ML20202C657

Forwards Rev 30 to EPIP-1.01, Emergency Manager Controlling Procedure (w/3 Attachments). EPIP Continues to Meet Stds of 10CFR50.47(b)

ML20202C657
Person / Time
Site:	North Anna
Issue date:	02/03/1998
From:	Matthews W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
98-060, 98-60, NUDOCS 9802120307
Download: ML20202C657 (5)

Text

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VINGINIA EI.ECTHIC AND POWEH COMPANY Hicnwonn,Vworn:A 20201 February 3,1998 3

U.S. Nuclear Regulatory Commission Serial No.98-060 Attention: Document Control Desk NAPS /JHL Washington, D.C. 20555 Docket Nos.

50-338 50-339 Gentlemen:

License Nos.

NPF-4 NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 REVISION TO EMERGENCY PLAN IMPLEMENTING PROCEDURE Pursuant to 10 CFR 50.54(q), enclosed is a revision to a North Anna Power Station Emergency Plan Implementing Procedure. The revision does not implement actions which decrease the effectiveness of our Emergency Plan. The Emergery Plan and implementing Procedure continues to meet the standards of 10 CFR 50.47(b).

Please update your manual by performing the actions described in Attachment 1, Tabulation of Changes.

Very truly v ours,

'du /? W W. R. Matthews Station Manager Commitments Stated or implied:

1. None.

Enclosure l-I.

U, cc:

U.S. Nuclear Regulatory Commission (2 copies) f I8 Region II Atle.nta Federal Center M V'b 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 Mr. M. J. Morgan NRC Senior Resident inspector North Anna Power Station ll!lll1111l'l!'l!I11IIll 98o2120307 900203 PDR ADOCK 05000338 F

P"R

s ATTACHMENT 1 TABULATION OF CHANGES VIRGINIA ELECTRIC AND POWER COMPANY REVISION TO NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE Enclosed is a recent revision to a North Anna Power Station Emergency Plan Implementing Procedure (EPIP). Please take the following actions in order to keep your manual updated.

REMOVE AND DESTROY DATED INSERT -

EFFECTIVE DATE EPIP-1.01, Rev. 29 3/1/96 EPIP-1.01, Rev. 30 1/23/98 Emeraency Plan Privacy and Proprietary Material has been removed. Reference Generic Letter No. 81-27.

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PAGE:

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IIO0trE ANNA 70WWL 81kTICEI

?)-9 LIST OF RAPS DIEMmWCY PLAN IMPLWWFFATION PROCEDURES 4

CNBCE DMIS FOR IATEFF DOCL8Wrt INFOIW4ATION O

m.c,.,U,.ER APPROVAL EPPECT**

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..D DOCu,W,, T m E EPIP.1.01 030 01/20/98 01/23/98 EsSRGENCY MANASER COIFFROLLING PROCEDURE EP17 1.02 010 03/13/96 03/10/96 RB8 Pow 15 20 Nor!FICATION OF URUSUAL EVEIrf EPIP 1.03 013 12/09/97 12/11/97 RE8PONSE TO ALENT EPIP 1.04 013 12/09/97 12/11/97 RESPONSS to SITE AREA EBERGENCY EPIP-1.05 015 12/09/97 12/11/97 RESPOWet 20 GENERAL EBEROMCY EPIP 1.06 002.02/02/95 02/08/95 PROTECTIVE ACTION RECO8ENDATIONS EPIP.2.01 019 01/07/97 04/11/97 NOTIFICATION OF STATE AND LOCAL 00VERIBGRIT8 EPIP-2.02 013 11/20/95 11/23/95 NOTIFICATICII 0F NRC EPIP 2.04 003 08/07/92 08/12/92 TRANSMITTAL OF PLAIIT, RADIOLOGICAL AND DEERGENCY STATU8 EPIP 3.02 Olb 12/17/97 01/07/98 ACTIVATION OF TECINIICAL SUProitT CENTER SPIP.3.03 012 12/20/93 01/01/94 ACTIVATI0tt OF OPERATICIIAL SUPPORT CENTER

]

EPIP.3.04 014 03/10/92 03/21/92 ACTIVATICII Cr LOCAL EDWIRGENCY OPERATIONS PACILITY

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-EPIP 4.01 015 02/02/95 02/08/95 RADIO!& 4 CAL ASSESSDWFf DIRECTOR CONTROLLING PROCEDURE EPIP.4.02 011 05/02/96 05/10/98 RADIATICII PIIDIECTIDW SUPERVISOR COIFFROLLIIIQ PROCEDURE

'EPIP+4.03 011 12/20/93 01/01/94 DOSE A388888SNT TEAM ColffROLLING PROCEDUIW WIP-4.04 009 11/21/94 11/28/94 EDSRGERICY PER80lulEL RADIATICII EXPO 8URE EPIP.4.05 000 12/20/93 01/01/94 RE8PIRA2ORY PICTECTION AND EI ASSR88 MERIT EPIP-4.06.

009 12/21/95 12/28/95 PER8010lEL MOIIITORING AND DECOIrrRMINAT100f EPIP.4.01 013 02/02/95 92/08/95 PRDTECTIVE MEASURE 8 EPIP-4.00-012 07/21/95 07/21/95 INITIAL OFF81TE RELEASE ASSESSMENT EPIP-4.09 011 07/21/95 07/21/95 SOURCE TEltt A88E88MEIrr D 17 4.10 009 04/07/97 04/11/97 DETEleGNATICII CF X/Q EPIP-4.13 008 12/20/93 01/01/94 OFF8ITE RELEA8E A38588MEIIT WITH ENVIROINENTAL DATA

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30stIW AINE POWER 59AT105 0

LIST OF WAPS BIERNMCY PLAN IMIm merATION Pm0CEDUR88 CNBCK DMIS POR IAtte? DocisWrt INFOIDETION f

APrlpFAL EFFECT**

~DOCUIWrt WUNEER IWY ' * *DME* * - **DATE**

DOCLAWrt TITLE EPIP.4 14 =

007 12/20/93 01/01/94 INFIAart MONITtstING Eftt.4.15

' 009.12/20/93 01/01/94 ONSITE MONITORING EF17 4.16

~ 012

.12/20/93 01/01/94 0FFSITE MONI1CRING EF19 4.17 013=

04/21/97 04/2$/97 MONI10 RING OF EDERGEICY RESPONSE FACILITIES EPIP*4.10 -

010 04/21/97-04/25/97-MONITORING OF LEOF EP1P.4.21

- 000 12/20/93 01/01/94 EVACUATICII AND REMOTE ASSSIBLY AREA MONITORING EPIP.4.22 013 04/02/93 04/07/93 POST ACCIDEIrr SaferLING CF CONTAIINeart AIR Er17 4.23 013 03/13/96 03/10/96 POST ACCIDBart SAMPLING OF REACTOR C00LAart

- Er17 4.24 -

000 11/05/96 11/13/96 QASEQUS EFFLUEIrf SAMPLING DURING All EDERGENCY EPIP.4.2$

- 004 07/33/93-07/29/93 LIQUID EFFLUENT 5AMPLING DURING AN DIERENCY Er17 4.26 -

010 11/05/96 11/13/96 BIGH LEVEL ACTIVITY 5 AMPLE ANALYSIS EPIP.4.28.

007 01/09/97 01/14/97 Tec/LEOF RADIATION MONITORING SYSTEM

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EPIP.4.30 003 06/20/94 06/21/94 USE or MIDAS CLASS A SCDEL

. EP'

. 31 ~

003 06/30/94 06/21/94 USE OF MIDA8 CLASS E MODEL EPIP.4.33-001 12/20/93 01/01/94 WEALTE PHY8IC8 NE1 WORK C0001UNICATIONS

' EPIP 4.34 001 12/20/93' 01/01/94 FIEIO TEAM SADIO OPERAIOR INSTRUCTIONS C

IFIP.S.01-

. 011 12/11/96 12/17/96..

