Text

Forwards Revised Epips,Including Rev 11 to EPIP-4.08,rev 11 to EPIP-4.09,rev 39 to EPIP-1.01 & Rev 21 to EPIP-3.02,per 10CFR50.54(q).No Commitments Contained in Ltr
	ML18151A623
Person / Time
Site:	Surry
Issue date:	01/13/1998
From:	Christian D; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18151A390	List: ML18151A623;
References
	98-016, 98-16, GL-81-27, NUDOCS 9801210253
	Download: ML18151A623 (111)
	v • d • e

.. *..

t **.

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 January 13, 1998 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555-0001 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 Serial No.98-016 BAG RO Docket No.

50-280 50-281 License No.

DPR-32 DPR-37 REVISIONS TO EMERGENCY PLAN IMPLEMENTING PROCEDURE Pursuant to 10 CFR 50.54(q), enclosed are the revisions to a Surry Power Station Emergency Plan Implementing Procedure.

The revisions do not implement actions which decrease the effectiveness of our Emergency Plan. The Emergency Plan and Implementing Procedures continue to meet the standards of 10 CFR 50.47(b). Please update your manual by performing the actions described in the enclosed tabulation of changes.

Vsyyours,

~Gulx=:-

D. A. Christian, Station Manager Surry Power Station Enclosure Commitments contained in this letter: None.

cc:

U.S. Nuclear Regulatory Commission (2 copies)

Region II Atlanta Federal Center 61 Forsyth Street S.W., Suite 23T85 Atlanta, Georgia 30303 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station

.------ ----~

1 I IIIIII IIIIIHIII IIIII IIIIII IIII IIII IIII

&&44D6*

~-----9801210253 980:Cf 3 ____________ ~_ --------,,

PDR ADOCK 05000280

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Serial No.98-016 Surry EPIP Revision VIRGINIA ELECTRIC AND POWER COMPANY REVISION TO SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE Enclosed are rev1s1ons to a Surry Power Station Emergency Plan Implementing Procedure. Please take the following actions in order to keep your manual updated with the most recent revisions.

REMOVE AND EFFECTIVE INSERT:

EFFECTIVE DESTROY:

DATE:

EPIP-4.08, Rev. 1 (v /

01/07/97 EPIP-4.08, Rev. 1~ ~ 12/17/97

)

,f EPIP-4.09, Rev. 1 oY' 01/07/97 EPIP-4.09, Rev. ;r,f 12/17/97

/"

EPIP-1.01, Rev. 38~

I" 04/04/97 EPIP-1.01, Rev. 39,v V 01/05/97

/

I' V

EPIP-3.02, Rev. 2'!¥

EPIP-3.02, Rev. 20V 03/14/96 01/05/97 Emergency Plan Privacy and Proprietary Material have been removed.

Reference Generic Letter No. 81-27

§o,--2~/l 5~pµ-t,pJe,r;r p~,.. ~v'/~ ~ J.fpjpj ~

lfl":"l/9~ #9~p/,Z/~.$.:>:3

( v-.,

Level 2 Controlled 01w1on Maintaine\\fjWttllij b nt Do not rem~l\\ls dl~e ir*T Jiitti work EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE E* P-4.08 INITIAL OFFSITE RELEASE ASSESSMENT (With 6 Attachments)

\\

PURPOSE l

_/

I

/

REVYSION I

/ 10

/" PAGE

/

1 of 11 Use of backup (manual) dose assessment calculations to

~s{ess consequences of actual o potential offsite releases.

/

ENTRY CONDITIONS Any of the following:

I I

/,-

I I

/

EPIP-4.01, RADIOLOGICAL ~SSESSMENT DIRECTOR CONTROLLING PROCEDURE.

EP I P-4. 03, DOSE ASSESSMENT E.'CONTROLLI NG PROCEDURE. -

r

- /'

CPIP-6.2, R~DIOLOGICAL /~ESS\\T COORDINATOR.

1.

2.

3.

4.

Direction by the Statj~n Emerge~~Y Manager.

