ML17347B111

Discusses 890418 Meeting in Atlanta,Ga Re Recent Proposed Rev to Emergency Action Levels & EPIP 20101 Which Contains Affected Emergency Classification Table.List of Attendees Encl

ML17347B111
Person / Time
Site:	Turkey Point
Issue date:	05/04/1989
From:	Ebneter S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Conway W FLORIDA POWER & LIGHT CO.
References
NUDOCS 8905180248
Download: ML17347B111 (62)

Text

0 W 04198g Florida Power and Light Company ATTN:

Nr.

W. 'F.

Conway Senior Vice President - Nuclear P. 0.

Box 14000 Juno

Beach, FL 33408-0420 Gentlemen:

SUBJECT:

MEETING

SUMMARY

- TURKEY POINT NUCLEAR PLANT, DOCKET NOS.

50-250 AND 50-251 This letter refers to the meeting conducted at your request in the Region II office on April 18, 1989.

The meeting was held for the purpose of presenting to the NRC your recent proposed revision to the Turkey Point Emergency Action Levels and, specifically, Emergency Plan Implementing Procedure 20101 which contains the affected Emergency Classification Table.

Your presentation included a

comparison of the current classification table and the proposed revised classification table with 'an explanation provided for each change.

Also provided was an explanation of how the changes meet the guidance of NUREG-0654.

It is our opinion that this meeting was beneficial and provided,a better understanding of the issues.

In accordance with Section 2.790 of the NRC's "Rules of Practice,"

Part 2, Title 10, Code of Federal Regulations, a copy of this letter and its enclosure will be placed in the NRC Public Document Room.

Should you have any questions concerning these matters, we will be pleased to discuss them.

Sincerely,

Enclosures:

1.

Current Emergency Classification Table 2.

Emergency Classification Table 3.

List of Attendees cc w/encls:

(See page 2)

Stewart D. Ebneter Regional Administrator 80~q~ 890504 ADOCK pg()pp~g()

PNU

Florida Power and Light Company cc w/encls:

J.

S.

Odom, Vice President Turkey Point Nuclear Plant J.

E. Cross, Plant Manager Turkey Point Nuclear Plant L.

W. Bladow, Plant gA Superintendent K.

W. Van Dyne, Regulatory and Compliance Supervisor State of Florida bcc w/encls:

G.

E. Edison, Project Manager, Project Directorate II-2, Division of Reactor

Projects, NRR NRC Resident Inspector Document Control Desk RII Cgg

~)

WRankf4/~/8'II RII lenjak JPStohr s

/89 4/ /89 F/7/89

ENCLOSURE 1

C < (PRE'v i

TABLE 1 EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 8 2/23/89

'I.

Primary Depressurization - ECCS Initiated Manually or Automatically UNUSUALEVENT

)

Flow to reactor core as in icated on Fl-'-943 (VP-B)

(Hi hheadSIS flow ALERT SITE AREA EMERGENCY GENERALEMERGENCY

?.

Primary Depressurization - Failure ofa Primary Safety or Relief Valve to Close UNUSUALEVENT

)

Sustained increased temperature on Tl-*-465,46Z, 469 or indication offlow through safeties on TEC flow indicators with pressure below normal s stem ressure.

ALERT SITE AREAEMERGENCY GENERAL EMERGENCY ACTION omp eteactions ist in tep

.4, a e30 mp eteactions ist in tep.,

a e42 omp eteactions ist in tep.,

a e54 ompeteactions ist in tep.,

a e61

TABLE 1 EMERGENCY CLASSIFICATIONTABLE EPIP 20101 2I25/89 3.

Primary Depressurization - Abnormal Primary Leak Rate UNUSUALEVENT RCS water inventory balance indicates leakage of > 1 GPM from an unidentified source and deemed unsafe after evaluation per Technical Specification 3.'I OR

) RCS water inventory balance incCicates leakage of > 10 GPM to a system not returnable to RCS r Technical Specification 3.1 OR RCS water inventory balance indicates leakage to a connecting closed system > 30 GPMbut < 50GPM per Technical Specification 3.1-(See Section 4) a)

b)

Increasing area radiation monitor or process monitor readings in affected areas, if applicable.

OR Increasing pressurizer relieftank level, pressure ortemperature OR Increasin sum levels ALERT 1)

LRCS water inventory balance i

icates leakage > 50 GPM but less than charging pump capacity (210 gpm) as indicated by mismatch of >50 GPM between charging and letdown (induding controlled leakage) and any ofthe ~foll owin t:

a) b)

c)

Pressurizer low pressure tripor RCS pressure decreasing uncontrollably AND High containment pressure (4 psig) or increasing containment sump level or increasing containment radiation level AND Pressurizer level decreasing rapidly SITE AREA EMERGENCY 1)

RCSwaterinventory balance indicates leakage greater than charginq pump capacity (210 gpm) as indicated by:

GENERAL EMERGENCY 1)

Containment pressure is >20 PSIG and a LOCAas defined in Site Area Emergency ofthis section has occurred or is in progress.

CAUTION: Consult Table 2, page 28.

ACTION omp etc actions iste inStep8.4, a e30 omp eteactions ist inStep8.5, e42 Comp ete actions ist in Step 8.6, a e54 Comp eteactions ist in Step 8.7, a e61

TABLE 1 EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 10 10/21/88 4.

Primary Oepressurization

- Abnormal Primary/Secondary Leak Rate UNUSUALEVENT 1) a)

PRMS R-15 alarming ANO b)

RCS water inventory balance indicates leakage

'1 GPM total through all SIGs not isolated from RCS per Technical Specification 3.1 (See Section 3)

ALERT 1)

A gross failure of orie steam generator tube (leak greater than 50 gpm but less than 210 gpm) has occurred with a loss of offsite power as indicated by loss of voltage to both Aand 8 4160V busses and one of the following:

a)

Valid alarm on PRMS R-15 or R-19.

OR b) Decreasing RCS pressure or pressurizer level OR c)

Increasing water level in affected steam generator.

(See Section 16) 2)

Arapid failure of steam enerator tubes has occurred leak of >500 GPM) as indicated by; a)

Valid alarm onPRMS R-15 or R-19 ANO

- b) no significant increase in containment sump level AND one of the following:

rapidly decreasing RCS pressure.

OR (2) reactor trip on low pressurizer pressure, OR (3) safeguards initiation on low pressurizer

pressure, OR (4) one steam generator level increasing rapidly (See Section 3) 2)

a) b)

no signi ficant increase in containment sump level or high range radiation; AND a valid alarm on PRMS R-15 or R-19 or one steam generator's level increasing (See Section 11)

SITE AREA EMERGENCY A rapid failure of steam generator tubes(leak of >500 pm) has occurred as indicated y one of the following:

a) reactor trip on low pressunzer pressure OR b)

RCS pressure decreasing uncontrollably OR c) -

Safeguards initiationon low pressurizer pressure AND A loss ot of fsite power has occurred which results in Loss ot voltage to both Aand 8 4160V buses withALLof the following:

GENERAL EMERGENCY Compleie ac iar i I()

A C'I'ed in Step 8 4, Complete actions listed in Step 8 5, a e42 lete actions listed in Step 8 6.

I oinplete actions lisie tep 8 7, sr

)4 p.iite 61

TABLE 1 m

EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 11 10/21/88 S.

Secondary Side Oepressurization

-Steam Line Break UNUSUALEVENT increasing containment pressure OR unusually loud noise outside containment associated with steam line break:

AND a)

Steam pressure is abnormally lower in one steam generator, OR b) high steam flowin coincidence with low Tavg

(<543'),

OR c) low steam generator pressure (<600 PSIG) in at least two of the three steam generators.

2) 3)

a)

High Containment Pressure OR b)

High Containment Radiation OR c)

Audible indication of steam break outside containment OR High steam flowwith low steam pressure or low Tavg AND RCS water inventory shows

) 10 gpm primary to secondary leak ALERT 1)

High steamline differential pressure safety injection with:

2) 3)

4)

SITE AREA EMERGENCY High steam line differential ressure safety injection and igh containment pressure (4 psiq) witheither high containment radiation or alarm on PRMS R-15 or R-19 or high SIG sample activity OR High steam flowand low steam pressure or lowTavg (See Section 11)

AND RCS water inventory indicates greater than 50 gpm primary to secondary leak AND RCS activity is greater than Technical Specification limitof 300 CII m I-131 DEQ GENERAL EMERGENCY 6.

Secondary Oepressurization

- Failure of Secondary Safety or Relief Valve to Close UNUSUALEVENT 1)

Uncontrolled loss of pressure from steam generator safety or steam dump as indicated by:

a)

Rapid and continuous decrease in steam generator pressure OR b)

Rapid RCS cooldown OR c)

Audible steam relief noise associated with failure of steam safety or steam dum 'valve to close.

ALERT SITE AREA EMERGENCY A C'I'I 0 N GENERAL EMERGENCY g

~

Complete actions listed in Step 8.4, a e30 Complete actions isted in Step 8.5, a e42 Comp ete actions isted in Step 8.6, 54 Complete actions listed i tep 8.7, a e61

TABLE 1 EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 12, 10/21/88 7.

Abnormal RCS Temperature and/or Pressure 4)

UNUSUALEVENT Core subcooling determined to be zero by one of the following three:

~ a) subcooled margin monitor, OR b) graph with RCS pressure and higliest loop temperature, OR c) pressurizer temperature, and highest RCS temperature OR l,i> 620"F OR RCS Pressure > 2535PSIG OR HCS Pressure ( 1770 PSIG with valid core exit thermocouple

) 620"F ALERT SITE AREA EMERGENCY A C'I' 0 N GENERAL EMERGENCY Complete actions iste in Step 8.4, a e30 Comp ete actions iste in Step 8.5, a e42 Comp ete actions isted in Step 8.6, a e54 Complete actions listed in Step 8 7, a e61

TABLE 1 EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 13 2I23/89 18.

Coolant Pump Seizure with Fuel Damage UNUSUALEVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 1)

. ReactortriporlowRCS flow and:

a)

High motor amps on affected RCP OR b)

RCP tripdue to actuation of RCP motor overcurrent relays AND'2)

RCS flowdecreasing rapidly on affected loop AND (3)

Increasing letdown line radiation levels as indicated by survey or PRMS R-20 alarming AND (4)

RCS I-131 activit ~300 Ci/ m

. ACTION ompeteactions iste in tep.,

a e30 omp eteactions ist in tep.,

a e42 omp eteactions ist in tep.,

a e54 omp eteactions ist in tep a e61

TABLE 1 EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 14 10/21/88 9.

Fuel Handling Accident UNUSUALEVENT ALERT 1)

Fuel damage has occurred or is imminent as indicated by:

Notification from the fuel handling crew that a spent fuel assembly has been dropped or damaged.

AND a)

Anyof the followingARMS channels alarming: R-2, 5, 7,8, 19,21,22, OR b)

PRMS R-12 or R-14 alarming.

OR c)

Radiological surveys indicate elevated radiation levels as a result of fuel damage.

(See Section 13)

CAUTION: ConsultTable2, page 28 SITE AREA EMERGENCY 1

Major damage has occurred to one or more spent fuel assemblies as indicated by:

Notification from fuel handling crew of major damage (e.g.,

large object damages fuel, water level below top of fuel)

AND a)

Anyof the followingARMS channels s~initicantt above the alarm point:

R-2,5,7,8, 19,21,22 OR b)

PRMS R-12 or R-14 significantly above the alarm point.

OR c)

Radiological surveys indicate significant increases in radiation levels as a result of fuel damage.

(See Section 13)

CAUTION: Consult Table2, a e28 GENERAL EMERGENCY Complete actions liste in Step 8.4, a e30 ACTION Comp eteactions ist inStep8.5, Comp eteactions iste inStep8.6,

.Comp eteactions iste inStep8.7, a e42 a e54 a e61

TABLE 1 EMERGENCY CLASSIFICATIONTABLE E PIP,20101 Page 15 10/21/88

10. Loss of Safe Shutdown Functions UNUSUALEVENT ALERT Failure of reactor rotection systerntoinitiatean comp ele a reactor tripwhich brings the

'eactor subcritical as indicated by reactor remaInInp critical after trip signal is initiated.