TRANSPOItTATION OF CONTAMINA2TD INJURED PEmacInIEL D17 5.03 019 12/09/97 12/11/97 PERSONNEL ACCOUlrrABILITY EPIP.S.04 006

.06/27/95 06/27/95 ACCES8 CollTROL EPIP.S.CS 013 06/25/96 07/02/96 BITE EVACUATION EPIP-S.07 009 04/21/97 04/2$/97 ADMINISTIUgTION or RADIOPROTECTIVE DRUG 8 EPIP.S.00 005 12/20/93 01/01/94 DAMAGE WIrrROL GUIDELINE EFIP.S.09 002 02/02/95 02/04/95-SECURITY TEAM LEADER ColrFIIOLLING PROCEDURE i%-

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PAG 88 3 e

208011 ANan Pawth #1173 cal LIST CP RAPS D m GrX Y FLAN !stkapsFTAT! cal PMcCEDUrts 8

CHECK t*18 POR % 7Erf DOCUMalt? INFOMMATION e

AFPMDVAL trrtCT" DocVMtEtEUMath Rint

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"DATE" DoctMRIr? TITLE EPIP.4.01 006 04#16/93 03/21/93 REakNTRY/MacevtRY OUIDrLINE b

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VIRGINIA POWER s

NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE rN

(

)

NUMBER PROCEDURE TITLE REVISION EPIP 1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 30 (With 3 Attachments) 1 of 6 PURPOSE To assess potential emergency conditions and initiate corrective actions.

LEVE.'2 CONTROLLED DSIRBUT0N ENTRY CONDITIONS l

Any Of the following:

,o 1.

Ar.other station procedure directs initiation of this procedure,

')

2.

A potential emergency Condition is reported to the Shift Supervisor.

APPROVAL RECOMMENDED SNSOC APPROVAL APPROVAL EFFECTIVE g

DATE CA DATE v e, s7 s4,, sma

< b CHAIRMAN SNSOC STATION MANAGER

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NUMBER PROCEDURE TITLE REVISION EPlP 1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 30 PAGE 2 of 6 ACTION / EXPECTED RESPONSE STEP RESPONSE NOT OBTAINED CAUTION:

Declaration of the highest emergency class for which an Emergency Action level is exceeded shall be made.

D n'il i EQII:

The ERFCS is potentially unreliable insthe= event of an earthquake.

Therefore, ERFCS parameters:sbould-be; evaluated lfohl accuracy should e i:. ! U

'o l-thiS Lituation occur.

, p,

, a ti 1

MAKE INITIAL ASSESSMENT:

a) Determine event category using EPIP 1.01, Attachment 1.

EMERGENCY ACTION LEVEL TABLE I

INDEX b) Review EAL Tab associated with event categor;.

c) Use Control Room monitors.

ERFCS. ano outside reports to get indications of ecergency conditions listec in the EAL Table d) verify EAL EX:EEDEC d) 11 EAL NOT exceeded, THEN RETURN T0 procedure in effect.

e) Record procecu e ir**':*

r By:

Date:

Time:

f) Initiate a ch*0nological log of events l

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4 _

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NUMBER PROCEDURE TITLE REVISION EP!P 1.01 EMERC ICY MANAGER CONTROLLING PROCEDURE 30 PAGE-3 of 6

)

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED fAUTION:

Continue througn-this and all further instructions unless otherwise directed to hold.

L 2 4NITIATE SUPPORTING PROCEDURES:

a) Dirc.t Emergency Communicators tr initiate the following rcocedures:

1) EP!P 2.01. NOTIFICATION OF STATE AND LOCAL GOVERNMENTS

2) EPlP 2.02. NOTIFICATION OF NRC b) Direct HP to initiate EPIP 4.01. RADIOLOGIC AL

[

ASSESSMENT DIRECTOR CONTROLLING PROCEDURE c) Establish communications with Scurity Shif t Supervisor:

1) Provide Setsrity v,it-current errergency classification

2) Direct Se:urity te mitiate EPIP-5.09. SECURITY TEAM LEADER C0t;iR0tt!!iG DD0;EDURE

NUMBER PROCEDURE TITLE REVISION EPIP 1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 30 4 of 6 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 OETERMINE STATUS OF TSC AND LEOF ACTIVATION:

a) Check TSC ACTIVATED a) 11 TSC NOT activated. IH{3 do the following:

1) Have STA report to the Control Room.

2) Notify Superintendeilt Operations or Operations Manager On Call.

3) Verify HP has initiated EPlP 4.01. RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE AND Consider having Radiological Assessment Director report to the Control Room.

4) WHEN relief SEM arrives.

THEN perform turnover using EPIP 1.01. Attachment 3.

Turnover Checklist. as time permits.

5) GO TO Step 4 b) Cnect LEOF - A:'!VATE:

b) 11 LEOF NOT activated, THEN GO TO Step 4

) Announce transfer o' ;r-s c from TSC to LEO

k

4 NUMBER PROCEDURE TITLE REVISION EPIP 1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 30 PAGE 5 of 6

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 4

!MPLEMENT EPIPs FOR EMERGENCY

^

CLAS$1FICAT10N IN EFFECT:

Notification of Unusual Event -

e GO TO EPIP 1.02, RESPONSE TO NOTIFICATION OF UNUSUAL EVENT Alert -

e GO TO EP!P 1.03, RESPONSE TO ALERT Site Area Emergency -

e I

GO TO EPIP 1.04. RESPONSE TO SITE AREA EMERGENCY General Emergency -

e GO TO EPIP 1.05, RESPONSE TO

-~

j GENERAL EMERGENCY 5 NOTIFY OFFSITE AUTHORITIES OF EMERGENCY TERMINATION:

a) State and local governments b) NRC l

O

NUMBER PROCEDURE TITLE REVISION EPIP 1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 30 PAGE 6 of 6 ACTION / EXPECTED RESPONSE REf>0NSE NOT OBTAINED STEP 6 TERMINATE EMERGENCY:

a) Make announcement to station personnel that addresses the following; Emergency termination e

Facility de activation

. Selective release of personnel Completion and collection of procedures

. Recovery b) Check if implementation of b) GO TO Step 7.

l I

re entry / recovery procedure -

REQUIRED c) Initiate Efl0 6.01.

RE ENTRY /RELOVERY GU*DE.!f.E 7

TERMINATE EPIP '. 01:

l Give completec !?!P;.

ent i

e otner applicab;e re: crc:

Nuclear Emerger.:, prece-(: e:-

(TSC Emergency arc;'c,*e-Coordinator if

e

-., '. e

Completed By:

Date:

Time:

El1U -

I k

i I

NUMBER ATTACHMENT TITLE REVISION i

EPIP 1.01 EMERGENCY ACTION LEVEL TABLE 30 ATTACHMINT PAGE

'1 4

-,e, CAUTION:. Declaration of the hichest emergency class for which an EAL is exceeded shall be made.

Emergency Action Levels shall be conservatively classified based on actual or anticipated plant conditions.

EVENT CATFG,QRY:

TA) 1.

Safety. Shutdown, or Assessnent System Event......................A 2.

Reactor Coolant system Event......................................B 3.

Fuel Failure or Fuel Handling Accident............................C 4

Containment Event..................................................D 5.

Racioactivity Event...............................................E l

6.

DILETED 1

7, L o s s o f S e c o n d a ry C o o l a n t............ *,..........................., G 8.

Electrical Failure...............................................H 5,

t ire......

.............,,..............,,,,,,...............,,,..]

10, Security Event.............,.....................................,J l',

Hazaro to Station 00eratic*,......................................K

-12, flotural Events.............