I I -

j APPROVAL 1~ECOMMENDED SN SOC APPROVAL I -

I DATE 1 /1 /11 CHAIRMAN SN SOC

\\

Form No. 723758i~Pr 91)

NUMBER PROCEDURE TITLE REVISION EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT 10 PAGE 2 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

~~

1 INITIATE PROCEDURE:

By:

Date:

Time:

NOTE:

An initial offsite release assessment should be performed within 15 minutes of declaration of a General Emergency.

2 CHECK IF CURRENT EVENT CLASSIFICATION - NOTIFICATION OF UNUSUAL EVENT OR ALERT l.E unknown, THEN GO TO Step 3 l.E Site Area or General Emergency, THEN GO TO NOTE prior to Step 6.

NOTE:

Evaluation of percent technical specifications in this procedure makes assumptions about flow rate, isotopic mixture and detector response. Further analysis upon completion of this procedure will be necessary to quantify releases.

3 CHECK IF EMERGENCY INVOLVES LIQUID RELEASE GO TO NOTE prior to Step 5.

I

_j

NUMBER PROCEDURE TITLE REVISION EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT 10 STEP PAGE 3 of 11 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE:

Results of Discharge Tunnel and SRF Liquid Monitor are not additive.

The Discharge Tunnel is considered the final liquid effluent release point.

4 DETERMINE PERCENT TECHNICAL SPECIFICATION FOR LIQUID RELEASE:

a) Get monitor indications:

Discharge Tunnel : ____ cpm

SRF RRM-131: ______ cpm b) Use the fo 11 owing equations:

Discharge Tunnel:

cpm X 3.0E-3 = % Tech Spec X 3.0E-3 =

RRM-131:

cpm x 3.37E-4 = % Tech. Spec.

____ x 3.37E-4 = _____ %

c) Compare percent Tech Spec with emergency classification criteria:

Percent Tech Spec GREATER THAN OR EQUAL TO 1000% - ALERT

Percent Tech Spec GREATER THAN OR EQUAL TO 100% -

NOTIFICATION OF UNUSUAL EVENT

Percent Tech Spec LESS THAN 100% - RELEASE WITHIN LIMITS d) Notify RAD or RAC of event classification based on percent Tech Spec for liquid release

NUMBER PROCEDURE TITLE REVISION EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT 10 STEP PAGE 4 of 11 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE:

Surry Radwaste Facility (SRF) Vent Monitor RRM-101 information is available from the SRF Control Room.

5 DETERMINE PERCENT TECH SPEC FOR GASEOUS RELEASE:

a) Get highest value of the following:

VG-110 (cpm)

VG-131 (µCi/sec and µCi/cc)

GW-102 C cpm)

GW-130 (µCi/sec and µCi/cc)

SV-111 (cpm)

SV-211 (cpm)

RRM-101 ( cpm) b) Get effluent flow rate (cfm) of the following:

Vent Vent flow rate

Process Vent flow rate

Air ejector flow rate

SRF Vent flow rate c) Record on Attachment 1 Determine total percent Tech Spec (STEP 5 CONTINUED ON NEXT PAGE)

IE NO gaseous release, THEN GO TO Step 10.

a) IE all values are NOT available, THEN get value of monitor in alarm.*

b) IE flow rate NOT available, THEN use design flow rate:

Vent Vent= 172,000 cfm

Process Vent= 310 cfm

Air Ejector= 25 cfm

SRF Vent= 51,340 cfm

f NUMBER PROCEDURE TITLE REVISION EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT 10 STEP ACTION/EXPECTED RESPONSE 5

DETERMINE PERCENT TECH SPEC FOR GASEOUS RELEASE: (Continued) d) Compare percent Tech Spec with emergency classification criteria:

Percent Tech Spec GREATER THAN OR EQUAL TO 1000% - ALERT

Percent Tech Spec GREATER THAN OR EQUAL TO 100% -

NOTIFICATION OF UNUSUAL EVENT

Percent Tech Spec LESS THAN 100% - RELEASE WITHIN LIMITS e) Notify RAD or RAC of event classification based on percent Tech Spec for gaseous release PAGE 5 of 11 RESPONSE NOT OBTAINED NOTE:

No release through Air Ejector(s) should be assumed if Air Ejector is diverted to containment.