OR RHR system not operable or inabilityto sustain forced or natural circulation which results in increasing RCS temperature as seen on wide range loop temperature recorders or core exit thermocouples AND one of the following:

a)

RMR pumps not running OR b)

No flowindicated on Fl-"-

605 OR c)

No flowon loop flow indicators 2)

SITE AREA EMERGENCY a)

A transient has occurred requiring opei ~tion of shutdown systenis with failure to bring reactor subcritical with control rod(s)

AND b)

No core damage immediately evident (e g.

PRMS R.20 not alarming)

OR Loss ot function of one of the following four needed for hot shutdown:

a)

Scram system inoperable OR b)

Condenser dumps, atmospheric dumps, and steam generator safeties inoperable OR c)

No normal and auxiliary leedwater flow OR d) inabilityto makeup to the RCS (inadequate high ressiire in'ection flow)

GENERAL EMERGENCY Reactor remains critical after transient induced trip signal is lltltlatecl AND a)

RCS pressure ) safety valve settings OR b)

Containment pressure or teniper ature increasing rapidly Consult Table 2, Page 28 ACTION Complete actions listed in Step 8.4, a e30 Complete actions iste in Step 8 5.

a e42 Comp ete actions list in 5tep 8 6, a e54 Complete actions listed in Step 8 I, ar ebt

TABLE 1 EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 16 10I21/&&

2)

AND Conliinied RCS sample indicates ll>at coolant activity is greater tlian the Technical Specification limit for maximum reactor cooldnt activity

11. Fuel Element Failure UNUSUALEVENT I)

Increased letdown line radioactivity as indicated by

'urvey or valid alarm on PRMS R-20 2)

ALERT RCS sample shows I-131 DEQ Activity> 300 pCi/gm OR PRMS R-20 significantly above alarm point or survey indicates increased letdown line activity and laboratory analysis shows anincrease qreater than 1%

fuel failures in 30 minutes or a total fuel failure of 5%

2) a}

RCS I.131 DEQ activity >

300 pCi/gm AND b)

RCSTi>>, ) 620"F or core exit thermocouple > 700"F OR Containment high range radiationmonitor reading > I 3 f4 R/hr SITE AREA EMERGENCY 1)

. Core damage with inadequate core cooling determined by:

GENERAL EMERGENCY b)

Known LOCA as defined in Section 3 of Site Area Emergent with containment pressure approacl>>ng design limits or containnient cooling has beeii lost or coniainmeni failing to isolate which provides a flowp~tl> to the envlfonnlent OR Rapid gross failure of steam generator tube (leal greater than 50 gpm) with a radioactivity flowpath to the environment as indicated by:

( I)

Mismatch between charging flowand letdown flowor decreasing RCS pressure or pressurizer level AND 1)

Fuel clad failure as defined in Site Area Eniergency of tt>>s section witlione additional fission product barrier lost and poientidl lor loss of the third barrier as indicated by:

A C'l'l 0 N Complete actions listed in Step 8.4, a e30 Comp ete actions isted in Step 8.5, a e42 Complete actions listed in Step 8.6, a e54 Complete actionS lisled in Step 8 7,

,ii e61

TABLE 1 EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 17 10/21/88

11. Fuel Element Failure (continued)

UNUSUALEVENT ALERT SITE AREA EMERGENCQ GENERAL EMERGENCY (2)

Incieased second<<ry side radioactivity <<s indicated by vdlid alarms on PRMS R-15 or R. 19 or by an<<lysis of secondary saniples ANO (3)

Main steam line break between containment and IVISIVor niain steam line break downstream of MSIV with imminent or actual MS!V failure

12. Other Plant Conditions Requiring Increased Awareness (Emergency Coordinator's judgement)

NOTE:

Activation of the Emergency Response Facilities does not require declaration of an emergency or entry into a specific emergency classification UNUSUALEVENT 1)

Emergency Coordinator's judgement that other plant conditions exist which warrant incre<<sed awareness on the part ol the operating staff and/or local offsite authorities ALERT 1)

Emergency Coordinator's judgement that other'plant conditions exist which warrant the increased awareness and activation of emergency response personnel SITE AREA EMERGENCY 1)

Emergency Coordinator's ludgement that other plant conditions exist which warrant the precautionary notification to the public near the site and the activation of FPL and offsite agency emergency response personnel.

GENERAL EMERGENCY 1)

Emergency Coordinator's judgment that otlier plant conditions exist whichmake release of large amounts of radioactivity, in a short period of time, possible(e g., known loss ol two fission product barriers with potential for loss of tlie third).

A C 'I' 0 N Coniplete dc lions listed in Step 8 4, i<<r~10'omplete actions listed in Step 8 5, a e42 Complete actions listed in Step 8 6, a e54 Complete actions listed in Step 8 7,

'e61

TABLE 1 EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 18 10/21/88

13. Uncontrolled Effluent Release UNUSUALEVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY I)

A release has occurred or is in

'rogress which exceeds:

NOTE:

a)

Gaseous release Technical Specifications limitas shown by sample OR as indicated by the Plant Vent noble gas monitor reading (R-14, SPIN 64 AND 3/4-ONOP-067, Waste Disposal System-Accidental Release of Radioactive Gas).

OR Liquid release Technical Specifications limitas shown by sample analysis.

Direct Chemistry to perform offsite dose estimates per Emergency Procedure 20126, Off-Site Dose Calculations CAUTION: Consult Table 2, a e28 a) b)

NOTE:

Ten times the gaseous release Technical Specifications limitas shown by sample or as indicated by the high range Plant Vent SPlNG4 monitor reading and 3/4-ONOP-067, Waste Disposal System-Accidental Release of Radioactive Gas.

(R.14 willbe offscale high)

OR Ten times the liquid r~eease Tech Spec limitas shown by sample analysis Direct Chemistry to perform offsite dose estimates per Emergency Procedure 20126, Off-Site Dose Calculations.

CAUTION: Consult Table2, a e28 I)

Arelease that has occurred or is in progress which is greater than:

1)

Arelease has occurred or is in

'progress resulting in 50 mR/hr whole body or 250 mR/hr thyroid for 1/2 hour or 500 mR/hr whole body or 2500 mR/hr thyroid for 2 minutes at

- the site boundary(l mile) as determined by per forming Emergency Procedure 20126, Off-Site Dose Calculations or by performance of offsite surveys.

1)

A release has occurred or is in progress resulting in 1 R/hr whole body or an integrated dose or 5R/hr thyroid at site boundary (1 mile) as determined by performing Emergency Procedure 20126, Off-Site Dose Calculations or by per formance ofoffsite surveys.

CAUTION: Consult Table 2, page 28 CAUTION: Consult Table 2, page 28 Complete actions isted in Step 8.4, a e30 ACTION Comp eteactions iste inStep8.5, a e42 Comp eteactions iste inStep8.6, a e54 Complete actions liste inStep 8.7, a e61

TABLE 1 EMERGENCY CLASSIFICATIONTABLE E PIP 20'101 Page 19 10/21/88

14. High Radiation levels In Plant UNUSUALEVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 2) 3)

Any valid area monitor alarm from an undeterminable source with meter near or greater than fullscale deflection (10> mR/hr).

OR Unexpected plant iodine or particulate airborne concentration > 1000 MPC as per 10CFR20Appendix B, Table 1, as seen in routine surveying or sampling.

OR Unexpected direct radiation dose rate reading or unexpected airborne radioactivity concentration from an undeterminable source in excess of 1000 times normal levels.

1)

. Containment High Range Radiatioo Monitor reading.

) I 3E4 R/hr Direct Cheinistry to perform offsite dose estimates per Emergency Procedure 20126, Off-Site Dose Calculations, to determine magnitude of effluent release (See Section 13) 1)

Containmeni High Range Radiation Monitor reading

) 1.3 E5 R/hr.

Direct Cliemistry to perform offsite dose estimates per Emergency Procedure 20126.

Ofl Site Dose Calculations, to deterinine magnitude of effluent release'(See Section 13)

CAUTION: Consult Table2,page28 CAUTION: Consult Table2,page28

15. Other Plant Conditions That Could Lead To Substantial Core Oamage UNUSUALEVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 1)

Aknown LOCA as defined in Section 3 ot 5ite Area Emergency and failure of ECCS todeliver flowto tttecore has occurred resul ting in clad damage as indicated by containment area monitors PRMS R 1-3 or R 4-6 or Containment High Range Radiation Monitor alarming OR A C 'I' 0 N Coinplete actions listed in Step 8.4, iuL 10 Complete actions isted in Step 8.5, a e42 Complete actions iste in Step 8 6, ar e54 Complete ac,tions listed in Step 8 7.

ar e61 0

TABLE 1 EMERGENCY CLASSIFICATIONTAS LE E PIP 20101 Page 20 10/21/88

15. Other Plant Conditions That Could Lead To Substantial Core Damage (continued)

UNUSUALEVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 2)

Reactor trip on low steam generator levels with wide range levels appfoaclllng zero with loss of main condenser, loss of auxiliary feed flowand no.

higliliead Safety Inlection capability.ind 30 minutes lias elapsed witlino low head Safety Injection capability or auxiliary feed flow OR 3)

A known LOCA as defined in Section 3 of Site Area Emergency has occurred and one ol the lollowing:

a) b)

RHR flowindicator is Fl-'-

605 reads zero for l/2 hour after recirculation phase is attempted and RCS temperature is rising OR Failure of containment spray and emergency coolers to prevent containment temperature from rising excessively.

A C'l'I 0 N CAUTION: Consult Table 2.

a e28 Complete actions listed in Step 8.4, a e30 Comp ete actions isted in Step 8.5, a e42 Complete actions listed in Step 8.6, a e54 Complete actioiis listed in Step 8 1, a ebl

TABLE 1 EMERGENCY CLASSIFICATIONTABLE E PIP 20101 Page 21 10/21/88 16.

LOSS OF POWER CONDITIONS UNUSUALEVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 1)

Sustained loss of offsite AC power capability as indicated by:

a)

Start-up transformer voltage and amp meters indicating zero AND h)

~ Swiichyard voltage recorder andmeter indicating zero OR Sustained loss of onsite AC power capability as indicated by:

Generator potential light extinguished or turbine generator otherwise unable to supply power to the auxiliary transformer AND Both diesel generators unable supply power to the busses on the affected unit.

CAUTION:

Some loss of power conditions may result in loss of primary emergency notification systems.

Use backup communications and restore power to the notification systems by starting tliiits 1 aiid 2 diesel eneralors.

2) a)

4KV bus "A"and "8" low voltage alarms with voltage and amp meters reading zero AND b) all supply breakers open with failure of emergency diesel generators to power their respective 4KV bus either automatically or by manual action from the Control Room.

See NOTE l.

OR Loss of all vital on-site 0 C.

power as indicated by D.C. load trouble alarms on all D.C buses or decreasing voltage on all D.C.

buses below alarm point.

See NOTE 1.

NOTE1:-

An Alertshould be declared as soon as a loss of power is experienced. ASite Area Emergency should be declared if the power loss lasts for > 15 min., or ifthe Emergency Coordinator leaves the Control Room during the fiist 15 minutes.

1)

Loss of offsite ANDonsite A C.

g ower capability as indicated y-b) 4KV bus "A"and "8" low voltage alarms for > 15 minutes with voltage and amp meters reading zero tor 15 minutes OR Allsupply breakers open and both emergency diesel generators lail to power their respective 4 KVbus either automatically or by manual action from the Control room or Local control board See NOTE 1.

OR 2)

Loss of all vital onsite D C.

power for >15 minutes as indicated by D C. load center trouble alarms or voltage decreasing below the alarm point on all 0 C buses.

See NOTE 1 1)

Extended loss of offsite power ANDloss of onsite A.C power capability for >15 minutes as indicated by:

1)

Extended loss of offsite power AND loss ol onsite A C. power capaLiility as defined in Site Area Emergency of tl>>s section.

.with loss of all feedwater capabilities7or > 1hour CAUTION Consul t Table 2,'Page 28 A O'I'I 0 N Coiiiplele acliorls listed in Step 8 4, 4ll 6 30 Complete actions listed in Step 8 5, a e42 Complete actions listed in Step 8 6, ia e54 Coi>>piete actioris listed in Step 8 7, ai e61

TABLE 1 EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 22 10/21/88 17.

LOSS OF CONTAINMENTINTEGRITY UNUSUALEVENT t)

Violation of containment integrity as defined in Technical Specification 3,3 resulting in initiation of shutdown of the

. reactor.