.....................................,(

13, Miscellaneous Abnormal Eve**,;,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,M

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HUMBER ATTACHMENT TITLE REVISION I

EPIP 1.01 EMERGENCY ACTION LEVEL TABLE 30 ATTACHMENT (TAB A)

O SAFETY, SHUTDOWN, OR AS1ESSMENT PAGE

• 1 SYSTEM EVENT

? of 4?

CONDITION / APPL]CABILITY

]NDICATION CLASSIF] CAT]ON CAUTION:

EAL C.2 is duplicated below for,;ross reference / comparison to EAL A.1; C.2.

Probable large Loss of Main Feedwater GENERAL radioactivity System, Condensate System EMERGENCY release initiated and Auxiliary feedwater by loss of heat System sink leading to core degradation MODES 1. 2. 3 & 4 1.

Loss of function Total loss of the SITE AREA needeo for unit HSD Charging /51 System EMERGENCY concition MODES 1. 2. 3 & 4 l

Total loss of the Main l

Feedwater and Auxiliary Faeonater systems I.

Failure of the

eactor trip setpoint and SITE AREA Reactor Protection tointiaences EXCEEDED EMERGENCY System to initiate en

comclete a AHL recuireo trip wn11e at Dower A,tomati: trip from RPS -

Tal.!D MODE 5 1 & 2 C

se' teac from Control

e

cP IAlLED O

t

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NUMBER ATTACHMENT TITLE REVIS10N' EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 30 l'

ATTACHHENT

^

SAFETY, SHUTO WN OR ASSES! MENT 1

SYSTEM EVENT 3 of a?

CONDITION / APPLICABILITY INDICATION CLASS!rlCATICN Most (>75%) or all SITE AREA 3.

Inability to monitor a significant annunciator alarms on EMERGENCY transient in panels "A*

to *K' NOT progress AV AI L/.B L E MODES 1. 2. 3 & 4 AND All computer monitoring capability (e.g., plant computer. ERFCS)

NOT AVAILABLE AND Significant transient IN PROGRESS (e.g., reactor trip. 51 actuation, turbine runDack >25% thermal reactor poner, thermal power oscillations >10%)

AND Inability to oirectly I

I monitor any one of the following using Control Room inoications:

Subtriticality Core Cooling Heat Sink Vesse' integrity Containment integrity 4

Evacuation of Mei-i e;,etior of the Control Room SITE AREA Cortrol Room witr v.

' i::e; shutoown control not EMERGENCY

ontrol not e;;e:'isnec within 15 minutes establisheo withir 15 minutes ALL MODES

,pebCA

e NUMBER ATTACHMENT TITLE REVISION EPIP 1.01 EMERGENCY ACTION LEVEL TABLE 30 O

,ATTAC W NT

'^

SAFETY, SH WN. OR ASSESSMENT 1

SYSTEM EVENT 4 of 42 Im CONDITION / APPLICABILITY INDICATION CLAS$1rtCAT10N 5.

Total loss of Secondary system cooling ALERT function needed for capability UNAVAILABLE unit CSD condition MODES 5 & 6 Loss of any of the e

following systems:

Service Water e

Component Cocling e

RHR M

ACS temper TPAN 140 ature GREATER e

F 6.

Failure of the Reactor trip setpoint and ALERT e

Reactor Protection coincidences EXCEEDED System to complete a C

trip which takes the M

Reactor Suberitical Automatic trip from RPS -

e MODES 1 & 2 FAILED E

Manual trip REQUIRED e

E Manual trio from Control e

Room SUCCESSFUL

NUMBER ATTACHMENT TITLE REVIS!0N' EP!P 1.01 EMERGENCY ACTION LEVEL TABLE 30 i

ATTACHMENT

^

SAFETY, SH W

OR ASSESSMENT 1

SYSTEM EVENT 4

CONDITION / APPLICABILITY INDICATION CLAS$1FICAT10N 7.

Unplanned loss of Unolanned loss of most ALERT safety system

(>75%) or all annunciator annunciators with alarms on panels "A" to *K*

compensatory for GREATER THAN 15 minutes indicators unavailable or a f.!iQ transient in All Computer monitoring progress capability (e.g., plant MODES 1, 2. 3 & 4 computer. ERFC5)

NOT AVAILABLE E

Significant transient -

INITIATED OR IN PROGRESS (e.g., reactor trip. 51, turDine runback > 25%

thermal reactor cower, thermal power oscillations

> 10%)

8.

Evacuation of Main Evacuation of the Control Room ALERT Control Room with shutcown Control recuired established within 15 minutes ALL MODES 9.

Inability to reacn Intentional reduction in NOTIFICATION recuirea mode witnin oower. load or temperature OF UNUSUAL tecnnical LAW T.S. Action Statement -

EVENT specification limits HAS COMMENCE 0 MODES 1. 2, 3 & 4 AND I.S. Action $tatement time limit for mode change -

CANNOT BE MET

NUMBER ATTACHMENT TITLE REVISION EPIP 1.01 EMERGENCY ACTION LEVEL TABLE 30 4

ATTACHMENT (TAB A)

' ' ' ^

PAGE SAFETY SHUTOOWN. OR ASSESSMENT 1

SYSTEM EVENT 4

6 of 42 CONDITION /APPllCABillTY INDICA 11gg

[11{j]flCAT10N

10. Failure of a safety 311 NOTIFICATION or relief valve to 0F-UNUSUAL 4

close after pressure RCS pressure LESS EVENT j

reduction, which may THAN 2000 psig i

Jffect the health 3

and safety of the-Da public I,

NOT Protection System -

l MODES 1, 2. 3. 4 & 5 IN SERVICE AND Any indication after e

lift or actuation that 4

Pressurizer Safety or PORV REMAINS OPEN A!!Q Flow UNIS0LABLE Main steam Excessive Steam e

Generator Safety. PORV or Decay Heat-Release flow as ir.dicated by rapid <CS cooldown rate AND Main Steam pressure greater than 100 psi celow setpoint of affected valve

!!. Uncienned loss of Unciannec loss of ?Sst NOTIFICATION most or ill safety

(>75%) or all annunciators 0F UNUSUAL' system annunciators en canels "A"

to "K" for EVENT for greater than 15 Go, TATER THAN 15 minutes minutes MODES 1. 2. 3 & 4 e

4 l

NUMBER ATTACHMENT TITLE REVIS10tl EPIP 1.01 EMERGENCY ACTION LEVEL TABLE 30 ATTACHMENT PAGE SAFETY, SHU N OR ASSESSMENT 1

SYSTEM EVENT 7 of 4?

CONDITION /AppllCABILITY INDICATION G AS$ 1 F IE AT 10N

12. Loss of Station PBX phone system -

NOTIFICATION communications FAILED OF UNUSUAL capability EVENT ALL MODES Station Gai tronics

+

system FAILED AND Station UHF radio 1 dem -

+

FAILED i

I e

l

WNSER ATTACHMENT TITLE REVISION EPIP 1.01-EMERGENCY ACTION LEVEL TABLE 30 ATTACHMENT (TA8 8)

REACTOR-COOLANT SYSTEM EVENT PAGE ummmmmmmmmmmmunum mem[nm&meMmmmmmm, CONDITION /APPLICABillTY INDICATION CLAtSIFICATION 1.

Loss of 2 of 3 Any two of a), b) or c) ev.ist GENERAL fission product and the third is imh.inent:

EMERGENCY barriers with potential loss of a)

Fuel clad integrity failure 4

3rd barrier as indicated by any of the I

following:

Att MODES RCS speci'fic activity e

greater than or equal i

to 300.0 pC1/ oram dose equivalent I 131 E

5 or more core exit thermocouples greater than 1200 'F Containment High Range Radiation Monitor RM RMS 165.