The total dose rate from each pathway should be calculated using, 3 and/or 4 if the release is from more than one pathway.

6 DETERMINE SITE BOUNDARY DOSE RATE (mrem/hr) FOR VENTILATION RELEASE:

a) Ask SEM (via RAD or RAC) to*

have someone observe the increasing or decreasing trends of the monitor (STEP 6 CONTINUED ON NEXT PAGE)

NUMBER EPIP-4.08 STEP PROCEDURE TITLE INITIAL OFFSITE RELEASE ASSESSMENT REVISION 10 PAGE 6 of 11 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 DETERMINE SITE BOUNDARY DOSE RATE (mrem/hr) FOR VENTILATION RELEASE: (Continued) b) Check if release pathway is through any of the following:

Process Vent

Vent Vent

Air Ejector

SRF Vent c) Check if monitors for affected pathway - OPERABLE:

Kaman Science

Eberline (SRF)

Victoreen (STEP 6 CONTINUED ON NEXT PAGE) b) IF release is through the Main Steam System, THEN GO TO Step 7 lE release is from containment leakage, THEN GO TO Step 8.

c) lE Kaman Science Monitor inoperable or offscale. THEN do the following:

1) Get parameters:

Stability Class

Wind Speed (mph)

mR/hr from VG-123 or GW-122

Flow rate (cfm)

2) GO TO Step 6.e.

lE SRF Eberline Monitor inoperable, THEN ask RAD or RAC for guidance lE Victoreen Monitor offscale or inoperable, THEN do the following:

1) Use Kaman Science Monitor

2) GO TO Step 6.d.

NUMBER PROCEDURE TITLE REVISION EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT 10 PAGE 7 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6

DETERMINE SITE BOUNDARY DOSE RATE (mrem/hr) FOR VENTILATION RELEASE: (Continued) d) Get the following information from RAD or RAC:

1) Monitor number of interest

2) Highest cpm, µCi/sec and

µCi/cc from monitor of interest

3) Flow rate (cfm) for release pathway

4) Stability Class

5) Wind Speed e) Record above data on f) Get X/0 and conversion factors from Attachment 5:

Site Boundary X/0 for Stability Class in effect

Monitor Conversion Factor (MCF) based on accident type

TEDE DCF

THY DCF g) Record X/0, wind speed and conversion factors on h) Determine Site Boundary TEDE and THY COE. mrem/hr. using i) Record results of Attachment 2 on Attachment 6

NUMBER PROCEDURE TITLE REVISION EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT STEP 8

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE:

No release is assumed from the AFWPT pathway if the AFWPT is isolated.

10 PAGE of 11

Results of Attachments 2 and 3 are cumulative if the release is through both the Main Steam System and Ventilation System.

7 DETERMINE SITE BOUNDARY DOSE RATE (mrem/hr) - MAIN STEAM SYSTEM:

a) Check if actual or potential release pathway through Main Steam Safety Valves or Auxiliary Feedwater Pump Turbine Exhaust (AFWPT) b) Get number and mR/hr of the monitor(s) of interest from SEM (via RAD or RAC):

Unit 1 Main Steam Unit 2 Main Steam a) GO TO Step 8.

MS-124 (A Safety Valves)

MS-125 CB Safety Valves)

MS-126 (C Safety Valves)

MS-224 (A Safety Valves)

MS-225 CB Safety Valves)

MS-226 CC Safety Valves)

Unit 1 AFWPT Unit 2 AFWPT MS-129 MS-229 c) Get the following information from RAD or RAC:

Stability Class

Wind Speed

Number of Main Steam Safety Valves that have lifted or may potentially lift

Status of AFWPT isolation (STEP 7 CONTINUED ON NEXT PAGE)

NUMBER PROCEDURE TITLE REVISION EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT 10 STEP ACTION/EXPECTED RESPONSE 7

DETERMINE SITE BOUNDARY DOSE RATE (mrem/hr) - MAIN STEAM SYSTEM: (Continued) d) Get X/0 and conversion factors from Attachment 5:

Site Boundary X/0 for Stability Class in effect

Monitor Conversion Factor (MCF) based on accident type

TEDE DCF

THY DCF e) Record X/0, wind speed.

valves and conversion factors on f) Determine Site Boundary TEDE and THY COE. mrem/hr, using g) Record results of Attachment 3 on Attachment 6 PAGE 9 of 11 RESPONSE NOT OBTAINED

NUMBER PROCEDURE TITLE REVISION EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT 10 PAGE 10 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE:

Results of Attachments 2. 3 and 4 are cumulative if the release is through the Ventilation System, Main Steam System and Containment.

~~

8 DETERMINE SITE BOUNDARY DOSE RATE (mrem/hr) - CONTAINMENT LEAKAGE:

a) Check if actual or potential release pathway from Containment Leakage b) Get CHRRMS reading, R/hr Unit 1 RMS-127 RMS-128 Unit 2 RMS-227 RMS-228 c) Get the following information from RAD or RAC:

Stability Class

Wind Speed d) Get X/0 and conversion factors from Attachment 5:

Site Boundary X/0 for Stability Class in effect

Monitor Conversion Factor (MCF) based on accident type

TEDE DCF

THY DCF e) Record X/0, wind speed and conversion factors on f) Determine Site Boundary TEDE and THY COE. mrem/hr, using g) Record results of Attachment 4 on Attachment 6 a) lE NO release pathway from containment. THEN GO TO Step 9.

I NUMBER PROCEDURE TITLE REVISION

-***** EPIP-4.08 INITIAL OFFSITE RELEASE ASSESSMENT 10 STEP ACTION/EXPECTED RESPONSE 9

DETERMINE DOSE RATES. mrem/hr. AT

2. 5 AND 10 MILES:

a) Use Attachment 6 b) Add results of appropriate release pathways:

Vent (Attachment 2)

Main Steam (Attachment 3)

Containment (Attachment 4) c) Determine Stability Class correction factor for distance of interest d) Do calculation Determine TEDE and THY COE at 2, 5 and 10 miles e) Report results to RAD or RAC 10 TERMINATE EPIP-4.08:

Give completed EPIP-4.08, forms and other applicable records to the RAD or RAC

Completed by:

Date:

Time:

-END-PAGE 11 of 11 RESPONSE NOT OBTAINED

j

~UMBER ATTACHMENT TITLE EPIP-4.08

% TECHNICAL SPECIFICATION WORKSHEET ATTACHMENT 1

Date:

YEtlI YEtlI*

CPM X

VG*llO:

X

µCi/sec X

VG*131:

X

µCi/cc X

VG*131:

X PROCESS YEtlI

CPM X

GW*102:

X

µCi/sec X

GW*l30:

X

µCi/cc X

GW*l30:

X UNII I AIR EJECIPR*

CPM x

SV*lll: ----

UtlII 2 AIR EJECIPR*

CPM SV*211: ----

X X

X SURRY RADWASTE FACILITY*

CPM RRM*lOl: ----

X X

Time:

CFM X

CF X

4.19 E*8 CF 3.52 E*3 CFM CF X

1. 66 CFM X

CF X 8.28 E*9 CF 5.88 E*5 CFM CF X

2.77 E*2 CFM X

CF x 2.01 E*5 CFM X

CF x 1.74 E*6 Completed by:------------

Date/Time: -----'----~

% TS I

I I

Highest% TS

% TS

_J

% TS I

I I

Highest% TS

% TS

_J

t TS

% TS

t TS TOTAL% TECH. SPECS.:

REVISION 10 PAGE 1 of 1

% TECH. SPEC.

I

r-lUMB6R ATTACHMENT TITLE REVISION *

EPIP-4.08 VENT RELEASE SITE BOUNDARY DOSE RATE 10 ATTACHMENT PAGE 2

1 of 2

.fillIL;_

Site Boundary X/0, Monitor Conversion Factors (MCF),

TEDE.Dose Conversion Factors (TEDE DCF) and Thyroid COE Factors (THY DCF) are provided on Attachment 5.

