GPM

'g 4

_ as indicated by SI pump flow or RWST level change.

1 o

p 4,. 9 4

o e Rapid failaure' of steam generator -

SITE All 3' of the '.following indications are pr.esent:.

--g tubes witn loss of'offsite power.

EMERGENCY (1) Secondary side activity increase as indicated.

y o

g ec4:

e-x H

above.

.:(2) Primary to Secondary !floh) 300 GPM kG (3) All three tranformerg areJde-energized

_co.

t i

+ _

' $a

,a

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r

+

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),,

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='

~

TABLE EP-AD-2.1 CHART E LOSS OF POWER o

?.

Ef2RGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPPJINDICATION Loss of offsite power bMUSUAL ll All three transformers: ' Main Aux, Peserve )ux,

.c a

.'cnd Tert iary ara de-energized.

i

-or-EVENT s

Lus's of onsite AC power capability.

- o r;-

Both Emergency Diesel Generag s (J/h are inoperable x

Buses 1-1 through 1-6 are de-energized, includino Loss of offsite power ALERT the D/G supplies to buses'1-5 gid 1-6.

AC pov.er l

-and-(short term)

Loss of onsite AC power

'is restered to bus 1-3 cr 1-6.iithin 15 minutes.

Loss of offsite power SITE BuscG l-l through 1-6 are de-energized includind

-and--

(long term)

EMERCENCY the D/G supplies to buses 1-5 and 1-6 for longer Loss of onsite AC power than 15 Minutes.

3 Loss of all vital onsite DC power SITE Low voltage lockout or de-energized conoition on for more than 15 minutes EMERGENCY all four DC distribution cabinets:

BRA-ll3 BRB-ll3 BRA-ll4 BRB-ll4 Failure of offsite and onsite AC power Buses 1-1 through 1-6 are de-energized including

-and-the D/G supplies to buses 1-5 and 1-6.

Total loss of Auxiliary Feedwater GENERAL

-and-2 dj makeup capability for:

EMERGENCY loss of the turbine driven AFW pump.

'S Q Greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

~ w "i

~

Conditions exists for greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

~

(Loss of power plus loss of AFW P., g would lead to fuel clad failure o co

  • ~

and potential contain:aent failure)

A

f QL hy

  • i

}

,-r'

'n J, a q :

y 4

TABLE EP-AD-2.1 CilAkT F.

ENGINEERED SAFETY FEATURE ANOMALY 3

EfERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION j.

h. Emergency core cooling initiated UNUSUAL Safety Injection Sequence has been initiated, and

~

i and discharged to the reactor vessel.

EVENT either the SI pumps arrRilR pumps have caused an unplanned injection of core cooling water into reactor vessel. This.shobld te verified by system flows, comparison of ' discharge pressure versus RCS 2

pressure, and/or SA/RWST level changes.

'r

'h t

Loss of engineered safety feature

'NUSUAL Any shutdown requireu by Tech Specs Limiting -

i function requiring shutdown by EVENT Conditions for Operation, Section 3.3, Engineered.

Technical Specifications.

Safety Features and Auxiliary Systems.

__ g Complete loss of any function required Loss of operability of both trains _ of RHR for for cold shutdown.

ALERT core cooling if the steam generators are unable to be utilized.

Failure of the Reactor Protection Fatlure of the reactor protection system to System to initiate and complete a ALERT initiate and couplete a reactor trip when required.

reactor trip which brings the reactor (e.g. A turbine trip from full power without'

ubcritical.

reactor trip.. Indication would be increasing reactor coolant system pressure leading to lifting of pressurizer relief valves.)

Complete loss of any function needed SITE Total loss of all auxiliary and main feedwater i for plant hot shutdown.