166 or RM RMS 265.

266

-GREATER THAN 1.8Sx102 R/hr D)

Loss of RCS integrity as incicatec Dy any of.the following:

RCS. pressure greater tnan 2735 psig L

M Loss of Reactor Coolant in progress

'oss o' containment ir.tegrity as indicated by any of the following:

Containment pressure greater than 60 psia anc not decreasing 3

n Release path to i

environment EXISTS

.1 NUMBER ATTACHMENT TITLE REVISION EP1F 1.01

!"ERGENCY ACTION LEVEL TABLE 30 ATTACHMENT li! ACTOR C N SYSTEM EVENT

.'^

1

,n,,,

CONDITION /APPllCABillTY INDl:ATION CLAS$1FICAT10N

?.

Fuel failure with Any two of a). b) or c) exist and the GENERAL steam generator inird is imminent:

EMERGENCY tube rupture g)

Fuel clad integrity f ailur? as Alt. MODES indicated by any of the followirig:

RCS specific activity greater than 300 pC. gram dose equivalent 1 131 E

5 or more core exi GREATER THAN 1200.t thermocouples F

M High Range Letdown radiation monitor 1 CH RI 128 or 2 CH RI '28 4

GREATER THAN S.9 x 104 mR/hr c)

Stea.s Generator tube rupture as indicated Dy both of the following:

5: coincidence SATISFIED AND Steam Gene ator tuDe rupture

!N DROGRESS

)

Loss of secondary integrity associatec with ruptured steam geaerator patnway as indicated by

e. c' ine following:

5teet Generator PORY OPEN E

Meir Steam Code Safety Valve OPEN E

Loss of secondary cooiant outside containment IN PROGRESS l

l

' NUMBER ATTACHMENT TITLE PEVISION EPIP 1.01 EMERGENCY ACTION LEVEL TABLE 30 REACTORC00fN

^ ^ ""

[

1. 0 SYSTEM EVENT

\\m /

1 in nr 42 CONDITION / APPLICABILITY JNDICATION CLA$$1rfCAT10N 3.

RCS leak rate e

Loss of Reactor Coolant in SITE AREA limit EXCEEDED progress and inventory EMERGENCY 1

balance indicates leakage MODES 1. 2. 3. & 4 GREATER THAN 300 gpm M

Pressurizer level cannot be maintained with two (2) or more Charging /S! pumps in operation 4

Gross primary to Steam Generator Tube SITE AREA e

secondar/ leakage Rupture IN PROGRESS EMERGENCY with loss of offsite power g

MODES 1. 2. 3. & 4 Safety injection REOUIRED AND Vent Vent A Kaman Monitor e

RM VG 179 GREATER IHAN 1.3 x 100 pCi/sec DE Steam Generator Blowdown monitor on affected pathway RM SS 122.

222 RM SS 123.

223 RM SS 124 224 GREATER THAN 1x106 com AND

+

A subsequent loss of offs 1te oower indicated by zero volts on voltmeters for 4160V buses D. E. & F

4 NUMBER ATTACHMENT TITLE REVISION' EPIP 1.01 EMERGENCY ACTION LEVEL TABLE 30

^ ^" "

REACTOR C N SYSTEM EVENT I^

1 11 of 4?

CONDITION / APPLICABILITY INDICATION CLASSir! CATION 5.

RCS leak rate limit Pressurizer level cannot be ALERT EXCEEDED maintained greater than 20%

with one (1) Charging /$1 MODES 1, 2. 3. & 4 pumo in operation M

RCS inventory balance indicates leakage greater than 50 gpm 6.

Gron primary to Steam Generator Tube Rupture ALERT secondary leakage IN PROGRESS MODES 1. 2. 3. & 4 E

Safety injection RE0 VIREO l

I I

i

NUMBER ATTACHMENT TITLE REVISION EPIP 1.01 EMERGENCY ACT:0N LEVEL TABLE 30

(

)

REACTORC00fN

^ ^"

^

SYSTEM EVENT 1

12 er at CONDITION / APPLICABILITY INDICATION CLAS$1FICAT10N 7.

Excessive primary to Intentional reduction in ALERT secondary leakage power. load or temperature with loss of offsite because the unit has power entered an. Action Statement or will exceed an LC0 MODES 1. 2. 3 & 4 AND Vent Vent A Kaman Monitor e

RM VG 179 GREATER THAN 1.83 x 106 pCi/sec 03 Steam Generator Blowdown monitor on effected pathaay RH SS 122.

222 RM SS 123.

223 9

RM SS 124 224 GREATER THAN 1x105 com b.U.D e

A subsecuent loss of offs 1 e power indicated by zero veits on voltmeters for 4160V buses D. E. & F I

l

NUMBER ATTACHMENT TITLE REVI S!0'N EPIP 1.01 EHERGENCY ACTION LEVEL TABLE 30 l

ATTACHMENT AGE REACTOR C00 N SYSTEM EVENT 1

13 of 4?

CONDITION /APPLICiBillTY INDICATION CLA$$]F] CATION 8.

RCS leek rate Intentional reduction in NOTIFICATION requiring plant power. load or temperature Ui UNUSUAL shutdown LAW T S.

Decause the unit has EVENT 3.4.6.2 or 3.4.6.3 entered an action statement or will exceed an LC0 M00E5 1. 2. 3. & 4 AND Unidentified RCS leakage -

greater then 1 gpm 23 Identified leakage -

greater than 10 gpm DA Controlled leakage to RCP Seals greater than 50 gpm Jtal S3 l

l A'ny pressure boundary leakage. EXISTS 9.

Drimary to Seconcary Intentional reduction in NOT!FICATION ieakage greater cower. loac or temperature OF UNUSUAL

nan 1 gpm ce:euse tne unit has EVENT ertece: an action statement MODES 1. 2. 3. & 2 o* will ex:eed an LCO LE ae.s :: Se:onaary tea.. age greater than 1 gpm DE

? li monitor indicates oatmacy to secondary

.ee age creater than T. 5.

aoaa 1e limits l

I

NUMBER ATTACHMENT TITLE REVISION EPIP 1.01 EMERGENCY ACTION LEVEL TABLE 30 ATTE HMENT (TAB C)

(

FUEL FA! LURE OR FUEL HANDLING ACCIDENT PAGE 14 e< 42 l

CONDITION / APPLICABILITY INDICATION CLASSir] CAT 10N 1.

Probable large Loss of reactor coolant in GENERAL radioactivity progress EMERGENCY release initiated by LOCA with ECCS A.N3 failure leading to core degradation RCS specific activity

• greater than 300 pC1/ gram ALL MODES dose eavivalent 1 131 23 Containment High Range Radiation Monitor RM RMS 165, 166 or RM RMS 265.

266 GREATER THAN 1.BBx102 R/hr AND C

High or low head ECCS flow not being delivered to the core (if expected by plant conditions)

C AL'?!0N :

IAL A.1 is cuell:! e: celow for cross reference / Comparison to EAL C.2:

A.1, Loss of fun:: 1 o r.

70 a1 loss of the SITE AREA neeced for uni:

nerging/S! System EMERGENCY HSD conc 1:1or MODES 1, 2, 3 & 4

'::al loss of the Main tet:na*er and Auxiliary Seeoneter systems 2.

PrcDadle large L:s: c' Main Feeawater System.

GENERAL recica::ivity 0:rceasate System and Auxiliary EMERGENCY release initiatec oy

'ee:na:er System loss of heat sink leading to core degradation MODES 1.~2. 3 & 4

ATTACHMENT TITLE REVISION' NUMBER EPIP 1.01 EMERGENCY ACTION LEVEL TABLE 30 l

ATTACHMENT FUEL FAILURE O E HANDLING ACCIDENT f^

g 15 of 42 CONDITION / APPLICABILITY INDICATION CLAS$!FICATION 3.