NOTE:

An Unusual Event shall be declared when actual load reduction be ins.

ALERT SITE AREA EMERGENCY, GENERAL EMERGENCY

18. CONTAMINATEDPERSONNEL UNUSUALEVENT t)

Ti~nspor tation of confirmed ex ter nally contaminated injured offliteniedicul facilii ALERT SITE AREA EMERGENCY ACTION GENERAL EMERGENCY Complete actions listed in Step 8,4, a e30 Completeactions iste inStep8.5, a e42 Complete actions listed in Step 8.6, a e54 Complete actions listed in Step 8 7.

a e61

TABLE 1 EMERGENCY CLASSIFICATlONTABLE E PIP 20101 Page 23 10I21I&&

19.

LOSS OF ASSESSMENT FUNCTIONS UNUSUALEVENT ALERT SlTE AREA EMERGENCY GENERAL EMERGENCY 1)

Significant loss of effluent monitoring capability, meteorological instruments, cominunications, etc, which impairs abihty to per lorm emergency assessment as indicatedby the following:

1)

Most or all Control Room annunciator alarms lost with plant not at cold shutdown AND inabilityto restore power to annunoators withinfive minutes.

1)

AllControl Room annunciator alarmslost for) 15m~nutes with a plant transient iii progress.

a) b)

c)

Loss of effluent or radiological monitoring capability requiring plant shutdown OR tossof all primaryand back-up communications capabdity withoffsite locations.

OR t.oss of pnmary and back-up on site meteorological instrumentation withloss of all communication ca abilit to HAFB.

AC'I't0 N Complete actions iste in Step 8.4, a e30 Comp ete actions iste in Step 8.5, a e42 Comp ete actions listed in Step 8.6, a e54 Complete actions listed in Step 8 7, a e61

0

TABLE 1 EMERGENCY CLASSIFICATIONTABLE E PIP 20101 Page 24 10/21/88 c)

Noiifi cat i on by the weather bureau of a hurricane warning OR Confirmed sighting of a tornado in the Owner Controlled Area OR Any earthquake felt or detected on installed seismic instrumentation.

OR 1 lurricane surges or floods that limitaccess to the site.

20. NATURAI PHENOhllENA UNUSUALEVENT 1)

Plant not at cold shutdown and one ol tlie following:

a) b)

c) d)

Notification by the weather bureau of the approach of a hurricane with winds at or near design basis (225 MPH) levels OR Any earthquake that could cause, or already caused shutdown of turbine generator and/or reactor.

OR Any flood or hurricane surge that raises the water level to at or near the design level of 18 feet above M.L.W.

OR Tornado striking any ower block structure ALERT.

1)

Plant at any mode of operation and one of the following:

a) c)

Notification by the weather bureau of the approaclt of a hurricane withwinds > 225mph.

OR Any earthquake that causes shutdown of turbine generator and/or reactor coupled with degradation of safety systems OR Flood or hurricane surge, that is > design level of 18 feet and causes shutdown of turbine generator and/or reactor with degradation of safety s stems.

SITE'AREA EMERGENCY 1)

.Planl not in a cold shutdown condition and any one o t e following:

GENERAL EMERGENCY 1)

A n>ajor internal or external event (e g, liies, earthquakes, plane crashes) has occurred, which could cause massive common damage to plant systems iesulting in any of the ot lier General Emergency initiatinrjconditions.

CAUTtbN Consult Table 2, Page 28 A C'I'I 0 N Complete actions listed in Step 8.4, a e30 Complete actions iste in Step 8.5, a e42 Complete actions listed in Step 8.6, Complete actions listed in Step 8.7, a eS4 a e61

TABLE 1 fMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 25 10/21/88

21. HAZARDSTO STATION OPERATION UNUSUALEVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY a)

Any aircraft crash onsite or unusual aircraft activity over facility OR Onsi te explosion NOTE:

Aiiexplosion resul ts from a rapid cliemical reaction result<<ig in the release of noise d<<d he J I dnd tlie rapid expansion of gases.

OR c)

Toxic or flammable gas release near or onsite could threaten personnel OR d)

Rapid turbine shutdown due to turbine generator rotating component failure l)

Occurrence of events that could threaten the safety of the nuclear plant or personnel as indicated by the following:

4) 5)

OR Detection by portable instrumentation, or notification from offsite sources that gases reater than their toxic or lammable limits have entered the facilityposing a threat to plant operation.

OR Turbine shutdown with observation of casing enetration 1)

Aircraftcrash onsite involving plant structure OR 2)

Missile impacts from any source damaging plant structures or components affecting plant safety OR 3)

Damage to plant structures or components from an explosion affecting plant operation NOTE:

An explosion results from a rapid chemical reaction resulting in the release of noise and heat and the rapid expansion of gases.

1)

Plant not at cold shutdown AND a)

Aircraftcrash resulting in damage to vital structures or components by impact or fire, OR b)

Missile impact or explosion resulting in severe damage to safety systems NOTE:

An explosion results from a rapid chemical reaction resulting in the release of noise and lteat and the rapid expansion of gases.

OR c)

Entry of gases greater than their toxic or flammable limits into control or vital areas and which renders one train of a safety related system inoperable.

A C'I' 0 N Complete actions listed in Step 8.4, a e30 Complete actions isted in Step 8.5, a e42 Complete actions listed in Step 8.6, a e54 Complete actions listed in Step 8 7, a e61

TAILE 1 EMERGENCY CLASSIFICATIONTABLE EPIP 20101 page 26 2/23/89

22. SECURITYTHREAT UNUSUALEVENT ALERT SITE AREAEMERGENCY, GENERAL EMERGKNCY l)

. Security contingency resulting in initiation of PTP Safeguards Contingency Plan bg declaration ofa "SecurityAlert tooneor more of the items listed below.

a)

Bomb threat b)

Attack threat

')

Civildisturbance d)

Protected area intrusion e)

Sabotage attempt f)

Internal disturbance

)

Vitalarea intrusion

)

Securit Force strike.

I)

A"Security Emergency dedared as defined in the Safeguards Contingency Plan.

l)

A Security Emergency involvingimminent occupancy ofthe control room or other vital areas to the reactor system as defined in the Safeguards Contingency Plan.

1)

Physical attack on the plant resulting in occupation of control room or other vital areas.

~unos Consult Table 2 Page 28.

23. CONTROL ROONl EVACUATION UNUSUALEVENT ALERT SITE AREAEMERGENCY GENERALEMERGENCY I)

Evacuation ofcontrol room 3) anticipated or required with control ofshutdown systems established from local stations.

Evacuation ofcontrol room and control ofshutdown systenis not established from local stations within l5 minutes.

24.

FIRE UNUSUALEVENT 1)

Uncontrolled firewithinthe power block lasting longer than l0 minutes ALERT a)

Uncontrolled fire.

'I) potentially affecting safety systems AND b) requiring offsite support.

3)

MaIorinternal or external fire which could cause massive common damage to plant systems resulting in any,ofthe other General Emergency initiatingconditions.

Fire compromising the function ofsafety systems.

Consult Table 2 P e 28.

SITE AREAEMERGENCY

= GENERALEMERGENCY ACTION Comp eieactions ist in tep.,

a e30 om eteactions ist in tep..

a e42 actionS ISt in teP..

54 ete actions is e6l

TABLE 1 EMERGENCY CLASSIFICATIONTABLE EPIP 20101 Page 27 10/21/88 25.

LOSS OF ENGINEERED SAFETY FEATURES/FIRE PROTECTION SYSTEMS UNUSUALEVENT 1

a)

Loss of engineered safety feature system functional capability as required by 1 echnical Specification 3.4 OR b)

Loss of instrumentation system functional capability as required by Technical Specification 3.5, Tables 3.5.1-3.5-3 AND c)

Failure to restore system functional capability or coiiduct a plant shutdown within the action times listed in the applicable Tecluiical Specification sucli that plant shutdown is required in accordance with Technical Specification 3.0.1.

NOTE Tlie enier gency condition shall be declared when load reduc tion commences in accordance with Technical Specification 3.0.1.

OR 2)

Loss of tire protection system functional capability in excess of the conditions and action times specified in Technical Specification 3 14 and failure to implement compensatory nieasures within the specified time limits NOTE:

Consult TSAR Section 9 6, for lurtlier guidance on fire rnieriions stem re uirements ALERT SITE AREA EMERGENCY GENERAL EMERGENCY A O'I' 0 N Complete actions listed in Step 8.4, Complete actions listed in Step 8 5, lete actions listed in Step 8 6, 1al e 30 a e42

~

4 Complete actions lisied

'i e61 8 7.

0 0

~ ~yU lENII ENCLOSURE 2

TABLE 1 EMERGENCY CLASSIFICATIONTABLE

t. Primary Deprossurization-ECCS Initiatert Manually or Automatically EPIP 20'ag XXIXX GENERALEMERGENCY SITE AREA EMERGENCY ALERT UNUSUALEVENT Sefetr Ihlectlohlhltleted Auo High head Sl pump liowto the core

< law SICuiS,OW primary Doproceuri cation - ECCS Initiated Manually or Automatically UNUSUALEVENT I)

Slow EoroorEof Coro ~ s ued oh II~'943 tur SI ra hood Sts liow ALERT SITE AREA EMERGENCY GENERAL EMERGENCY CH~G E i)

CIrkcr ok c Ioqs,4 co 4

h ol'4 4 Wu I o~ ( Gd 5n A

~owe )

4 o<+l o~

~o

>~ <++

~ I <~+< Mar ~ ~I.

L ~ ~

v>tJ knws gJ' I 4i ooO wygkoP.

TABLE 1 EMERGENCY CLASSIFICATIONTABLE EPIP 2010 Q2. Primary LeakageILOCA GENERALEMERGENCY Erthw I or 1:

I)

RCS Itakagt QNstw than avarlabie charging pump capKII'y ANO Containment pressure > 10 pug SITE AREA EMERGENCY RCS ltsksgt greater than av>>labl ~

eh>>ging pump capscIty AND No indication of increased steam generator 'lutwItaka9t.

ALERT RCS leakage ) 50 gpm ANO RCS leakage witrvnsvailsb: ~ charging pump capacrty ANO Noindicationolihtrtaff

', Iteafh gtnerator lube leakage NUSUALEVENT U

TIther I, 1. 3 Or S I)

UfvdtntifitdhCSleskage

> I gpm ANII It($leakage evaluated as unss Ptf TKhnyral Specihcation 3.1 Reactor Coolant System 1)

RCS ltaks9t 9ftatef than

~vailabte char gyng pump toss ol conmnmtnt integrity which provides a l towpath to the envIIOnment.

CAUTION: Consult Table 1, page 1$

lor required protectiye KtionIKommtndauons.

1)

Idtntihed RCS leaksgt tv 10 9pm I0 a system Aot returnable to the hCS.

3)

Identified hCS leakage

)30 gpm to a connecting dos systtrh.

4) failure 0 I a pfimwysafety of Ittielvalve to clew resulung r uncontrolled RCS dtprtsuJ fr sation.

Z/sq P.eurus Ofu

~

2.

Primary Dopfossurizadon - Failure of a Primary Safety or Relief Valve to Close UNUSUALEVENT I)

Sustained IACN>>td tempersrwe on Th'sSS, SST, SSS of uldlraUOAOl flow uvough saftuts on TSC Row uuucatofs wrth pfesswe below normal I tm tsluft 3.

Psirsafy Doprossuftaatlon - Abnormal Primary Leak Rata 3)

UNUSUALEVENT RCS water inwntofybsknce indrcases kakage of > 1 GPM from an urwtenuliod source and deemed unsafe aber evsluauon per Tecivucal Specilicauon 3.1 OR R

watw inventory balance Itslosksgeof a IOGPM to a system AotIttWnabk to Techfucal Spoofrcauon I

OR RCS watw ivontofrybaknco Idicales kakaQe los connecdng dosed system X 30 GPM but c SO GPMpw Techncal Spocilicau'on3.1 ISee Socuon 4)

ALERT I)

~RC w>>er inventory balance Ifii&caksleakage > SO GPM but kss than char IPIyg PwrlP capacity il10 gpm) as indicated bymismatchof >SOGPM be Iwtth Ihsfgyno shd l et dowfl frhclwllAQcontrolled leaksQe)

~yy y yy

~ldl a)

IAcrtsuA9area fsdiauon mofliter of process moNlofItackhgs Ih a IIKled aNasy II applicable.