EMERGENCY.-

ryste:ns (e.g. loss of both feedwater. pumps and all y ci.]

three auxiliary feedwater puaps) when the primary j g? -

j, system temperature is above 350 F.

uMu O

O

O TABLE EP-AD-2.1 CHART G FIRE AND FIRE PROTECTION

~

EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION Loss of Fire Protection System func-UNUSUAL Kewaunee has no Technical Specifications which tion requiring shutdown by Technical EVENT require shutdown with loss of a fire Protection Specifications.

System function.

A fire within the plant lasting more UNUSUAL A fire within the Administration Building, Turbine than 10 minutes.

EVENT Building, Warehouse, Auxiliary Building, or Containment Building lasting more than 10 minutes.

A fire potentially affecting safety ALERT A fire within the Auxiliary Bldg., Safeguards

systems, alley, D/G rocas or Screenhouse lasting more than 10 f..inutes that causec ESF equipment to be inoperable.

A fir'e comproaising the functions SITE A fire within the Auxiliary Bldg., Safeguards of safety systems.

EMERGENCY alley, D/G roons or Screennouse thct has rendered both trains of ESF equipnent that is needed to bring the plant to hot shutdown inoperable.

2 CDE

$bS

gZ C

gB

TABLE EP-AD-2.1 CHART H LOSS OF INDICATION EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDIC/> TION Indications or alarms on process or Refer to Technical Specification Sections 3.3, effluent parameters not functional UNUSUAL Engineered Safety Features and Auxiliary Systems, in Control Room to an extent requir-EVENT 3.5, Instrumentation Syste.n, and 3.10, Control Rod ing plant shutdown or other signi-and Power Distribution Limits, to detennine if plant ficant loss of assessment shutdown is required.

capability.

Most or all alarms (annunciators)

ALERT Total loss of Annunciator System Computer Alarms, lost.

and Sequence of Events Recorder.

Most or all alanas (annunciators)

SITE Total loss of Annunciator System, Computer Alarms, lost and a plant transient initiated EMERGENCY and Sequence of Eveats Recorder with an uncontrol-or in progress.

led plant transient in progress or initiated during the loss.

1 3 09 QE

s OW m se 4

TABLE EP-AD-2.1 CHART I SECURITY CONTINGENCY EERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION Security threat or attempted entry UNUSUAL Examples: - Bomb threat accompanied by interception or attempted sabotage.

EVENT of bomb materials.

- Adversary intercepted in the protected area.

- Undetonated bonb found on prenises.

Ongoing security compromise.

ALERT Examples: - Armed attack -on plant.

- Bomb detonated within-the. protected area.

Imminent loss of physical control SITE Example: -. Armed. intruders within protected area-of the plant.

EMERGENCY about to enter Control ' Room.

?OE

$ Os.

go e g -..

,J8 r

TABLE EP-AD-2.1 CHART J PRIMARY-SYSTEM ANOMALY l

EMERGENCY CLASSIFICATION CRI~5RIA CLASSIFICATION KNPP INDICATION Abncrmal coolant temperature and/or Technical Specification section T.S. 2.1 limits pressure UNUSUAL exceeded.

Indications:

~

- o r-EVENT

- RCS pressure vs Tave exceeds Figure T.S. 2.1-1 abnonnal fuel temperatures exceeding

- Subcooling meter indicates zero or negative.

l Technical Specification limits.

-Incore thennocouple readi,ngs exceed 1000*F

- o r-Fuel te:nperature limits are exceeded as i

determined by flux mapping and computer. code.

calcuiations.

Ccolant pu,np seizure leading to ALERT Primary flow transient and subsequent fuel failure fuel failure.

indicated by:

l

- Zero indication on one RCS loop flow l

- Overpressarization of RCS :ind relief valve lift-ing causing PRT temp and _ ;cessure alanas -

I

- R-9 indicates greater than 10 R/hr, verified by l

RCS sample analysis l

8cE i cN w.o 5M b Oma e

==*

f

o i

TABLE EP-AD-2.1 CHART K SECONDARY SIDE ANOMALY EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION Turbine rotating component failure UNUSUAL A failure. of the turbine resulting in an iranediate causing rapid plant shutdown.