Probable large Rx nuclear power after a GENERAL radioactivity trip greater than St EMERGENCY release initiated by failure of 3,9 protection system to bring Rx subtritical RCS pressure greater than and Cavsing core or equal to 2485 psig degradation ALL MODES Containment pressure and temperature rapidly increasing 4

Probable large Loss of all onsite and GENERAL raoloactivity offsite AC power EMERGENCY release iniciateo by loss of AC power and AND all feeowater Turbine Driven Auxiliary ALL MODES Feedwater Pump not operable

(

)

AND Restoration of either of the above not likely within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> i

I

i NUMBER

' ATTACHMENT TITLE-REVISION

[

EPIP 1.01 EMERGENCY ACTION LEVEL TABLE 30

~

ATTACHMENT (TAB C) p4gg FUEL-FAILURE OR FUEL HANDLING ACCIDENT f

1 i

] A nf p CONDITION / APPLICABILITY INDICATION CLA$$1FICAT10N 5.

Probable large Loss of reactor coolant in GENERAL radioactivity progress EMERGENCY-release initiated-by-LOCA with loss of g

ECCS and containment cooling High or low head ECCS flow not being delivered to the ALL MODES core (if expected by plant conditions)

M Containment R3 sump e

temperature greater than 1900F anG NOT decreasing ER All Ouench Spray-and Recirculation Spray systems

• NOT OPERABLE

.O v

4 t

P G

O k

,,,,....,.w.y__

,,,,,_.mm._

.,,,,,,_..,.r.

.._,,,.mm.,,.

._,_..my.m.,w,_.mnw.my.

s-NUMBER ATTACHMENT TITLE REV!Sf0N EPIP.I.01 EMERGENCY ACTION LEVEL TABLE 30 TfE(}HANDLINGACCIDENT ATTACHMENT

^

FUEL FAILURE O 1? e< 42 CON 0tTION/APPLICABl(lli INDICATION

((A531FICAT10N 6.

Core damage with a)

Fuel clad failure as SITE AREA possible loss of indicated by any of the EMERGENCY coolable geometry following:

MODES 1. 2. 3. & 4 RCS Specific activity greater t:an 60 pC1/ gram do.e equivalent 1 131 LE High Range Letdown radiation monitor 1 CH Rl 128 or 2 CH Rl 228 GREATER THAN 1.2x104 mR/hr AND b)

Loss of cooling as

(

)

19dicated by any of the following:

5 confirmed core exit thermocouples greater than 1200

• F OR Core celta T zero DE Core delta T rapidly aiverging I

NUMBER ATTACHMENT TITLE REVISION EPIP 1.01 EMERGENCY ACTION LEVEL TABLE 30 ATTACHMENT

^

( '-)

FUEL FAILURE OR UEL HANDLING ACCIDENT s_-

1 19 of 4?

CONDITION / APPLICABILITY INDICATION CLASSIFICATION 7.

Major fuel damage Water level in Rx vessel

$1TE AREA accident with during refueling below the EMERGENCY

-adioactivity top of core rs ease to containment or fuel EE buildings Water leve'e in spent fuel ALL MODES pool below top of spent fuel AND Verified damage to irradiated fuel resulting in readings on Vent Vent "B" Kaman monitor RM VG 180 GREATER THAN 2.74 x 100 pCi/sec 9

S.

Severe fuel Clad High Range letdown ALERT Darage raciation monitor MODES 1. 2. 3. & 4 1 CH RI 128 or 2 CH RI 228 increases to GREATER THAN Hi Hi Alarm setpoint within 30 minutes anc remains for at least 15 minutes e

4 NUMBER ATTACHMENT TITLE REVISIO$

EPIP 1.01 EMERGENCY ACTION LEVEL TABLE 30 l

ATTACHMENT

^

FUEL FAILURE O E HANDLING ACCIDENT to e' 42 CONDITION /APPLICABillTY INDICA 7 jay CLASSIFICATION 9.

Fuel damage accident Verified accident involving ALERT with relta$e of damage to irradiated fuel radioact1vity to containment or fuel ARQ Du11 dings Health Physics Confirms e

ALL MODES fission product release from fuel E

vent Vent '8" Kamen monitor 1.b3x10 E

AN pC1 /sec 10, Potential for fuel Continuing uncontrolled ALERT oamace to occur oecrease of water level in ouring refueling Reactor R f ling Cavity or Spent Fue 01 l

l

11. Fuel clac damage 1ntentional reduction in NOTIFICATION ino1 ation Dower, load or temoerature OF UNUSUAL LAW r EVENT activ$ actor Coolantity T.S. Action MODES 1. 2. 3. & 4 Statement

• HAS COMMENCE 0 E

High Range Letdown roo18 tion monitor 1:R:i:lli '

!ncreases to GREATER iMAN M3 Alarm setpoint w tnic 30 mnutes and tmains for at least

c'nutes

NUMBER ATTACHNENT TITLE REVISION i

EPIP 1.01 EMERGENCY ACTION LEVEL TABLE 30

. ATTACH NT

1. 0 FUEL FAILURE OR E HANDLING ACCIDENT

,mmmmmmmmmmmmmme

- amm Ma d Almasses, i

CONDITION / APPLICABILITY INDICATION CLAS$1FICAT10N i.

l

12. g p ndent Spent erified g 1 g g face N TIFl ATION e

1 k

kVEh

($$f$ )!NN e!ON event 2-ALL MODES

' Sealed urface Storage CC5k ($ SC mishand ec) dropped or G

j O

O

I

_.__s_-.,

., fl NUMBER ATTACHMENT '.'ITLE REVISION EPID 1.01 EMERGENLY ACTION LEVEL TABLE 30 9

.^ # "" "

CONTAI N EVENT PAGE 1

t

?! M 4?

CONDITION / APPLICABILITY INDICATION CLASSIFICATION 1.

Extremely high Containment High Range GENERAL

=

containment radiation monitor EMERGENCY radiation, pressure and temperdture RM RMS 165.

166 or RM RMS 265.

266 MODES 1, 2, 3, & 4 GREATER THAN 3.76 x 102 R/t.r AND Containment pressure greater than 45 psia and not decreasing E

Contair. ment temDU ture greater than 2800F 2.

High high Containment High Range SITE AREA 6>

conte nment radiation monitor EMERGENCY redi 2 ion, pressure, anc temocrature RM-RMS 165. -166 or RM RMS-265.

266 MODES 1. 2, 3 & 4 GREATER THAN 1.88 x 102 R/hr AND Containment pressure -

g' cater nan 27.75 ps.a and ro; cecreasing

?.'

• ontainment temoerature -

eater tnan 200 *F 1

0

- m - um amu m seum

1 1

NUMBER ATTACHMENT TITLE REVISION' EPIP 1.01 EMERGENCY ACTION LEVEL TABLE 30 ATTACHMENT CONTA N EVENT f^

?

1

?? 04 42 i

CONDITION / APPLICABILITY

_ INDICATION CLAS$1FICATION 3.

High Containment Cont-linment High Range ALERT radiation, pressure radiation monitor and temperature RM RMS 165, 166 or I MODES 1, 2, 3, & 4 RM RMS 265, -266 GREATER THAN 81.5 R/hr AND Containment pressure

=

greater than 17 psia DE.

Contai ment temperature -

greater than 1500F l

I t

I

NUMBER ATTACHMENT TITLE REVISION EP!r 1.01 EMERGENCY ACTION LEVEL TABLE.

30 b

.^"# "" "

b RADIO V TY EVENT 1

I

?3 of 42 CONDITION / APPLICABILITY INDICATION CLASSIFICATION 1.