OR b)

IhcfesuAQpfesswltw Nbef taAL level. pfesswt or ttlhperstwe OR c

incftsu w

levels SITE AREA EMERGENCY I)

RCS water inventory balance lhdrcates leakage QNatw than cherty Ag pump capacity f310 Qpnt) asrhdicattdbyl a)

PI>>surirw lowprtuure uIp or RCS pceuwe decreasing uncontrollably ANO b)

Itygh containmtnt presswe (4 pug) or Increaung contauvtleht sump kvel of inert>>ino containment radiodonltvel ANO c)

PItsswitw level dKfstung rapidly GENERAL EMERGENC')

Containment pressuN is s PSIGI and a LOCAos dehnr Site Area Emwgency ofth SKuon hat OCCWIWIOr IS r Progress CAUTION: Consult Table 1, pegy

+oy u~+ 0 Ho\\It

~washy vk Iu

~~v~tyt Q

s frog Q

u. I)

Ifv yv S srwy. ~fit y

S ~ y

~ L ~

~

y 4(cn3 g $ 4E Ig JI gJ fc I

v 0

y t h

I err' C~ I toss l Cbfrfi& c(syf ~lsr'c sec

~ sv~.

Iy~ Ly~ eye sutrydIHQSS Iyr << II Cle St<<g.

0 )

ytyyfof5 Etc g Ray gfyufrdl PAgs Isl ly~> (4hl utr+pc I-)

TABLE 1 EMERGENCY CLASSIFICATIONTABLE EPIP 2010 1 XXFW89 Steam Generator Tube Lea'rupture GENERALEMERGENCY SITE AREAEMERGENCY SltHll9tnerr<<or tubt Ita'ka9t gfta'Itf than availabl ~ the<ging pump capacity ANO loss o I o I(site power CAUhON: Consult Tablt 2, page 20 for possible protecvvt actionrecornmtndations Eilhet I or 2 ALERT 2)

Sttam generator tube ltakagt greater than avtulable charging pvrnp capacity.

1)

Confirmed hearn generator tubt Itaka9t > 50 9pits AND Steam generator Iubt leakage withinavailahl ~ chaiging pump capacity AND loss o(of(s<<e powtr UNUSUALEVENT cirtaltrthais s009pd steam 9tfitfatof tubt Itaka9t SLR Grtattf than I gprii Steam genefalor tubt Itakagt NOTE: Ae(er to TKhnicat SpK)firat<on 3.1 ~ RtKSOr Coolant System

>Jrtfq IE(Evla<DPD

?esto I

i.

primary otpressur(tat(on

~ Abnornsal prlmaryrsecondary Leak Rate UNUSUALEVENT I) 4)

PRMS A I S atJimin9 AND bl RCSwuter inventoty ball<<<t ifldicarts IeJk agt b I GPM IOiJl IhiOugh 4tl S<GS not nol ~ted (iom RES per fech<N< Ji Spec<I<ca<ton 3 I (Set sec non ))

ALERT I)

Ag<OnluituieOIOnes<eum gene< ~iui I<<lie (Icut <J<tJ<er tlsun 50 gpni l<<il<en<I<un 210 0 p<h) I 1J1 <N < i<i< td wiIh 4 1011 0 I olh<<e pnwv< 41<<NI<<JIedby lon ol volIuJc Io liothA Jnd 8 4 160v bunvsu<KI oht of the following; 4)

Vuhd 414<m O<t PRMS R 15 ot A I'J OR b)

De<raising HC5pressuit or p<essunre<

reve<

Olt In<<e Jsuig wu<c< Itvel in Jlrectcsl ne Jm gene<<<<or 15ee 5ec<ion Ikl 2)

Afap<d Iuiluicolsteam cue< J<o<<ubes I<as occurred ItJk ol ) 500 GPM) Js indicated by,')

Vuhd glum on PRMS R 15 o< R 19 AND b) no s<gn<hcunl increase in co<<< 4<<w wn< sump level AND 5 uf <lie lullow<<19 lf

<4<<idly dK<tasih9 RCS pic<su< ~

OR (2) ie u<w <tip wiluw, Ii<1'1luli<ei Plessult, lie

())

'14<e<JuJ<ils llllt<JI<o<1 wihiw prew<i<<tet INf 1'i i<i1',

OR (c) niie 1<euih geiie< 4l o<

lvvi'Ialuleuu<lg

<,ilw<ly (5ee Set<ion ll 2) 4)

<cJ<fni flipoh low pits'Nit<If<pltssui ~

OR b)

HC.S p< enure dti<eJung un< un <<ol IJbl y OA Sulegu Jids i<unJtiwson Iuw p<snsunlcl pltnU<t AND A loss ul u<hi<t powe< 1<41 occurred wt<<<h <tsuhs i<< loss ul vorlage <ulio<hAJhv v ~ 160v bu'<VS W<<h AllOl <IitIOIIOWlhg c) iiu 'il<J< II(<curl< 1<K<cuit i<1

<ontahuhen< suinp ltvel w INVII~4futt fJiliuliuii AND 4 vuh<<ul Jtm wSPRM5 It 15 u< A lgui ones<tarn gvnii4<w'1 level i<K<cuu<NJ fSet Set<to<< 11)

SITE AREA EMERGENCY I)

A <Jlvd Ivu<uie os sfeuhi gen<<<niui Suites(leuk ul ) $00 phi)li.ni<<uiirvdJsinilituttd iy ohe ul Itic In<lawn<0, GENERAL EMERGENCY

("HANGE'-.

a(sf < ~ I i c ~ > ~ \\ssefhlivg w< 8(3(J+

g cthe,uvula cfi~trio

~ weoeyaA 4)

(toss ('<<- EAt2

@I<kg <<4 $ <c) (- +crL dr) w'

'+pcc hs (sun< Ntu.,

TABLE t EMERGENCY CLASSIFICATIONTABLE EPIP 20)(

~4. Loss of Secondary Coolant GENERALEMERGENCY SITE AREA EMERGENCY Sttsmlint or feedline b eak which results in Saftty lzKtionsnustion ANO Connrmtd RCS OEQl 131 activity R 300 pci/gm ANO Confirmed litem generator tube leakage > SO gpm CAUTION: Consult fable 7. pop>> 20 for powible prolec>>ve actionrecommendations ALERT Sttamlint or feedhnt brtsli w4ch rscull t in Salt ty InieCtiOn SCtuatiOn AND evidence of significant)>10 gpm) steam generator tube leakage UNUSUALEVENT Sithtr I Of in I)

St tamline or feedline beast Vim'Ch resuns in Safety I"Sectio act ustIori.

7) faiturtof s sttam yewrator salt ty or steam dump to atmosphtrt vslw lo close resulting in uncontroued stcond tktion.

g/gll Fcui 4 ~ otu Role \\

S.

Secondary Side Oepressur)sation

- Stcam Line Break UNUSUALEVENT I)

IOCIJWflgCohluNlltnt pressure OR unusually loud noise out>>de containment associated wilhWeun lint break:

ANO

~)

Sltsin pftssuftis abnormally lower in ont sltam ljHwfalor, OR b)

Bgh Wesm flowin C&hCidtfICtWilhlowfavg Icsa) ) ~

OR c) lowuesmgentralor prtssweIC600PSIG) in at Itasl twooftht lluM sltshl QNWJIN1.

7) 3)

J)

HigliCoiilJihillthl Piewuit OR b)

High Conlunment llJdistion OR c)

Audibltindication of sitJhi hitJk out>>de conlunmenl OR High wesm llowwithlowsteam pieisuit w low fJf9 ANO RCS water inventory shows o 10 gpm pnmuy so SKonduy leak ALERT I)

High ste Jmhne diner enlist prewwe salttyi IKtionwilh:

7) 3)

SITE AREA EMERGENCY High wean line dillerenlist t"t'lsuit sJltly iillKIlohahd IighcolltuIWloAIpres>>iie (J pug) wilhuther Bgh conlainmenl iuhalion of slum onPIIMSR ISor R Igofhigh 5 0 sample JC>>vily OR High sitJin flowahd low st tain pressure or low fsvg ISet Sec>>on 11)

ANO RCS wJI er inventwymdica Its greater Shan Sogpm primuy IO second,uy le Jk ANO RCS Jc twilyis giesltr ttun fee~CA Sptohcuiohhmit of 300 scv mr 13101 GENE)tALEMERGENCY E.

Secondary Depressurization - Failure 01 Secondary Satety or Re)let Valve to Close UNUSUALEVENT I

I)

Uncontrolled loss ofpesswt front sitJib gener KorSJNIy or stean dump as Indicued by:

a)

Rapid and con>>nuous dKrtast Ihsltun gehtfalu pftssw t OR b)

Rapid RCS cooldowh OR c)

Audible slesmretiefnoise associated withfulwe of sltun saf ~lyor sltun dum vow tdchsse.

QH Asst Ct

~ (r Cs

~ f Lkft o. >

c ksf OLOSS ( R/4 iorr

'c Ak art + ROS

'P 30p visa/It~)

r )

O, e QPJr ruovC i 4aur s/cv laeakr ~ A r fag ty Cf

+It/Pelage,F Sfh'fve NO~

v sea Los" OF 5ocofjfticy Ctslhw+ SCJ4vv'

..)*

S.

Abnormal RCS Temperature andior Prcssure GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUALEVENT KitlwrI, l, 3 or a:

I) ltCS saturated or superlwated l)

Tat0 >63IPF 3) hCS preuure >l53$ prie a) hCS preswre << I770psig AN/

Core crittiwrmocoupies

>630'F 2

I I

1.

Abnormal RCS Temperature and/or Prcssure UNUSUALEVENT I)

Colt wbsoolusc determined Io br rrrobr ~col rht follow>>u3 l~lu ALERT SITE AREA EMERGENCY GENERAL EMERGENCY el ei wbsoulrdnlw~nmululur.

Oh bl gluPIlw>>h NCS PltlSWt else Iullhesl loop Irmprlrlwe.

oa prrswllrrr I~lnptlalult,

~lullughtu RCS Ienlpelrlwt oa I,.e i aru I ON KCSPrtswse ) 353SPSIG oa NCSPleSSWt << t))OPSIGunlh rend IOre el>> ther mOI duple

)6)u'I QIIAsao u.

lg g C

y,4a) uft flag gvLceolllvq W Dcgount wl srfe5a elate/

crl'olr rL4 dc 6~ o$ Q bcIP,

~ 4 g r Isr ~ ~

( wlILuvq4. *++airsplia4 u Ace ot 4 ates s

TABLE 1 EMERGENCY CLASSIFICATIONTABLE EPIP 201 XXIPXf

6. Reactor Coolant Pump Seizure With fuel Damage GENERAL EMERGENCY SITE AREA EMERGENCY ALERT Reactor tnp doe to lowloop liow ANO Conlirmed ACS DEIST 13 I activity a 300 PCdpm UNUSUALEVENT r+r.l,

'Xolot L

Coolant Pump Seiaure with Fuel Damage UNUSUALEVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY I)

" Aeaclor tnpor low ACS liow and.'

I Hrotrmolor empt on

~Iletled IICP OR b)

ACP trip doe loectrreuon ol ACP motor Overrwrenl relays

• NO I))

ACS liowdeer eetrrre rapidly on allecled loop ANO l3)

Increeting letdown line radiauonleveit ~trltdrcatedby Urrvey or PRMS R 30 alarmrrvp AND lal ACSI I3laCUvil a300 Cir m Oaenwo 4

Sl

\\

C <<L c t<<lh

'Ivr <<at<<b,:

e-<

ef}o3e-c>>S tve e

vP ceerecv nr 4r R C p ~ v<<r>>. ( Rc p rv

~<<I ~

4 e~

~

$)<<vf4 Ic

<<r c vtryveeg )

TABLE 1 EMERGENCY ClASSIFICATIONTABLE EPIP 10',

7 Fcsef Handling Accident GENERAL EMERGENCY SITE AREA EME)lGENCY 4ither I ~ 1 or 3:

I)

Major damape to one or more spent Iuel elements has occurred ANO ffflucntreieaseisinevcessof Secuon 11, Uncontrolled tlllutntRtltast, Site Area 4mar panty valuts.