EVENT shutdown and/or overspeed condition and for which turbine repair requires major disassembly.

~

Rapid Depressurization of the UNUSUAL The uncontrolled depressurization of the secondary i

secondary side.

EVENT system to the point where automatic safety l

injection is initiated (less than 500 psig steam generator pressure).

Steam line break with significant ALERT Main.steamline break that causes ECCS actuatica (greater than 10 GPM) primary to (less than S00 psig S/G pressure).

l secondary leakage.

-and-R-15. or R-19 reading a factor of 1000'above normal, j

verified by 5/G chemistry sample' analysis

- o r-l RCS to S/G leakage. verified by mass inventory l

>10 GPM.

l l

Steam line break Main steamline break.that'causes ECCS actuation with SITE-(less than 500 psig S/G pressure)

Primary to Secondary leak >50 GPM EMERGENCY

-and m com E C3

' * ((7y and R-15 or R-19 readings offscale, verified by S/G Indication of Fuel Damage chemistry sample analysis

,g

- o r-

~s, n

RCS to S/G. leakage verified by mass. inventory o _.

. > 50 GPM "c0

-an'd R-9 indication >10 R/hr and verified by~RCS chemistry sample analysis.

O TABLE EP-AD-2.1 CHART L MISCELLANE0US ABNORMAL PLANT CONDITIONS EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION Loss of containment integrity UNUSUAL Refer to T.S. Section 3.6 to determine if shutdown

~

requiring shutdown by Technical EVENT is required.

s Specifications.

Other plant conditions that warrant Conditions at the discretion of the Emergency increased awareness on the part of UNUSUAL Director or his designated alternate. Examples plant staff or state and/or local EVENT include cooldown rate exceeding T.S. limits or authorities, and requires plant pipe crack found during operation.

shutdown under Tech. Specifications.

Evacuation of Control Room antici-Evacuation of Control Roaa (E-0-06) with control pated or required with control of ALERT at shutdown panel.

shutdown syste:n established from local stations.

Evacuation of Control Room and control SITE Evacuation of Control Rooin.(E-0-06) and failure gn of shutdown systems not established EMERGENCY to estdolish control at shutdown panel within 3

'i

  • M ';

froin local stations.

15 minutes.

E EC 0 0~5 1

L 9

e

TABLE EP-AD-2.1 CHART L (cont'd)

MISCELLANE0US ABNORMAL PLANT CONDITIONS-EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION Other plant conditions that make a Two fission product barriers 'are lost 'with the.

release of large amnunts of radio-potential or probability of losing the third

~

activity in a short time period.

GENERAL barrier. (At least one verified indication in each possible, e.g. any core melt EMERGENCY category below.)

situation Indications:

Containment boundary potential failure Examples:

- pressure >46 psig

- Failure of Main FW and AFW systems

- loss of contain.nent cooling systems "or extended period without ECCS RCS_ boundary flow. Plus a containment failure

- no ECCS flow is inninent.

- failed open relief or -Safety valve with no

- Transient requiring the operation isolation capability.

of shutdown systems with a failure

- RCS break of these shutdown systems.

In Fuel Cladding addition failure of ECCS and-

- R-9 > 10 R/hr containment failure is imminent.

- RCS chemistry analysis E cQ 1Q 3xa l

VO ut w

e

i i

TABLE EP-AD-2.1 CHART M PERSONNEL INJURY EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION Transportation of contaminated and UNUSUAL' Sel f-expl en'atory seriously injured individual from EVENT site to an offsite hospital.

4 tos

--sa

$N b:

p.

YO w--

?

TABLE EP-AD-2.1 CJIART N EARTHQUArsE EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION Any earthquake felt in plant or UNUSUAL Activation of seis.aic recorder (Annunciator 1-45) detected on station seismic EVENT with EVENT light lit in relay room instru'aenta tio n.

-and-Verified by actual physical ground shaking or by contacting Dr. David Willis, U. of W. (Milwaukee) seismic center, at 1-414-963-4602.