Release imminent or HP assessment indicates GENERAL in progress and site actual or projected doses EMERGENCY boundary dose:

at or beyond site boundary projected to exceed greater then 1.0 Rem TEDE 1.0 Rem TEDE or 5.0 or 5.0 C-m Thyroid CDE s

Ren Thyroid CDE L

ALL MODES l

Release imminent or HP assessment indicates SITE AREA

-in progress and site actual or projected dose at EMERGENCY.

houndary doses or beyond Site Boundary projected to exceed exceeds 0.1 Rem TEDE or 0.5 0.1 Rem TEDE or 0.5 Rem Thyroid CDE Rem Thyroid COE ALL MODES t

i v

w

NUMBER ATTACHMENT TITLE REVISION EPIP 1.01 EMERGENCY ACTION LEVEL TABLE 30 ll ATTACHMENT (TAB E)

~

PAGE RADI0 ACTIVITY EVENT 1

2a of a?

CONCITION/APPllCABILITI INDICATION CLAS$1FICATION 3.

Effluent release a) Any of the following ALERT greater than 10 moniters indicate valid times 00CM allowable readings above the limit specified velues for greater than 15 minutes ALL MODES Clarifier Effluent RM LW lll GREATER THAN 4.8x105 cpm Discharge Canal 4M 5W 130 or 230 GREATER THAN 5 x 104 com Vent Vent A Kaman RM VG 179 GREATER THAN 1.83x106 pCi/sec I

I

. Ven: Vent B Kaman Ru-VG 180 GREATEF.,THAN

.33x100 pCi/se

D Ocess Vent Kaman RM GW 173 G:EATEE THAN

.E x 107 pCi/sec 21 essessment (sample "esults or dose

cjections) indicate

eate inan 10 times ODEM allowaole limit I

I 1

1

NUfiBER ATiACHMENT TITLE REVISION

-EPIP 1.01 EMERGENCY ACTION LEVEL TABli 30 ATTACHMENT (TAB E)

RADI0 ACTIVITY EVENT PAGE u_ nr 4c M DITION/ APPLICABILITY INDICATI0A CLASSIFICATION 4

High radiation or Valid readings on any of the ALERT 6irborne following monitors have contamination levels increased by a factor of 1000 indicate a severe and remain for at least 15 degradation i'.

minutes:

control of radioactive material Ventilation Vent Multi-sample gaseous or ALL MODES.

particulate monitor RM-VG 106 or 105 {

Control Room Area RMS-157 Aux. tag. Control Area RMS-154 Decon. Bldg. Area RMS 151, I

l Fuel Pool Bridge Area

=

DRS 153 h ev. fuel storage Area jDMS152

.3::*atory Area

{?'*1155 Setoie Roo.T. Area

( DM5 156 9

NUMBER ATTACHMENT TITLE REVIS10k EPIP 1.01 EMERGENCY ACTION LEVEL TABLE 30 l

ATTACHMENT

^

RADIO V TY EVENT I

2A of n i

CONDITION / APPLICABILITY INDICATION CLASSIFICATION 5.

Effluent release a) Any of the follcwing NOTIFICATION greater than ODCM monitors indicate valid 0F UNUSUAL allowable limit readings.above the I 'ENT 4

specified value for more ALL MODES than 1 hour:

. Clari<ier Effluent lRMLW111 lGREATERTHAN4.8x104 com

. Discharge Canal RM SW 130 or 230 GREATER THAN 5 x 103 com Vent Vent A Kaman RM VG-179 GREATER THAN 1.83x105 pCi/sec

{

. Vent Vent B Kaman RM VG 180 GREATER.THAN 1.S3x103 pCi/sec Process vent Kaman

! $[:6W;178 p : A i : *. IHAN, l :,0 x 100,ati / se c

.03 c)

Ho essessment (sample results or cose projections) indicates creater than ODCM allowable limit

.- NUMBER

. ATTACHMENT TITLE REVISION EPIP 1.01 EMERGENCY ACTION LEVEL TABLE 30 ATTACHMENT-

'^

LOSS OF 0 ARY C00LAt!T 9-1

?7 of 4?

CONDITION / APPLICABILITY INDICATION CL ASS 1FICt TION 1.

Major secondary Conditions a) and b) exist SITE AREA line break with with c):

EMERGENCY significant primary to secondary a) Uncontrolled loss of secondary leakage and fuel coolant - IN PROGRESS camage indicated AND MODES 1, 2. 3. & 4 b)

RCS specific activity exceeds limits of T.S. Figure 3.4 1 (See Attachment 2)

E High Range Letdown radiation monitor 1 CH RI 128 or 2-CH kt-228 GREATER THAN Hi Alarm setpoint AND

~

c)

Vent Vent A Kaman Monitor RM VG 179 GREATER THAN 6.45 x 107 pCi/ set M

Steam Generator Blowdown monitor an affecteo patnway Re SS 122.

123. -124 D* 55 222.

223.

224 G:!ATEc THAN 1 x 106 com 2

Mata Steam Line High Range monitor or a'fectec patnway P" MS 170.

171.

172 R* M5 270. -271.

272 GREATER THAN 12.2 mR/hr

'g

NUMBER ATTACHMENT TITLE REV!S 80N' EPIP 1.01 EMERGENCY ACTION LEVEL TABLE 30 ATTACHMENT

^

LOSS OF SE O DARY COOLANT 29 of 4?

CONDITION /APPllCABillTY INDICATION CLAS$1FICAT10N 2.

Major secondary line Uncontrolled loss of ALERT break with setendary coolant - IN significant primary PROGR'55 to secondary leakage M.Q MODES 1. 2, 3. & 4 Vent Vent A Kaman Monitor RM VG 179 GREATER THAN 1.83 x 106 pCi/sec 23 Steam Generator Blowdown monitor on affected pathway RM-55 122.

-222 RM 55 123.

223 RM 55 124 224 GREATER THAN 1x105 cpm DS i

Main Steam Line High Range monitor on affected pathway RM MS 170.

270 RM-MS 171.

271 RM-MS 172.

-272 GREATER THAN 0.14 mR/hr

?

3.

Major seconcary line un:en: oiled loss of secondary NOTIFICATION oreak c: clan; - IN PROGRESS OF UNU5dAL MODES 1. 2, 3. & 4 EVENT i

g

NUMBER ATTACHMENT TITLE REV1SION EP!P 1.01 EMERGENCY ACTION LEVEL TABLE 30

(

Ak" "

^

A ELECT L ALLURE

?9 of 42 CONDITION /APPLICABillTY I NDI C ATI0j,l CLASSIFICATION 1.

Loss of-offsite and The following conditions exist SITE AREA onsite AC power for for greater than 15 minutes:

EMERGENCY more than 15 minutes Ammeters for 4160V Reserve e

ALL MODES Station Service Buses D, E.

& F all indicate - zero (0) amps M

Ammeters for 4160V Station e

Service Buses A. B. & C all indicate zero (0) amps M

Ammeters for 4160V e

Emergency Buses H &~J both indicate zero (0) amps 2.

Loss of-all onsite The following conditions exist SITE AREA Q

DC power for greater for greater than 15 minutes:

EMERGENCY

. V than'15 minutes

.All station DAttery ALL MODES voltmeters indicate zero (0) volts M

No light indication e

available # o Reserve Station Service creakers 15D1, 15El and 15F1 b

f'V 1

NUVBER ATTACHMENT TITLE REVISIDA EPIP 1.01 EMERGENCY ACTION LEVEL TABLE 30 ATTACHMENT

^

ELECTR C L FAILURE 1

10 2.f.4?

4 1

CONDITION /APDllCABillTY INDICATION CLASSIFICATION CAUTION:

EAL A.1 it duplicated below for cross reference / comparison to EAL H.3:

A.1.