ALERT Aspent futlelement has been dropped or damaoed ANO Release of radioacuwty Nom tht damaped sptnt luel element hat betn detected.

UNUSUALEVENT 1)

Major damape lo one or more

~ptnt tuel ~ltrntnuhas occurred AND Containmern radiation levtls

)1,3 El Rem/hr 3)

Major damape to one or more sptnt fuel tltmtnt1 due to water ltvtlbcrnp below top of nt tuel.

g gsa,eW Rcslo I Fuo) Handling Acddent UNUSUALEVENT ALERT fuel damapt has occurred or st rmmrntnt as sndrcat ed by:

Notlllcatlon Irons tile Iutl handlrnp crew that a spent lutt

~sstmury has bttn dropped or dani aped ANO a)

Any Ol She IONOWrnp ARMS channels alarnunp:

N 1, S, 2,4. Ip.ll,l2, OR b)

I'IIMSN lier 4 ll alur rhlnp OR cf Lrdroloprcal surveys rndhtatt tltvattdradratlon level t ut ~ result nl lull darnape.

IScc 5cctlon I))

CAUfION: Consult fable 1;pape 14 SITE AREA F MERGENCY Mater dama9t hal occurred to one or more spent IOH asstrnolrcs as rlsdrcattd by:

Not I I I tv I run IIorll Iu et Ilandlrnp crew elrnmur damapt (~ Q ~

tarot uulvC I siumtpcs Iutl, water level below top ol lutl)

AICD a)

Any ul lhe IOIIOWrnOARM5 ctranntls Rpn~lr ~f above the alarm per nt:

R l. 5, f. 4. 19, 21, 21 ON b) yrtMS k llor N I ~

Sr pre flear ltlyabove II'it uiarlllpcvrll Il OR C)

Nudrulotsr Cul SurveyS rndrsate uprufrcant User casts sn radiauon levtls as ~ resuh ol Iutldamape.

ISee Sec uon 13)

CAU11ON.'onsult fabi~ 1, 24 GENERAL EMERGENCY E NIHJO b

~

E,~LC f~g 4I~I 4vr w CL W. ~ rahrpachVd frsstvuHW M.cds vrr4 Juferrvcfvo>Aw CI tpd 4

SAI te ctguog ~~~

dg gl

+I'<< ~ vS 4d vrS I:Sc.

TABLE 3 EMERGENCY CLAS IFI ATI N TABLE EPIP 20

~PR c

Loaa ot Sate Shucdown functions GENERALEMERGENCY 5)TE AREA EMERGENCY ALERT UNUSUALEVENT.

tither I or 2:

I)

Inabilityto briiigthe reactor subcr i<ical A<r'1 RCS pressure ~ 24RS pug.

1)

Inabilityto bring the<sac<or Subcnticsl ANO Containment pressure 0 4 ps<Q CAIITION: Consul< Tab< ~ 2, Page 2b Ior re<<uired pro<K<ive JOloh recommendatiohu bther I ~ 2, 3or 4:

I)

Inabilityto bring the reactor Subcnlicsi withcontrol rods a) b)

c)

Condensei s<e Jm dumps ANO Atmospheric Steam dumps AND Alii<san< generator safeties 3)

PlantinMode I 2 3 ANO Loss of seCo<< i)iryhest sink has occurred ANO RCS bleed irii)Teed is <e<tuired.

1)

Plant in Mode I 2 3 AND Loss of steamielease capability from all ol <he following:

Lither I, 2, 3 o< 4:

I)

RJJCIOr Cntital ANO failure of <~sector Pro<schon System to initiate 4 tnp signal when a uip Ietpoinl has been a<ceeded.

1)

Reanor ciiticsl ANO Reactor fails to trip on aulo<nJtlc Sighsl 3)

Reactor criucsl ANO Reactor fails to tnponmanual sigr<al 4)

Uncontrolled RCS temperature increase due Io Ion of decay heat removal cspab< lilyIrom alt of the following:

4)

Plant in Mode I 1 3 ANO RCS injection capability has been lost from:

a)

Chs<Q<no pumps ANO b)

High head SI pumps a) b)

c)

RHR systein AND force8ltCS circulation AND NatuiaaRS circulahon v'2]<s<<

Iau 4<'o< i el<st wl TO. Loss of Sate Shut<)ourn functions UNUSUALEVENT ALERT ta<urv ol feei I<S~ii<~oh Sys<eih <u <h<u4<e Jnd compte< ~

4 reve<or <lip vI<ii<liWings

<Iie

<vs<<or su<re<<<<<4< 4<< hd<<4<ed by<ca<<oi ivmvirvng <<<<ir4<

a<<a< I>>p snp<4I n i<v<<4<ed OR RI<R synvrn nut upv<JWe oi

<nab<lily Iu su<<4u< Iorcvd ur natural cucuteuw< which results ininc<eJung RCS Ienipe<atu< ~

Js seen oh wide <4hQe loop tempera<we<vcurde<sor Core

~ s<t ll<v<n<u<uup<vs ANO ghgul <Iw lulluwn<Q, 4)

R<<R pun<ps iwt <u<uw<g OR Ii)

Nu I<uw i<W<<~<vd oi<f I'<os OR c)

Nu slow wiluup liow OWi<4<uis SITE AREA EMERGENCY I) 4)

A<<4niwii<l<4iuiruned

~ vi<ui<IIlu us<v< 4<i<inul sllu<uuwlisyl<w<liwi<<<

I4ilviv<u Wuw <e4<tor

<vu< ~ sr i<4< withCunuO<

<ui<hi AND 4)

Nuauiedunwgv un<<ivili4<vlya<eden<

te g VRMS I< 10 <<o< 4<4<m<rig)

OR 1) toss ul IunsbOn Ol une of lhe followu<g l<wr heeded tor hol shu Wuwn S<<wnsvsten<<nope<able OR h)

Cm<<lvn<v< dunip<,

4<n<u<<<hv<<< dun<in. iuW

<<v4<<i (Jv<ier Jloi 'safeties n<upv<JWe OR

<)

Nun<innvl 4<W Jun<< J<y Ivvdw ilv< Iluw OR il)

<i<am<i <y Iu nivicup 10 <<ie

<<LiIl~<4<<vi<iiv<vI<<Q<i 4 vsu 4 v 4 vihui < IfuwI GENERAL EMERGENCY Reactor

<erne<hi<i<<<eel afi I<shush< induced trip uQ<<,

un<is<ed ANO

~)

RCS pressure ) sJI ~ I<

valve se<tn<gs

'OR b)

Con<unman< pressu<<

temperature <here aur rJp<dly Consult Tab< ~ 1, Page 20

<<r44i<Lu is<ere. dpddr'Pi'c,. err'Arva t.A)trs l

~

r'ra r<rik CCJLZJEVan4 ef 4m< fey~ Ar ~~ P suLJ A

'p r

~ s evw~s J

~t'<<c4.0 Ae L tocterc.

• tr'Jg Q)t saucy:CM ~r COME pop )

I<))

9'surA4 stpeavf< 4

<fdic-foe'r~~ pc~<<r~

TABLE 1

'j EPIP 101 EMERGEN Y CLASSIFICATIONTABLE

9. Fuel Elensent Failure GENERAL EMERGENCY Putt element failure as defined tn5rtt Area fmergtncy of this secuon I

AND

'Anyoftht fdlowingn inuninent or in progress:

4)

LOCA'with loss of con tkinrntht Cooling OA b)

LOCAwithloss of con tainmtnt inttgntywhich provides a llowpath to Ihe eninronment Qh c)

Steam generator tuberupture wvthurusolabt ~ llowpath from ruptwed steam Qehwatorfs) to tht eiwirohm tnt.

CAIJTIOff: Cohutlt Tabl ~ 3, page 39 for required protKtive action VKoiiiiilthdatiohs SITE AREA EMERGENCY fuel eltment lrnlurt as indicated by I, 3 or 3:

1)

Con fitmed ACS OfQ I~ 131 sctivt ty t 300 pctrgm.

AMO RCS Ttuu >E3IPP.

3)

Confirmed RCS OfQ I 131 acliinty a 300 pCirgrn, Atro Core tritthtrmocouplts

> 700'F.

3)

Containment high rangt radiationmonitor reading

> t.3 fa Rtmrhr.

filhtrI, 3 or 3; ALERT I)

Conhrmed ACS DfQ 1.131 acuvity a 300 pCi/gm.

3)

Total fuel lalurt of S55, 3)

Anincreastof ) ISS futl failure in 30 minutes.

UNUSUALEVENT I

tatK tlwlTechrUCai RCSacuvity sgr Specification 3.1 limitfor maximum RCS activity.

Qrtdc) y.'I Ji'ot I v)ol4 I

11. Fuel Element Failure UNUSUALEVENT 4NIcivrJ I~ Idowh Iihe

~idioa livrIy 41'u ups ised liy swvcv ur viridcram oh PAM5 A lo Atro CwtlnrNeo AC5 sanplc indicitcs IliilIool4Ill4c I ivir'ris Qrc41 cr illihIlia ICCINUC41 5PtCllic4IIWI Iilrut lul nlivnnuln Itie Iin CooliiiliilivlIy ALERT AC5 simple uwvvS I 131 OfQ ACIiVily) Joopci/illli OA PRMS H l0 siuiiihiintly4ltuvt

~1am pwniw iuivvyniuii~Its nurccicilIclouvvii4iic Kit city irNt lituuclwyciiilrNs sltovvs anuuiccwuicavr Iliai ISS lucl 4ilwciNi 10 uni wits Wi lotit fuel lalwc ul 555 SITE Akt*EMERGENCY I)

CWtilinr.nJVVVrlltutnitvquar~

cwc auurnuJucicrrturicusty,

~ )

III5 I I I I Ot() viiiivily) roilIICIIIIIii Art0 41 Nts li.i ) afu'I w Cuit ciir ilicrminuuluc ) )00'f OA ll Cwilunnncru tnstttrninJV rnuiulnntniwulw rcafshg ) I I fa Wlu GENERAL EMERGENCY 11 fWl Clad tvUIWe 4S dehned in 5iI~ Asti fnitrgency of tins section withone afdrtrcusit Ilsuoh produc I barrier lost as iVhtict Iw loss ul Iliallwu tittisttuticctcdby

~)

tctiowri LOCAasdthnwl 5ccliwi )ulSII~ Arcu fmc IIJc hey with cohlahmthl piesswe

~pin uci I wig dcu Qh liiiuI Ol Cuhl4ihnithl Cooliiig llisbiitiiIosl w IcNIIa hhltnt 1a Iiri9Io isul4 It whittipiOvldtS 4 liowpiilito tlw cliviiuhnwiil OR b)

Rirud giuss faluie ol sicim gcrserator lube (I~

Qit41tr Ih4h SO Qpiri)wil aradiOKliwty IIOwpith Iht thvrrorunttll ~ s indi Cited by.

II)

Mtsmatchbtt ween clwgrng liowund I el dowil flowoi dtcitiung ACS piassur ~ cu presswraer ltvtt AHO g

IJp'r +rr w 8 o ~ ~

IIIicaglvg cr i~v>> '6 g

Qcl t) Ca<<c O'Cd 10~

CtIYYita1) 2

~ 44 h lerf, Aa g EO ra('vcvv wtpa 3)

$ w ~

c~ G'tvvI fe d' re~

'vtsttcvfi0 cr'.)rvr ~ -

uv 44v fo/kg C

S)

SA pl'fvd~

tb

~INTT3.

r 3JOI)t>lr'IL p Ph ~

ude radioactivity is indil~Itd by valid ilainsonpRMSR 1

or R 19 or by arsdyu of secohday san+v Alto (3)

Mainsleimlint tueaa between Contarnmtht and MSlvor nlanutam line brecA downstream ol MSlt withimmlhctlt IN icluifM5IVlaluie

TABLE )

EMERGENCY CI.ASSIFICATIONTABLE EPIP 2 TO. OE)ser Plant Conditions Requiring Increased Awateness gtnergency Coordinator's Judgetnent)

GENERALEMERGENCY Emergency Coordinator'sI udgment that Other planl COndi liOnleciSI whiCh nuke release of targe amounts of rarhoacsi vrty,in a shon period ot time, posuhfe SITE AREA EMERGENCY Emergency Coordihathr,'S Judgement that other plane conditions cciilwhich warrant the precauhonary noti hcation IO the public neK the Ate and the acuvauon offPL and offute agency

~mar gency response personnel.