VG-123 and GW-122 should only be used when KAMAN or Normal Range Monitors are offscale or inoperable.

Date: _____ ; Time: ___ _

VENT VENT*

C CPM x

CFM x

X/0 x

MCF

) / WINDSPEED = mrem-Ci/Rem-m3 I VG-110:

C x

x --- x l /

I I

/ WINDSPEED

=

mrem-Ci/Rem-m3 I

(µCi/sec x l.OE-3 x X/0 VG-131: (

x l.OE-3 x __

I

(µCi/cc X

CFM X 4.72E-l X

X/0 h

) / WINDSPEED = mrem-Ci/Rem-m3 I I VG-131:

(

X x 4.72E-l X ___ ) I 11 mr/hr X

CFM X

X/0 X

MCF I I

) / WJNDSPEED = mrem-Ci/Rem-m3 I I VG-123:

X X

X ~~> I I I

__J I HIGHEST mrem-Ci/Rem-m3 I

f-x -j TEDE DCF I

I L...--- x -j THY DCF I

eBQCESS VENT*

(

CPM X

CFM X

X/0 X

MCF

) / WINDSPEED = mrem-Ci/Rem-m3 I GW-102:

(

) /

I X

X X

mrem-Ci/Rem-m3 I

(µCi/sec X l.OE-3 x X/0 l / WI NDSPEED I

GW-130:

(

X l.OE-3 x

) /

I

) / WINDSPEED = mrem-Ci/Rem-m3 h

(µCi/cc X

CFM x 4.72E-l X

X/0 I I GW-130:

(

X x4.72E-l X

) /

I I l / WINDSPEED = mrem-Ci/Rem-m3 I I C mr/hr X

CFM X

X/0 X

MCF I I GW-122:

(

X X

X

) /

I I

_ __J I HIGHEST mrem-Ci/Rem-m3 I

f-x -j TEDE DCF I

I L...--- x -j THY DCF I

TEDE IW!lllLhJ::

THY CDE lD.WlLhr.

, NUMBE,R ATTACHMENT TITLE EPIP-4.08 VENT RELEASE SITE BOUNDARY DOSE RATE ATTACHMENT 2

A IR E,l ECTOR*

(

CPM X

CFM X

X/0 X

MCF

/ WINDSPEED = I mrem-Ci/Rem-m3 SV-111: (

X X

X

) I

=I CPM X

CFM X

X/0 X

MCF

/ WINDSPEED = I mrem-Ci/Rem-m3 SV-211:

(

X X

X

) I

= I TOTAL OF AIR EJECTORS I f-x --j TEDE DCF I

I

~-- x --j THY DCF I

SURRY RADWASTE FACJI UY*

(

CPM x

CFM x

X/0 x

MCF

} / WINDSPEED =J mrem-Ci/Rem-m3 RRM-101: ( ___ x --- x --- x l /

=I ~---

TOTAL VENT RE\\ EASE*

SUM OF: VENT VENT, PROCESS VENT, AIR EJECTORS. SRF:

Completed by: -----------

Date/Time: ----~---

X TEDE DCF I

TEDE mr.emLb..c.

SUM TEDE J mrem/hr REVISION 10 PAGE 2 of 2 THY COE mr.emLb..c.

SUM THY COE I

I J mrem/hr J

""""""7""".

NUMBER ATTACHMENT TITLE REVISION EPIP-4.08 MAIN STEAM RELEASE - SITE BOUNDARY DOSE RATE 10 ATTACHMENT PAGE 3

1 of 2 NOTE:

Site Boundary X/Q, Monitor Conversion Factors (MCF), TEDE Dose Conversion Factors (TEDE DCF) and Thyroid CDE Factors (THY DCF} are provided on Attachment 5.