Loss of function Total loss of the SITE AREA needed for unit Charging /S! System EMERGENCY HSD condition MODES 1. 2. 3 & 4 Total loss of the Main Feedwater and Auxiliary Feedwater Sjstems 3.

Loss of all offsite Ammeters for 4160V Reserve ALERT and onsite AC power Station Service Buses 0. E.

& F all indicate - zero (0)

ALL MODES amps AND Ammeter! ror 4160V tation Servi ie Buses A. B. & C all indicate zero (0) amps AND Ammeters for 4160V Emergen:y Buses H and J Dotn indicate zero (0) amos 4

L:ss of all onsite Al' station oattery ALERT C: power vcltmeters indicate - zero

(:, vcitt AL. MODES 2

AND He lignt indication availaDie to Reserve Station Service Breakers 1501, 15El and 15F1 l

I

NUMBER ATTACHMENT TITLE REVISION EPIP 1.01 EMERGENCY ACTION LEVEL TABLE 30

^

ELECTb L

^

AILURE 11 of 42 CONDITION / APPLICABILITY INDICATION CLASSIFICATION 5.

Loss of offsite Unit main generator and NOTIFICATION power or both emergency diesel 0F UNUSUAL onsite AC power generators out of bervice EVENT capability g

ALL MODES Loss of all 34.5 KV reserve station service buses U

i G

d

NUMBER ATTACHf;ENT TITLE REVISION EP!P 1.01 EMERGENCY ACTION LEVEL TABLE 30

/

ATTACHMENT (TAB I)

~ ~ ~

FIRE pAgg 32 of 42 CONDITION / APPLICABILITY INDICATIQN.

CLASSIFICA'!ON 1.

Fire resulting in Fire w h i c'.1 causes major SITE AREA degradation of degradation of a safety EMERGENCY safety sJstems system function required for protection of the MODES 1, 2, 3. & 4 public AND Affected systems 3re caused to be NOT operable as definto Dy Tech, Specs, 2.

Fire potentially Fire which has potential for ALERT affecting station causing a s:fe*y system not to safety systems e operable as defined by Tech, w

i I

. secs.

MODES 1. 2, 3, & 4

(N 3.

Fire lasting greater Fire within the Protected Arec

. NOTIFICATION s,,-

tnan 10 minutes in or Service Water Pump / Valve OF UNUSUAL Protected Area or house which is not under EVENT Service Water control within 10 minutes after Pump / Valve House Fire Brigdoe - DISPATCHED ALL MODES I

.g

-M

NUMBER ATTACHMENT TITLE RCVISION EPIP 1.01 EhERGENCY ACTION LEVEL TABLE 30 i

ATTACHMENT

^

i SECUR Y VENT 33 M 4?

l CONDITION / APPLICABILITY INDICATION CLASSIFICATION 1.

Lors of physical Shift Supervisor has been GENERAL 3

Station control informed that the security EMERGENCY force has been neutralized

-ALL MODES by attack.:resulting in loss of physical control of station E

Shift Supervisor has been informed of intrusion into one or more Vital Areas whict are occupied or controlled by an aggressor 2.

Imninent loss of Security shift Supervisor has SITE AREA physical Station notified the Operations shift EMERGENCY-control Supervisor of imminent intrusion into a Vital Area ALL MODES v

'3.

Ongoing Security Security Shift Supervisor has ALERT compromise notified the Operations Shift Supervisor of a confirmed ALL MODES nnneutralizec intrusion into

.e Protected Area 4

3ecurity threat.

~ Se:vrity Snif t Supervisor has NOTIFICATION unauthorized re:ommenoec tnat the Operations 0F UNUSUAL attempted entry. Or Sr.1't Supervisor declare a EVENT a

-attempted sabotage het 't:ation of Unusual Event

! A'. acclicable Sect rity ALL MODES

-ttagen:y Plan implementing P" :e ures e

l NUMBER ATTACHMENT TITLE REVISION EPIP 1.01 EMERGENCY ACTION LEVEL TABLE 30 I

ATTACHMENT (TAB K)

PAGE HAZARD TO STATION OPERATION

\\

1 34 of A-CONDITION / APPLICABILITY

_ INDICATION CLASSIFICATION 1.

Aircraft damage to Aircraft crash which affects SITE AREA vital plant systems vital structures by impact or EMERGENCY fire MODES 1. 2. 3. & 4 2.

Severe explosive Explosion which resui:s in SITE AREA damage severe degradation of any of EMERGENCY the following systems required MODES 1. 2. 3. & 4 for safe shutdown:

CVCS System DE ECCS System DB Main / Auxiliary Foeowater System V

3.

Entry of toxic or Orcontrolled release of SIT AREA flammable gases into toxic or flammable agents EME t:NCv Diant vital areas greater than life otner tnan the

!.nre3tening or explosive Concrol Room limits in Vital Areas MODES 1. 2, 3. & 4 M1D Evacuation of Vital Area

ner tnan Control Room -

REQUIRED 2

P Significant degradation of

Tant safety systems resulting in loss of a safety system function re:uirec for Drotection of

"e DuDIic

(.

NUMBER ATTACHMENT TITLE REVISION I

Ep!P 1.01 EMERGENCY ACTION LEVEL TABLE 30

"~'

Al iACHMENT (TAB K) 42ARD TO STATION OPERATION PAGE '

1 35 of a?

CONDITION / APPLICABILITY

]NDICATIQN CLASSIFICATION 4

Severe missile Missile impact causing severe SITE AREA camage to safety degradation of safety systems EMERGENCY systems required for unit shutdown MODES 1. 2. 3. & 4 5.

Aircraft crash on Aircraft crash within the ALERT the fdcility Protected Area or Switchyard 6.

Explosion damage to Unplan.Ted explosion resulting ALERT facility in damage to plant structure or equipment that affects plant ALL MODES operations 7.

Entry of toxic or Notification of uncontrolled ALERT I

I flammable gases or release of toxic or flammable licuics into plant agent which causes:

facility Evacuation of personnel ALL MODES from plant areas ANO t

Safety related equipment is renaered inoperable 8.

Turbine failure or Fa iure of turbine / generator ALERT missile impact reteting ecuipment resulting in

a: n:~ cenetration MODES 1 & 2 9

=

NUMBER

' ATTACHMENT TITLE REVISION EPIP 1.01 EMERGENLY ACTION LEVEL TABLE 30

-[

ATTACHMENT

'^

HAZARD T A ON OPERATION 36 of-42 CONDITION / APPLICABILITY INDICATION CLASSIFICATION 1.

Missile damage to-Notification of missile impact ALERT safety related tausing damage to safety equipment or related equipment or structures

-structures MODES 1. 2, 3. & 4

10. A,rcraft crash or Confirmed notification of NOTIFICATION unusual aircraft aircraft crash within the OF UNUSUAL activity

. tite boundary EVENT ALL MODES Da Unusual aircraf t activity in the vicinity of the site as determined by the Operations Shift Supervisor or the Security Shift Supervisor rs

11. Train derailment Confirmed report of train NOTIFICATION l.

witnin Protected derailment within-Protected 0F UNUSUAL Area Area EVENT AL'. MODES

'2. Exolosien within Confirmed report of unplanned NOTIFICATION Protected Area ex0losion within. Protected 0F UNUSUAL A*et AL; MODES EVENT i

13.-Onsite or nearsite he: #: cation of unplanned NOTIFICATION release of toxic or release of toxic or flammable OF UNUSUAL flammaDie liquids or agec : wnicn may affect safety EVENT gases o' station Dersonnel or ecu otent AL; MODES e

m m

NUMBER ATTACHMENT TITLE REVISION EPIP 1.01 EMERGENCY ACTION LEVEL TABLE 30

^ ^ "" "

^

HAZARD TO 5 A 10N OPERATION 1

37 nf 42 fj_NJ.[, TION / A PPll C A B ill TY INDICATION CLASSIFICATION N

14. Turbine rotating Failure of turbine / generator NOTIFICATION component failure rotating equipment resulting in OF UNUSUAL with no casing immediate unit shutdown EVENT penetration MODES 1 & 2 l

NUMBER ATTACHMENT TITLE l

REVISION EPIP 1.01 _

EMERGENCY ACTION LEVEL TABLE 30

/7 A

Q

. TTACHi4ENT (TAB L)

NATURAL EVENTS pAgg 39 of 42 CnNDITION/APPLICABillTY INDICATION CLASSIFICATION 1.