ALERT Emergency Coordinator'I Iudgemeht that other plant condiuons ecist wlvch warrant them.reeled awarenessand

~cuvauon Ol I her gency response personnel.

UNUSUALEVENT Emergency Coordinator' Iudgemi that el her plant condltlone ear st w warrant increased ewarenma ante part of the operaUng staff and/or I offute authonties.

CAI)hON: Consult Table 2, page 28 forrequired protecUve acUon IKommandaUons

)IOTE: Actlvalionofthe Emergen Response facitit'les does nol require declarationol an emergency or enuy into a stwcinc emergency c asuficauon.

y, u.tu e ~ I R hie I

)l. Other Plant Conditions Requiring Increased Awaieness(Emergency Coordinator's Judg>>

ient)

IIOII ArlivaiiOAOIIIW tni~igcncy Rclpohie facilities docs nor icqv<<e dc ilar a noh el ah eiileigvlliyui cfiiiyliilo4 urer 1lii cmcigcricy 1 I iiiiIII41 10A UNUSUALEVENT I)

Emergency Cour diiialol'I

- tudgmtwAI llialollwiplaiil Conddiunieini whiChwarrant iiiiieaicCIawaieheii OA Ihe pail ol Uieoperauhg slaii ahdror IOCal Olfule auriuuilict ALERT I)

EmcrgcruyCuurdirrator s

Iudgcinchl ibai uilwiplant curWlhuln calli wlecti waiiaiil IlwIACicairil4war Ciieiiand aclivahcu'I iilciiiciiJHicy Ialliohw Irc1iui4 wI SITE AREA EMERGENCY I)

Einciuciuy Cour Juralw'I

)ullitvillelllll1al O'IliclplaAI rorWinurn eiiilwlecii warrmil the pr el e iiiuiiaiy IinIIIII4 IioA Io Ihc Iwlithi war llw ule ahd Ihcaciiva<<uhulfPI aiidottut ~

~14cricv cuicigciuy iciticaiw per tul 11 11' ENC EIAHgency Coordinator'I tudgmenI I liat olher plr'll coAdilioASe ~illwlvch make teleaie of far ge amounts OI

~ radioachvity. in a shor I pena ol liine prnuhte fe g ~ shown lintel two hiuon prod~et barners wiiiiPOlcnnal for Ioi o I lhe IIel d)

GENERAL EMERG Y

I)

Citarual IQ Etawvaf

<yac..gc-vafcrervca+r lose.

oF frssiara Pralea cic Q.

TABLE I EMERGENCY CLASSIFICATIONTABLE Eplp 201t T T. Uncontroffod Efffuent RA)ease GENERAL EMERGENCY IIT E AREA EMERGENCY ALERT'NUSUALEVENT Performance of E PIP.20126, Olivia Dose Caiculation ofoil<<to swvtys

~ indicate dte boundary elPoswe lewis neve boon evctoded Ji lhd>Cat td by

'shef I~ 2, 3 or J:

I) a I Ronvtv whose body 2)

R I Iten integrated whol~ body dose 3) h S Renulv thyroid J)

R SAom)nttgrattdthyroid dose Pefformanceol EPIP.20126,0lhitt Do>JCJlcutauonor olluttsurveys indicate vtt boundary e Jposul ~ levels have bttn escoeded Jsihdicattd by

<<ther I. 2, 3 or a:

I) h SOmR<<hlhrwhotebody for Illhour 2) k 230 mlttmrhr thyroid lol lrl hour 3)

R SOOmaenurv whol~ body lor 1 minutts J) 2 1500mRem>rv thyroid foll minutes

~

Afeltast to tht Uruostncted Area has occun<<t ofi~ in progrtsswhiCh

~lceeds ollhor I or 1:

I)

Ten urn<<i Technic Jl SO<<elf>couth 3.9 limits lo QJSIOui l<<leJl ~.

NOTE: Direcl Chtmntly toptlform off<<to dose estimates por Ep>P 20tl6.Olivia Dose Calculauons.

2)

Ten umes fechnical Specilicmlon 3 9 Amiss lwliquid rett Jso, NOTE: Direct Chemistry to perform release calculation in accordance withOlfsile Dost CalculatlonManual.

Aftltast to the Uhftsulcted Area ha occurred ofls Ih pfogftss WHch

~scteds either I or 1:

I)

Technical Spedfilcation 3.9 lim lorgaseous release.

NOTE Direct Chemistry to ptl fOnn oltvttdose OSUlhates pef EPIP 1011C. Oftv'tt Dose CNCulati or>L 1)

Technical Specification 3.9lin forliquidfortJst.

NOTEI Direct Chemistryto perform ftleast cat cut Jt>on In Kcofdance w>UlOffvtoOov Calculation Manual.

NOTEI Sist boundary equals I mil~

fJdlui rfonlJlrtcttlrunl t.

ICAUTION: Comult Table 1, pago 20 lor >tow>ed fvoiectlvt I

Kul<<lrKommohdJtiom NOTE: Site bouhd Jry equals I nlil~

r<<rlus Irom Jllocttd unit.

cAUIlok: consult Table 2, pJge 26 lofpot<<bit protecuvt

~cl>on><<comm<<ndauons CAUTION: Consult Tabl ~ 2, page 20 lofPoi>ibt~ tvottcuvt KtlonfocCHllmehdJuohL CAUTION: Consult Tablel,pageld for possible protecuw

~cu on Itcomnithd a'll oh'v Ou lv I O v3 e) 4 Ib 'I

13. Uncontrolltd Effluent R a)ease ALERT 1)

UNUSUALEVENT 11 AleloJwhal occuffod ol I~ In pf09>est wruch e lcoeds:

J)"

Caitousrelease Itch>veal Sooc>hc Jllohs Nnul al Sllownbytampl<<OR Ji lnd>cJl<<tby trw plant voht hobi~ Qas mon> IOIIe<<unQ ta IJ. sp>Hco AJ>o 3>c o>>op-o67, uyaslt 0 >pesos System Acrid<<h>JI R<<loose ol Rod>OKI>v<<

CJs)

OA 4) t>qwd>tttest fecruuc JI Spec>I>cat>onsbnut as Shown by Sample Jnalyut Du<<ct G>tnusuy to ptrform otfu to dost tsumalts per Emernoncy Pyoctdwe 2012C,O}f $>te Dose Ctuulavant AIolJ J lo Ihal r>J> OCC<<>ltd of ls in p>OQ>tn wluch ligreater

>lian:

J)

TRIIt>fftfI lho QJsooui roloase ftcluucal Sptclucauonshmit as Ihewnbylalhpltof Ji 4<<I<<JI<<d 4y lhe hioh rJng>> Plant vent SIT>NCJ Ihohllol IvJdulQ Jnd 3>J O>lt)P 06).WJSIO D sposol Syst<<m Ace>den( Ji Rcl<<JS<

OKtive CJS, (R low>llutullttalerugh) DA b) 'Ivn l<<h<<1 the llqwd rittosefectlspoclimlt Js sl<<>wn by SJlnPI ~ anal yvs NOIE: D<<<<lt Cl>onusrrylo p<<llwm oil<<i <<dole O>um Jtet p<<l Em<<fnenty Proledwe 20126,01( Slt~ Dose Caicul ~lions TIOSI: COnSul t )atua 2, )N CA CAUflDN"Conwlt fJbl<<2. 2N HOTE SITE AREA EMERGENCY GENE)(ALEMERGENCY I) Arelease has occwl<<for>sir Pleglessrosuiungin I Rdv whole body or an >hteglated dose of sarhr thylcud at vtt boundary(l nufe) as determined by perforn>ihh Emtrgoncy Proctdwe 10 IR, oil Site Dost Calculauons or por folmJhce ol ollute swvts II! Arel<<vso has occurred or >i In prug>tssiosullmo>n Sgmlbtv whole body or 150 mR>tv sl>)>Old lw II2hour gr S00 n>Lru wnol<<body w 2600 OIR/Iu thy>old lor 1 Ihlnutos Jt the<<I<<boundary(t mlle)as d<<t<<mined by polio>nu~ En>Owl<<Or<< Procedure 201}6. Oll Sllo Dos<<C aleut Jtlena Or by P<<llwm<<<<e ol ullute survtyt. CAUTION. Cuhlult Iable 2, page 20 CAUTION: Consult fable 2. page 16 C'tshs 4 4 'E>P<<~'fit +tfc>>La, to TS L } hl P3DUF ~0 >)>)of ), vIIyfs ASJI v CLJ'ws hl, yfcpLvfiJ Aul'J vier W haul> P fJ~ -~~t Ehf Sh 4 TABLE 1 EMERGEN Y CLASSIFICATIONTABLE EP)P 20 xxK

12. High Radiation Lcvcls In Pfant GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUALEVENT Containnwnl H<yh Range Radiation Monitor reading >1.7 ES Rem/hr.