An earthquake greater than ALERT Activation of seis.nic recorder (Ann.1-45) with Operational Basis Earthquake (0BE).

horizontal EVENT and L0 lights lit in relay room

-and-0.069 horizontal ground acceleration experienced at site.

Verified by contacting Dr. David Willis, at 1-414-963-4602.

An earthquake greater than Safe SITE Activation of seis.nic recorder (Ann.1-45) with Shutdown Earthquake (SSE).

EMERGENCY EVr.NT, LO and ill lights lit in relay room

-and-0.129 horizontal ground acceleration experienced a t s i t.e.

Verified by contacting Dr. David Willis at 1-414-963-4602.

E' C5

's Ss t 4, O &

e

t i

TABLE EP-AD-2.1 CilART 0 FLOOD, LOW WATER, OR SEICllE EMERGEf1CY CLASSIFICATION CRITERIA CLASSIFICATION ENPP INDICATION

50 year flood, low water or seiche UNUSUAL High' water level above 530 feet. Low forebay water EVENT level condition that cannot be cleared by stopping the circulating water systein. Wave greater than 18 feet..

.L..........~.

Flood, low water, or seiche near Design iligh' dater Level, =.582-' feet"

%.u design levels.

ALERT Design Low Water Level

= 575 feet.

l_

Design Deep Water WAVE = 22.5 feet i

I i'

i l

.:1 os Ho

'. U tc b M

'O b^

N S3 4

'. ~

TABLE EP-AD-2.1 CllART P-TORNADO OR HIGH WINDS EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION Any tornado on site UNUSUAL A tornado.within sight of the plant which has EVENT caused the loss of at-least one of the offsite transmission lines.

Any tornado striking facility ALERT A' tornado which strikes th'e faci ity and causes i

damage that -affects the continued -safe operation of the plant.

Sustained winds in excess of design SITE Winds in excess of 100 mph for greater than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

levels with plant not in cold EMERGENCY shutdown

~

t cy!.

uw l C H tob

o n-TABLE EP-AD-2.1 CHART-q.

EXTERNAL EVENTS EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION Aircraft crash onsite or unusual UNUSUAL An' aircraft crash within the site boundary aircraft activity over facility.

EVENT or notification fraa the security force or other source of higher than nonnal aircraft activity over-the site.

Aircraft crash on facility ALERT An aircraf t crash into plantLbuildings or switchyard which affects plant operation.

Missile impact fron whatever source ALERT A missile strikes the facility which affects on facility.

plant operation.-

Entry into facility environs of ALERT-Release of toxic-or flamaable gas fran a ruptured uncontrolled toxic or flammable gases.-

container such that.the gases enter the plant protected area or buildings.

Known explosion damage to facility ALERT Sel f-expl anato ry -

y n

affecting plant operation.

3 ca?-

a cn>

Hf

=

-=

y Ado N Aircraf t crash affecting vital SITE An aircraf t crash into plant buildings which causes or.

structures by innpact or fire.

EMERGENCY the loss of Engineered Safety Features reguirai to bring the pTant to hot shutdown conditions.

N.!.8 4

4 1

o.

TABLE EP-AD-2.1 CHART Q (cont'd)

EXTERNAL EVENTS EMERGENCY CLASSIFICATION CRITERIA CLASSIFICATION KNPP INDICATION L

Severe damage to safe. shutdown equip-SITE A missile strikes plant buildings or explosion ment from missiles or. explosion EMERGENCY occurs within a plant building which causes the loss of Engineered Safety Features required to bring the plant to hot. shutdown conditions.

Entry of uncontrolled fla..Taable Release of flannable or toxic gas.fron a. ruptured gases into vital area, or entry of SITE container which enters vital. areas as described uncontrolled toxic gases into vital EMERGENCY at left. Portable H2 monitor detects' explosive ;

areas where lack of access to the concentration of Ita in vital area.

area. constitutes a safety problem.

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