Date:~. _____ ; Time: ____ _

UNIT 1 MAIN STEAM:

( mr/hr X

Valves x X/Q x

MCF

) / WINDSPEED =

mrem-Ci/Rem-m 3

MS-124: (

X X ___ x

)/ __

MS-125:(

X X ___ x __

MS:126: (

X X ___ x __

TOTAL OF UNIT 1 MAIN STEAM t-x -j TEDE DCF:

'----- x -j THY DCF:

UNIT 1 AFWPT:

mr/hr x X/Q x

MCF

) / WINDSPEED =

mrem-Ci/Rem-m 3

MS-129: (

x x

) / ---

I f---- x -j TEDE DCF:

I I

L x -j THY DCF:

TEDE THY CDE

NUMBER ATTACHMENT TITLE REVISION EPIP-4.08 MAIN STEAM RELEASE - SITE BOUNDARY DOSE RATE 10 ATTACHMENT PAGE 3

2 of 2 NOTE:

Site Boundary X/Q, Monitor Conversion Factors (MCF), TEDE Dose Conversfon Factors (.TEDE DCF).and Thyroid CDE Factors (THY DCF) are provided on Attachment 5.

Date: _____ ; Time: ____ _

UNIT 2 MAIN STEAM:

( mr/hr x # Valves x XIQ x

MCF

) I WINDSPEED =

mrem*Ci/Rem*m 3

MS-224:( ___ x --- x --- x ___ ) / ---

MS-225:( ___ x --- x --- x ---

MS-226:( ___ X ___ X ___ X __

TOTAL OF UNIT 2 MAIN STEAM

~ x -j TEDE DCF:

'---- X -l THY DCF:

UNIT 2 AFWPT:

mr/hr x X/Q x

MCF

) / WINDSPEED =

mrem*Ci/Rem*m 3

MS-229:(

x ___ x

) / __

I f-- x -j TEDE DCF:

I I

L x -j THY DCF:

TOTAL MAIN STEAM RELEASE:

(SUM MS AND AFWPT)

Completed by:

Date/Time:

TEDE mrem/hr THY COE mrem/hr

NUMBER ATTACHMENT TITLE REVISION

---**. EPIP-4.08 CONTAINMENT RELEASE - SITE BOUNDARY DOSE RATE 10 ATTACHMENT PAGE 4

1 of 1 NOTE:

Site Boundary X/Q, Monitor Conversion Factors (MCF), TEDE Dose Conversion Factors (TEDE DCF) and Thyroid CDE Factors (THY DCF) are provided on Attachment 5.

The CHRRMS Monitor Conversion Factor is calculated for design leak rate of 0.1% per day.

Date:

Time: ____ _

CONTAINMENT:

RMS-127 RMS-128 RMS-227 RMS-228:

R/hr x

MCF x

X/Q

) / WINDSPEED =

mrem-Ci/rem-m 3

___ X X

)/ __

I f-- x -j TEDE DCF I

I I

I L

x -j THY DCF I

Complet:ed by:

Dat:e/Time:

TEDE mrem/hr THY CDE mrem/hr

NUMBER ATTACHMENT TITLE REVISION EPIP-4.08 SITE BOUNDARY X/Q VALUES, 10 ATTACHMENT MONITOR CONVERSION FACTORS, PAGE TEDE FACTORS, AND THYROID CDE FACTORS 5

1 nf 1 X /Q, SITE BOUNDARY:-

I STABILITY CLASS I A

B C

D E

F G

4.82 E-5 1.6L.E-4 3.28 E-4 7;54 E-4 1.2 E-3 1.87 E-3 2.44 E-3 MONITOR CONVERSION FACTORS (MCF):

I MONITOR MSLB SGTR I

FHA WGDT VCT I

LOCA IPRI. GAS I LKD. ROTORI NORMAL I SRF I VG-llO l.lE-8 l.OE-8 I l.lE-8 I I 4.4E-9 I 9.9 E-8 1.lE-8 I J VG-123 J 22.a 15.3 I 56.6 1.41 J 16.2 36.6 J GW-102 J1.07E-7 l.31E-7 J I l.38E*7 J GW-122 J sa.1 17.4 37.5 J MS-1(2)24 I I