NOTE: Direct Chemistry to ptrform o1 hite dost esuma Its ptr EPIP-20126, Ol 1 Site Oow Calculauont. fSee Stcuon I I ~ Unconuolled Ellluent Reteaw) CAUTION: Consult Tablt 2, Page 21 Iot reqwred pro<Ktive KlionIKommehda tioAL Containmtr<t High Range Radiation Motor reading ) 1.3 Ea Rem/br. /- NOTE: Direct Chemistry to perform oIlute dose estimates ptr 6 PIP 20116, Olf.6<It Dose Calcul ~ I<0<is fste Secuon 11, Unconuol ltd 6llluent Release) CAUTION: Consult Table 2. page 26 lot p<nublt ptoletuve KtionrecommehdauonL Either 1,2 or 3: I) Anyvalid area monitoi alKm from an undeieimmable Sou<Ca vvithmettt heat or 9<taltf tlwil fullscale deflect<on flglmR/tu). 2) Uhtapet ltd plant iodine or particulate a<<borne cohcehua<<oh b'000 MPC as ptt 10 Cr R 20Apptndia 8, Tabl ~ I. 3) UMapected dirKlradiation dost rale rtad<A9 or uritaptcltd alibortw radioacuvily conctntration from anundeltrmined source in Recess of 1000 times normal levels HL4<<'A v)OIDI 1C. High Rad<ation Lcvcls In Plant UNUSUALEVENT ALERT Ahy variJ>>44<lluhliui 4<vh< 1<tin ah ura<4<v<<mhaul ~ source wi<hmvi~i hvai w <pea<el <lith lullsa4<e dvnvai<W< 1 luih<H/lul OR Uhvina<ltu P<4A< iudiht or paturur4<t a<I@Nut coiiceh<raiiwi > lt<caIMPC ai Pet 1t< Cl H ru APIw<NI<~ II, 14bl ~ I, ~'i attila<<it<<I<<it su<ac'y<AQ or san<pl<i<9 OR Uhvaptc<val duvc< i>>ua<<oh dost<mr <vaa<N<SI ui NMapv<<ed 4uliuuw rad<oaauv<<y awuvhua<<oh liwil4<i a<INIv<v<iilll<4u<v a<hi<at <h 4 i<an ul I OOO <Nhel <w<mal Ivvvli SITE AftEA EMERGENCY ll Coi'ii>><ihlwi<I<igl<H4<NS4 Ran<.<<uva M<NN<ui reading ) I II4 W<i< U<iv< I I I<4<Ah<<y <u lit<Iuim oIINIvi<uiv via<i<i~<viptr 1 hw<gaiu y P<utvd Nit )0126, Oll 'a<v Uuiv Calaulauuhs, Io dviviniuivh<>>3<uludv ul ~ 1lluvin <vlvaae tSve Svauoh 131 CAU)IOH Cwhuh Iaulv 2. page Ja GENERAL EMERGENCY I) Co<i<a<Ah<ah< ss<QI< R4AQe Red<4<it<i Mori<<or itaJihg a I 3 6 S R/tu 0<<KI Clw<ius<fyIoptrlotah olluie dose esumates pet fmergency Procedurt 20126. Ol1 S ie Dose Cafculauo<<L ic dtiv<<mM h<49<ii<witol ~lllutht release 1$ee Secuoh CAUTION, Cohwlt fable 2. page Jt ~Art Ca I- ~ ) ~~ + npf J, taa caa<um) daw<pls<v) ( mat avat. (oufya/c. as t,uCare.) TABLE 5 EMERGENCY CLASSIFICATIONTABLE . t3. Other Plant Conditions That Could Lead To Substantial Core I)anlage E PIP 1t) 50'age 5 XX/)OQK GENEltALEMERGENCY 1: ither I or I Potential core damage IAdICaltdby all oftht following: ~) Known LOCAgresttr than wsilsblt charging pump capacity AHO b) Failure ol ECCS to deliver flowto the core ANO c) Contaihmtht Hi9h Itshot R<<tistioh lAÃlltorIt<<flrig > 1.3 Ea Ittmrhr. SITE AREA EMERGENCY ALERT UNUSUALEVENT Potential core damage'ndict'ltd by all st tht following: ~I Loss ofsecondary hest sink ANO b) RCS ~snd feed I squired AND c) Ho big~a<<t Si no available ANO d) Ho hIIIITiowtor greater than 30 minutts ANO e) HoAIW)fowforgrtater than 30 minutes, Ullotf: Consult Tabl ~ 1, page 10 for required protecuw ~ctioh reconihieridstlonL rl O IOI 1$. Other Plant Conditions That Could Lead To Substantial Core Damage UNUSUALEVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY II AinOwn LOCA aS dehned in 5<<lioll Iol sil~ AIta fhi<<itency <<NI l<<lwe ul LCC5 Iodeut<< llaw Io iliacoit rirs ocluiiedltsurllng ih clad dam<</t rs ind<<el ed by cohlsinmtnl wta AioAI lors PRM5R I ~3cr Rt aa Coill<<MIltnrHigh RaAge Raiilauoii Monllw4I<<himg oa GENERAL EMEILGENCY C)IA~C ~ l4c~ Z )dh;s sM 5) lnsLuei ~ o+ I.ock GE t~~v~. I lo/etl) c.e s /I ~ <<h'<<vc I lr4) Lass I%4 '4o S gr'<<JI ~ P frss ~ 4 ass~ r crrC arr Sri 4 ~ Reactor IflpoA low srtsnl gen<<aror trelsurlliwide 'r<<igt lasers aptu oaclrng C<<O wnh loss or m<<n condtinti. loss olwiih<<ylead liowand no hlghlWad 54ltlyIIIiecllon capauihty Img to ihinults has ~Iapwdwillinqlowliard 54tety Ihitcuoncapatrhryoi ausihaiy ised liow OR AsnowhLOCAasdthn<<tin 5eclioA )of 5iltArts tm<<rrency liaS OCCWied tnti one oi lhe Iollowing sl RHR flowindicator is II, ~. 60$ Itsds r<<o lor Irlievr ail<< ltcilculauonphaseis ~utmpled snd RC5 Ithip<<el we Is IraA9 OR bl failwtotloni<<nmeiu Sorry ahd tm<<gtACy IooltiiIoPitrehl COAIalnliltiIIItilip<<4IWe horn IiungtIctsurtry CAUIION C~l ta&e 3. la ~ I ~ ~ ~ ~ ~ I '. I I I ~ ~ I TABLE 1 EMERGENCY CLASSIFICATIONTABLE T7. Notur8) Phenomena GENEIIALEMERGENCY 4~ot natUral ever>t (t.g. ~ Ngh <<fnda, earthquake, hOOding) haS ~cwted, which ccwld cause massive Ianeye to Plant systems rtsvlting in inyof ttw ottwr General Emerytncy Aitlatiny conditions. ALTON: Consult Tabi ~ 2, paya 28 for required protecuve ~cIoflftcoti>l71Nldatiof>s. a) b) c) Confirm ed burr)cant warning unth marimum wind spteds in ercess of 22$ mph. Olt 8 4rthq uatt'a I c4vsed Ios s oI any safety system function Hvtficat>t/floodsvfgt Chat raises water level s 18 ttet ~bcwe MLWand rmtts in shutdown of turbine gentrator ot teaCCEÃ, SITE AREAEMERGENCY Plantin Mode I 2 3 4 AND either a, b or c: ~) b) c) d) Con lirmtdhuuicane warning vhth marimvm vnnd speeds >n e tress of 200 mph ON Tornado stt>Ling any power block structure OR Eafthqv Jilt Ii>JS could cJust or has caused shutdown ol the turbint gtnetatot or reactor gh Hunicane/liood surya that rasts ware/ level > SS feet ~bow MLW A).ERT Rant in any mode including dtfueled. ANO either a, b, c or d: UNUSUALEVENT Plant in IVlodt l 2 3% AND either a, b, c or d ~) Conyitmed humane warning ON b) Confirmed tornado ln ewnet controlled arta OR c) Anyearthquake detmed onsi> d) Hwrkonetflood~ that Pftwfltslahd access to tht site g,gu1$ 1 oM

20. NATURALPHENOMENA UNUSUALEVENT I)

Plan> Aoi aI cold ~>down ahd ~ os Ilia lotlowiny: 4) Not>f>rahonby Iht wtn>I>tibi>itJ>I Ol a l>>i>idJAJ warm~ OR b) Cohl>imrd Ughf>hg ol a tomato in IliaOwner CoilttolltdAtt4 ON c) Ahytat shqvake Itis of dt lac ltd on installed Stl>m>C >AII/Ui>>et>IJI>OA OR d) Hwr>cuw swats or it ooch that linus JCCJSS IO tht u It ALERT I) Plant a> ahy mode ol~tat>on JAd olwvl II4'lil>owiliy: 4) Not>f>>4>>>>nhysht wtn>I>> i hhi eau ol lhe a upi >>4th of 4 hurricane will>w>>>>IS nt Or neat dtv>SAI>nust 22$ MPH) level> OR h) Anyt >It nqunke thai Could Cau>t, At alieady caused Shv(down ul Iutt>>nt gtiltinIV>hhd/ot ItJCIO/ OR c) hhy III>>xlot t>>>the ant SV/gt II>alI4>~ IritWJttf levtt Io 41 m near the dtugn level Ol l8 Itet above M t W OR d) lot>><<lu>tt>k>>>yawny t> Idvck utvtt>>t ~ SITE AREA EMERGENCY I) Pfah> gh> ih ~>~IN >~ow colldilivi>dlJv ally AAfol Iht lotthw>>>>3 4) Ht>>>I>>.>>>m>by Ilia wtn>l>> i t>>>>tnU ol Slit +it>>i>a> ti I>I 4 livttie>>At w>>I>wn>>h > 22$ rhph Oil Ii) A>>y e.>>Iten>ast Ili.>I fasts Sl>UIdowi>ol Ii/tin>&gtiwfJ>ot JAd/of It N>i>> Ihvpltilwi'll> (Itgl >>I.>tioi>Ol 14 it>'y 1yslriii\\ ON c) Iloud vl S>>>ttic4At sUtgt, II>41 A > dtugnltvtl oi l8 I tet.md Cann st >>>I down OI Iii>I>>hegtf>tfalvr and/At itat>OC wsh devi Vital>m>ul safely I \\I>'ill> GENERAL EMERGENCY I) AmHoe>AI<<nolo> t>>einat trent I~ g, sita, earth~wats. plant CtJshts) has dec u/ftd, wiveh could cast masuve ccm>hoh d~sge Io plnhl svs>th>s i ewlf>>>g >n any ol Ilia o>twas G~nt th arly ii>>I>41>hg Cui'>illI>oin AUTI 'Conwts lade l. I'ayt ly Cnst~ al p k arP op St>ar kc, va Lug 4r ~. ~ A' ~ At~ I CSAIL a ( f OV 1nsI n n>0 ) "n h)0QC, 4)nr +r~ )a+ f ~ t ~ i ~~ I SR A.A ~,A ~sA,o> ny S a I ns> ~ ~ Sw g)OJ.C, rm tw ~y ~CE" I . r. "/-~v i ~ I )2 r1 >i
• 0 Au nvl~ ~
~ a( (I TABLE 1 EMERGENCY CLASSIFICATIONTABLE EPIP 2010 P>log 2< XX/)Otf8' 1$. Itazards To Station Personnel And Equipment GENE)tALEMEltGENCY ~) b) c) Aircraftcrash OR Missiie impact CLIt Kaptowoh 5)TE AREA EMERGENCY Either I or 2: I) PfantinM<y. I 2.3% ~ Af<D Sa Ntysysttm~miaye ftiled or structural damagt to vital structures has been caused by ei Ihtr ~, b or c: Either 1,2 or 3: ALERT ~) b) c) Airerah crash OR Missile impact CLN Eaplowon I) Aieduc<ionin the levH of safety of plant suuctufes or cornpontntswithin the protected area due to damage caused by ether a, b or c: UNUSUAlEVENT Safety of nudear plant or personnH threatened byeither 1,2,3,aors: \\) Hrcraftcfa<honsfte 2) VnusuN aircraft activityover facility 3) Toaicor hammatdt yes<elec<a NOTE: Eaplosion Is defined as a rapid chemical rtaction resulting in noise, twat, and the rapid tapahsfon ol 9as. 2) Toaic or flammable gas release Into control or vital artas ~hich renders one vain of safety related systems inoperable. NOTE: Eaplodon is defined as ~ rapid chtmicJl reaction resulting in ACN'Se, htat, JAd tht rJP<d ea pansi on of 9Js. 2) Toaic or flammable gas< Htase which threaten plant operation. 3) Turbine generator failure rtsultf in casi t rat ion. I) Tvfbifieyentralof rota<<Ay component law lure ft<tui<ihy rapid twbine shutdown S) Onsite txptos)on NOTEI Eafdosfonf1 deh<ntd as a rapid Chtmi cal reaction rtsul tinyin noise, fwat, and t)wrapid ~ ol 0,/t)ct a2dvieiorJ

21. HAZAROS TO STATION OPERATION UNUSUALEVENT I)

Occuwenct ol cvenn Chat could Ihfear tflIhtsalt ty Of Iht <writJf p<Jilt or ptisohAH as ihd<CJ<td by Iht follow<fig: ~) Ahy Jaw<alt<Ca<ho<sutta< li<WS<ial Jut<aft JCI<v<<y Ovtf IJC<t<<y OR bi Ohw<ecaplowon Hots: An eaplos<on<csut<S l<om a IJP<d <liam<<HitJcwon Iesolling wiIht rHeJse of noise Jhdlwat Jhd <lwrJpid ea panuon of yeses OR c) 'foaic o flJmmabt t gas fHtJst AcJf of onwle could threaten personnel OR d) RJP<d Iwb<h~ shutdown due lo Iwbine generator foI~I<A9component fadwt 2) ALERT Aire<J I< c cJsl iVAust invelvih9 plant II<VHVCC OR Mnwl~ wiil)4< II lions Jhy sovrc ~ dam Jg<hg PIJAI a<rue tuft<or COCAPOAC<IIS Jlfcc<ifigplant sJN<y OR Damage <o p<,sni suwcturts w CCN<IPOAtlliiIivlhJii ~ CPIOS<OA J Ilec wwg Il<ail< vlacfJuan HOIE: Aci va plowoiiresults Iioih ~ rJINJ clicwii<Jl <vast<on ~tsol I<i<9 wl IlivfeltJwf ol Aoist ~ JAd heal 4 <<d <ht fafwJ ~ipafisioiivl <f4<vs 0 II Oclectionhy portable <nsl<umtn< Juon, o nohhc ation Iran olio<a soviets<I<at gases PtJ<t< Ilia<i<lie<< Ioaic oc I4<AmJ i<It h <his S havt tnt ared Ilia fJ<ih<y lwisuig J IINCJI IO Pl ah< OPt<4<iOA ON lu<twnc show<Own vw<h ob st< vel<on 0 I cJ sin9 AtIiJI <AA SITE AREA EMERGENCY PIJAI Ao< 4<cold slwtdown AHD al awe< JII C<Jsh <csvlt<hg In il4< hJg ~ I0 viIJI IICut Iu fts O<<ON<Pont AIS by impact or l>ii, ON Ii) M<sw<v wnpJCI o cap<OWOn icsw<iwigin severe ham Joe io vila<y syucms NOIR: Ah caplosi<wi fcsul<s Iiuin4 fJul <Iiciiili4I <c4< Iiof'i ftsullwvlm Iht CHtJse ot holt Ji<J Iitwt Jiwl Ilia fapl<i C afiJl lwiN Iill(j4\\Ca Olt ci tlliiyiil<JJscsg<CJ<tf II<J<i t1<v<<thai< or ilJmm Jbfe lihii<swi<vcon<iul or vital Jie iSJWJ Wha<hfendtrs <NivIt ii<1ol ~ sat tl'y ralJ<rJ sys<ciri w<optfatfit GENERALEMERGENCY C3t Aaa daf Ci.r.....- q',...,>. ca<' <a wtaa of<<a f <c EC,. gt + ~>>av~ ~ Tw.r N It CJn (KC '4, TABLE 1, EMERGENCY CLASSIFI ATIONTABLE EPIP 20) XXfaCf 1%. Security Threat GENERAL EMERGENCY Physical at tack on tlwplant tosulling inoccupauon of UwConud boom ot other >> tal <<eav by InuuderL SITE AREAEMERGENCY Decl<<ation ol ~ Security 6mergency involvingimminentoccupancyof the Conuol Room ot other>>tal areas by rntruders. ALERT Oect<<ation of a Secunty Emergency UNUSUALEVENT fwd<<Ãionof~ Security Alert du toetther t,3,3,4,5,6,7orL I) bomb throat Ctft)Off: Consult Tabl ~ 1, page lb for required protecuv ~ action recommendatlons. 1) AtlsCk threat 3) Civildisturbance 6) protected area intrusion 6) Sabotage attempt 6) Internal disturbance 7) Vital area intnnion 6) Security force suike Q/+ Ibsen s L i a + 1X SECURITY TIIREAT UNUSUALEVENT I) Serunry CenurWOnry rervr ln Wues4n ot P fP Sal ung Conungency P4n bg r4cratatlon ~guards of~ SecwltyA4rt soonest snore ol the trams liswd be4ur. ~I borob threat b) Att<<k throat cI Crvrl dnturbancp d)" protected voa usuuuon ~) Sabotage attempt I) cornel dasturbanca Intel <<ca ustruaion Socurir force suite. ALERT ) A Secwit fmv 1 y decl<<ed as delirwd intlw Sa4guards Condngency P4n. S)TE AREAEMERGENCY I) A Socunty Emergency'nrvohring unminent OCCuOanCy ofthe conuol room or ottwt vital areas to ttw reactor systerts ~sdekned In the Safeguvds Contingency P4a I) Physical attack on tlwp4nt ressdtlng Inoccupat4n of control roora or other >>lal Q!055 Consult Tab41Pago lR. tsa tao u I) par~& ~ v/dr e. + ~ <Cttr ~ EMERGENCY CLASSIFICATIONTABLE XXI)fX/89