Earthquaie greater Confirmed earthquake which SITE AREA than or equal to DBE aciivates the Event Alarm EMERGENCY levels on the Strong Motion Accelerograph ALL MODES S

Alarms on the' Peak Shock Annunciator indicate a horizontal motion of greater than or equa' to 0.12 g or a vertical motion of greater than or equal to 0.08g t

2.

Extreme winds above Extreme winds confirmed which SI'i E ARE A Design Basis exceed UFSAR Section 3.3.1 EMERGENCY Conditions of 80 mph conditions (80 mph)

ALL MODES 3.

Flood or low water Flood in the Lake Anna SITE AREA level above design Reservoir with indicated EMERGENCY levels level - greater tnan 264 feet MSL ts i ' MODES

.QE Low watcr level in the Lake Anna Reservoir with indicated level less than 244 feet MSL V

O

ATTACHMENT TITLE REVI580N' NUMBER EPIP 1.01 EMERGENCY ACTION LEVEL TABLE 30 ATTACHMENT

^

fh NATURA EVENTS ll 30 of 4?

CONDITION / APPLICABILITY INDICATION CLAS$1FICATION 4

Earthauake greater Confirmed earthquake vhich ALERT than or equal to OBE activates Event Alarm on levels the Strong Motion ACCelerograph ALL MODES M

Alarms on the Peak Shock Ar.nunciator indicate a horizontal motion of greater than or equal to 0.06 g or a vertical motion of greater than or equal to 0.049 5.

Tornado striking Tornado visually detected AL.RT facility striking structures within the Protected Area or Switenyard l

I 6.

Hurricane force Confirmation by Virginia ALERT wincs projected Power Weather Center that onsite within 6 nurricane force winds ncu s (greater than 73 mph) a crcJected onsite within 6 AL. MODES nours 7.

Flood or low water Flooo in the Lake Anna ALERT level near design Rese*voir witn indicated levels leve' greater Inan 263 fee: "5L AL MODES 2:

. o r. water level in the Lake Anne Reservoir with incicated level less than 245 feet MSL i

)

i l

}

NUMBER ATTACHMENT TITLE REVISION

(

EPIP 1.01 EMERGENCY ACTION LEVEL TABLE 30 I\\.^

k

'#0 NATURA EVENTS

's /

1 40 of 4?

CONDITION /APPLICABillTY INDICATION CLAS$1FICAT10N

-i S.

Earthquake detected Confirmed earthquake which NOTIFICATION activates the Event Alarm on OF UNUSUAL ALL MODES the Strong Motion ACCelerogrCDh EVENT 9.

Tornado wi thin Tornado visually detected NOTIFICATION Protected Area or within Protected Area or OF UNUSUAL Switchyard Switchyard EVENT ALL MODES

.10, Hurricane force Confirmation by Virginia NOTIrICATION wines projected Power Weather Center that OF UNUSUAL onsite witnin 12 nurricane force winds EVENT hours (greater than 73 mph) projected onsite within 12 ALL MODEC hours

-g (s /

1'. 50 year flood or low Flood in the Lake Anna NOTIFICATION s

water level Reservoir with indicated 0F UNUSUAL level greater than 254 EVENT AL'. MODES feet MSL DE Low water level in the Lake Anna Reservoir with inc1Cated level less than 247 feet MSL

NUMBER ATTACHMENT TITLE REVISION EPIP 1.01 EMERGENCY ACTION LEVEL TABLE 30

/'~N ATTACHMENT (TAB M)

()

hlSCELLANEOUS ABNORMAL EVENTS PAGE 43 c< 4?

CONDITION / APPLICABILITY INDICATION CLAS$1FICATION 1.

Any major internal Shift Supervisor / Station GENERAL or external events.

Emergency Manager judgement EMERGENCY which singly or in combination cause massive damage to station facilities or mb rearrant evapur ion of the put tc AL'. MOSeb 2.

Station conditions Shi f t Supervisor /?'. ition SITE AREA wnicn may warrant Emergency Manager suogement EMERGENCY notification of the public near the site ALL MODES I ' f'N

\\s /

3.

Station conditions Shif t Supervitor/ Station ALERT wnicn nave the Emergency Manager judgement

-potential to degrace or are actually oegracing tne level ci safety of tne station ALL MODES k

a til'

~,

NUMBER ATTACHHENT TITLE R'EVI S ION' EPIP 1.01 EMERGENCY ACTION LEVEL TABLE 30 ATTACHMENT

^

I MISCELLANEOU BNORMAL EVENTS 4? of 42 CONDITION /APPLICABillTY INDICATION CLASSIFICATION 4

Station conditions Shift Supervisor judgement that NOTIFICATION which warrant any of the following exist:

OF UNUSUAL increased awareness EVENT of state and/or local authorities Unit shutdown is other than ALL MODES a controlled shutdown DE Unit is in an uncontrolled condition during operation 23 A condition exists which nas the potential for l

escalation and therefore i

warrants notification l

I f

9 NUMBER ATTACHMENT TITLE REVISION EP P 1.01 TECH SPEC FIGURE 3.4 1 30 O-

• ATTACHMENT PAGE

%.)

- 2 f

1 of 1

)

275 x,

i x

,,i i,.

, i i,i, ix

, iia

, i t iii

! i i i i '

i i

4...

i i (x,i i

,,i i i, i i ii, 250

, i

(

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. NUMBER ATTACHMENT TITLE REVISION

^

EPIP 1.01 TURNOVER CHECKLIST 30 ATTACHMENT PAGE 3

1 of 1 Conduct a turnover between the onshift and relief SEM in accordance with the following checkli st.

Use placekeeping aid at left of item.

• to track completion.

1 ~.

Determine the status of primary responder notification.

2.

Deter. vine the status of initial and follor up

• Report of Emergency to State and Local: Governments." EPIP 2.01. Attachments 1 and 2.

Get completed copies if available, 4

?

3.

Determine status of the " Report of Radiological Conditions to the State." EPIP 2.01. Attachment 3.

Get completed copy if available.

o 4

Determine status of Emergency Notification System (ENS) communications l

and completion status of NRC Event Notification Worksheet (EPIP 2.02 ).

5, Review classification and initial PAR status.

6.

. Review present olant conoitions and status.

Get copy of Critical

(}

Safety Functions form.

Review status of station firewatches and re-establish if conditions 4

allow.

8.

Determine readiness of TSC for activation.

9, After all information is oDtained, transfer location to TSC. (Consider direct transfer of State & local notifications to LEOF/CEOF.)

10. Call the Control Room anc assess any changes that may have occurred curing-transition to tne TS:.

11. When sufficient personnel are available the relief SEM is to assume the following responsibilities from the onshift 5tation Emergency Manager:

a.

Reclassification, b.

Protective Action Recommendations until LEOF activated.

C.

Notifications (i.e.. state, local, & NRC).

Upon LEOF activation, transfer notification responsibilities except for the NRC ENS.

d.

Site evacuation autnorization.

e.

Emergency exposure eutnorization.

f.. Command / control of onsite response.

12. Formally relieve the interim SEM and assume control in the TSC.

Announce name and facility activation status to facility.

i 1

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