t. LOSS Of En )nacred Safety FcratilreSlfire PrOteCtiOn 9

GENKRALEMERGENCY SITE AREAEMERGENCY ALERT UNUSUALKVKNT Either I or 3: ll Power reducthsn started In <<cordance withTechnical Speaficatron 3.0.1 to comrdy withone ol the foilowint): a) T<<hnicai Specification 3.3. Cols'Iarlillieh'l. OR b) Techie specification 3.a. Tnpiheerine Safety FtatultL c) Technrca) Specification 3.$. Ihstrumtntatiori. Tahiti 3.S.1 through 3.$.3. 2) Fire protection compensatory measures not implemented wilhinthe tirhe limitsspecified by T<<hnical Specifica>>on 3.14, Fire Protection Synelhs NOTE: Consul t FSAItSection 9.0, for funher ouidance on fire prottction syst<<n 'r<<htnts g/9<) g,gui5io n) 2$. LOSS OF ENGINEERED SAFETY FEATURESIFIRE PROTECTION SYSTEMS UNUSUALEVENT I al toilol th9lhttrtd salt'I'y ltaluie sysrem fuh<liohal Capab l<<y aS Itqu<<ed by Iechlii<ai Sptcili<alioA 3 t oa b) toilof ihnl<<mania>>on Syiitm fun<irohal capabi>> Iy as I~(<<I by tact<<ural 5oecrfi< ~lith3 S, tables 3.$ I 3.S 3 ANO I) failure iortslor ~ syiltm luhc Iiohai capabiliiy or <Ohdu<l a plans Shuldown wiliunIhe a<>>on limes liiwlin Iht appli<ablt ttiluucaI Ssiecrfi<a>>oh Such Ihal planl shutdown iiI<<Iuirtd in a<<or dance willife<luucaI Spe<<4<a>>on 3 0 I NOTE the em<<geh<y Coh<hlion Shall bt de<la< td when load ltdu<>>on commences in ac<oCdah<t wilh Techru<al Sp<<ill<a>>on 3 0 I OR 3) toss of liltproltc>>on system fun<I<<<<saf capatul<<y in eactss of lhtcondrt<<shs and action times sptcihtd ul I<<hru<el Spa<ill<el<<sn 3 la ahd lad<<re Io ihiPltllithlCOmPehia Iory mtasurts vnltun Ihe sp<>oui S NOIE: Comull ISCIN Stc>>on 9 C, Ior )<<liber gurdah<t On hre Olt<lioni IthiI i<tin<<ill ALERT SITE AREA EMERGENCY GENERAL EMERGENCY

37. LOSS Of CONTAINMENTINTEGRITY UNUSUALEVENT I) vlolarronof cohlaihmthI uslt9<nyusdehnedin f<<brutal Spt<r fr<a>>oh 3 3 resul>>ng in lhr>>alroh ol shuldown ofIht ICIICIOC NO'IE:

An Unusual Event sliall be declared wlithactual load ltdu<iioA4t ihi CHhnf CCK I )not<<Pa~ Qltr) Q j p~r ~ />>3tr Q A 3 ~ pi suras w 5 ~ '<< 'r v ~ I n<+rrdrhtr Cuas 9'; Lr ar rsf I ~ 0 Id+sr>>)rs ~ ~ clr'<

21. fire GENERALEMERGENCY Amaior fu~ has occurred which could cause macaw damage to plant systemt resulting in any ol the other Gerwral Knwrgency Iritiating conditions.

SITE AREA EMERGENCY. Sire which prerents a safely system Irom perlorming its design Iunction. ALERT Unconv¹led hre potendally allecting salety systems AMO Olhite support reqoued. UNUSUALEVENT UnconVdled Rre witMnthe power Mock testing longer than I0 minute cAllyloss: consult TaMel.pagele lor required protects Te ~coon recommendauonL 4./Qct Ciusotod t) Unconu¹tod Srle ~rhrn tlw power trtodr tasting longer than 10 ounu sos Unconuollod Srr~ potentiallyall~ safety ~yssom ~ 0) requrrrng olhile supporL EA EMERGENCY I Sire compromising the unction ol sa4r ysyuonu. GENERALEIlERGEQCY Mcould cause roasshro conuoon damage toplant other general Bnorgoncy systeros resulting lnany oltlw Inldadng condidonL Consult Table l1 Crt's a F 'n,~or Cor& v pr ~ ~ o~ (A4 I' utter ~sc no (I ~ ~ 4 TABLE 1 ) EI<IF20 EMERGENCY CLAS IFI TION TABLE Colstrof Roosts Evacuatlors GENERAL EMERGENCY SITE AREA EMERGENCY (onvol rtoomhas been evacur ied ANO local control of~town sptems has ~NT been established from ~I stations within l S minutes. ALERT (ontrol Itoom evacuation anticilsated or re<tuiied UNUSUALEVENT et/1g ILf<pie<or

13. CONTROL ROOM EVACUATION ALERT I)

S vacuadon of control room ant idf<ated or re<tuued wlth conuef ol shutdown stntems ~stabti<hed from terat statist SITE AREAEMERGENCY I) Evacuation ofcontrol room and control ol shutdown sygenas notestabt<shed fromlocal stadons wiihinI Css<<,<ac< ss 5< f<l $<'~<o~ o4 (f ~ I <<v ~ )tie<'0 ~ ,I A b~ t p~h'mc.. 4 ~ lo '8 LI T N ~ if<< ~v~J s c'A TABLE 1 I EPICS 20 EMERGENCY CLASSIFI ATIONTABLE Control Room Evocsrotlon GENERALEMERGENCY SITE AREA EMERGENCY Control ftoom has been evacuated Afro Local control ol sRuutown srstems has ~sr r been established from local scapi'ons withfn 1$ mmutes. ALERT Control toonl evacuaUon antler fsated or reOu red UNUSUALEVENT Ql'l ti ILLvraio<<s

23. CONTROL ROOM EVACUATIOH ALERT QTE AREAEMERGENCY II EvacuaUond conud room

~nUcifsated or required with conud ol shuufown systems ~stabUshed Iromlocal stauons I) EvacuaUon olcontrd room and control ol srwufown systems not established from toed staUonswlthfn I C,'stir,ro 4 rr gr~pltgc~.e~ lac& c<<- Ic+ o4 Ce ~ I isa. ~ v'tier't > ~~r << '-t'ur +~0 i b& rr br ~p&rU'wc. Car y w~ rov '8 o.at<<LlisL~ ef vr sec ~ J u ~At TABLE 1 EMERGEN Y CLASSIFI TI N TABLE I EPIP 2C . Control Room Evacuation GENERALEMERGENCY SITE AREAEMEIIGENCY Control itoom has been evacuated atro Local control ol sEuutown systems has Ngy been estal hed lrom local stafions within. $ minutes. 'LERT Contrd ltoom evacuauon anticipated or rertui fed Q/1% ktvs<<o~

23. CONTROL ROOM EVACUATIOH ALERT I)

IvacuaUon of control room ~nucipated or required with contrrd ofshutdown systama ~stabNshed fromloral stauons. QTE AREAEMERGENCY I) Evacuadon of control room and control of shutdown systems nos established from local stations within t S minu Qs4+Igcr I Os ~ ~ I. our g, I o o,afaJLIi>L~ ~ I' pua h'~ O E'O i ~ p ~4 ~ pi ~v~ ~ J ilaw ~A 8 TABLE 1 EMERGENCY CLASSIFICATI N TABLE EPIP 201 1S. Contaminated Personnel GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUALEVENT rrentporletlon 0 Fon Irflled ~tternkly contaminated injured Indiviauktt) Irorn tite site to on ofrtjt medi k I cali g])g Rt hatt toQ cttls7I 1L CONTAMINATEDPERSONNEL UNUSUAL EVENT I) troll uor14IIENloitonlllrhed ~stenWlr ~@united snrM<ed lll4lvloUeldlifrom tile @le Iu 4n ollullmrdsrA Ioc>lsl ALERT SITE AREA EMERGENCY GENERAL EMERGENCY Crt Aaa c, IQ N 0 C.ho ei ga. ~ TABLE 1 EPIP 2tI KMERGEN Y CLASSIFI Tl N TABLE . Control Room Evacttatlon GENERALEMEItGENCY SITE AREA EMEllGENCY Control ttoom has been evacuated Alto local conttol ofsRuutown systems has QNTbeen established from loCal stalions within lS minutes. 'LERT Control Room evacuation anticipated ot requited ial\\oi g\\vssiosa

23. CONTROL ROOM EVACUATION UNUSUALEVENT ALERT S)TE AREAEMERGENCY I) fvacuadon ofconuoi rooia

~ntidpatad or required with conuol of sttutdown strstams ~stabtished from total stations I) fvacuaUon ol conuol room and control of slwtdovvn systems not established from local stations within 1$ Qstaktu4 ts 5,>> Piler& o~ 14c<<L c ~ tt<<f<< o4 (r ~ I is<< ~ r')let't >-<~ <<s << " <<.,t'ur <<~0 << ~ ) o 4s4AsliaLQ yi' ~psst'<'~ c e o ~ Xo T'ot W s Pi ~u~ ~ -t ~AP ENCLOSURE 3 LIST OF ATTENDEES NRC B. A. Wilson, Branch Chief, Reactor Projects Division, RII D. H. Collins, Branch Chief, Radiation Safety and Safeguards Division, RII W. H.'ankin, Section Chief, Radiation Safety and Safeguards Division, RII J. Munro, Section Chief, Reactor Safety Division, RII E. D. Testa, Senior Radiation Specialist, Radiation Safety and Safeguards Division, RII D.C. Payne, License

Examiner, Reactor Safety -Division, RII FPL J. J. Haisler, Manager, Emergency Planning L. LaGarde, Coordinator-Emergency Planning G.

R. Madden, Principal Engineer, Nuclear Licensing