I J MS-1(2)25 I 5.6E+3 I 4. 5E+3 I

3.87E+2 2.2E+3 I MS-1(2)26 I

I I

I MS-1(2)29 J 1. 2E+4 I 1. 25E+4 I I

1.9E+3 7.5E+3 I SV-lll I

I I

I SV-2ll J 6.4E-6 I 6.6E-6 I I 6.45E-6 I 3:9E-5 I 6.6E-6 3.6E-6 6.6E-6 I I RMS-1(2)27 I

I I RMS-1(2)28 J 7.3E-2 I l.6E*l I RRM-101 I ------ I ------

l.9E-a I 2.6E-7 TEDE DOSE CONVERSION FACTORS (TEDE DCF):

MSLB I

SGTR I

FHA WGDT I

VCT LOCA IPRI. GAS I LKD. ROTORI SRF I

J 5.5E+3 J 2.8E+3 I 3.lE+l l.78E+1J 4.0E+l 1.4E+3 J l.4E+2 J 7.2E+3 J 2.1E+2 I THYROID CDE DOSE CONVERSION FACTORS (THY DCF):

MSLB I

SGTR I

FHA WGDT VCT I

LOCA JPRI. GAS I LKD. ROTORJ SRF I UNFILTERED I 2.0E+4 J 5.7E+3 J 6.8E-1 0

0 J 7.9E+3 J 6.6E+l

3. 7E+4 0

J FILTERED J 2.5E+2 J 6.9E+l J 6.8E-2 J 0

0 I 7.9E+2 I 6.6E+O 0

NUMBER ATTACHMENT TITLE REVISION EPIP-4.08 DETERMINATION OF 2, 5 AND 10 MILE DOSE RATES 10 ATTACHMENT PAGE 6

1 of 1 STABILITY CLAS.S CORRECTION FACTOR I MILES A

B C

D E

F G

2

1. 3 7E-2 l.12E-2 4.27E-2 6.37E-2 8.33E-2

1. 28E-l 2.38E-l 5

6.02E-3 2.36E-3 8.84E-3

1. 5 9E-2 2.42E-2 3.74E-2 7.79E-2 10 3.llE-3 l.24E-3 2.80E-3 5.84E-3

1. OOE-2 1.SSE-2 3.24E-2 CALCULATION:

SUM OF TEDE:

ATT. 2:

ATT. 3:

CORRECTION FACTOR TEDE mrem/hr ATT. 4:

2 miles:

,___ =

2 miles:

SUM:

TEDE DOSE RATE, CORRECTION FACTOR TEDE mrem/hr SITE BOUNDARY

-x--

5 miles:

.....__ =

5 niiles:

mrem/hr CORRECTION FACTOR TEDE mrem/hr 10 miles:

,___ =

10 miles:

SUM OF THY CDE:

ATT. 2:

ATT. 3:

ATT. 4:

CORRECTION FACTOR THY CDE mrem/hr SUM:

2 miles:

-=

2 miles:

I THY. CDE CORRECTION FACTOR THY CDE mrem/hr DOSE RATE

-x--

5 miles:

-=

5 miles:

SITE BOUNDARY mrem/hr CORRECTION FACTOR THY CDE mrem/hr 10 miles:

-=

10 miles:

NUMBER EPIP-4.09 PURPOSE Level 2 Controlled Distribution Maintainedlllj&fi~ tle~t Do not remmfd.JftM d86Wiiln$ik lfW work EMERGENCY PLAN IMPLEMENTING PROCEDURE PROCEDURE TITLE SOURCE TERM ASSESSMENT (With 6 Attachments)

REVISION 10 PAGE 1 of 13 To provide guidance for assessing radioactive release rates.

ENTRY CONDITIONS Any of the following:

1.

Activation by EPIP-4.01, RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE.

2.

Activation by EPIP-4.03, DOSE ASSESSMENT TEAM CONTROLLING PROCEDURE.

APPROVAL RECOMMENDED SNSOC APPROVAL APPROVAL EFFECTIVE DATE

-9\\

DATE DATE

,,,/

1 !-i/17

.i;.,.

c.___::), E., '"

1-1-,7 1-1-17 CHAIRMAN SNSOC l STATION MANAGER Form No. 723758(Apr 91)

~UMBER EPIP-4.09 PROCEDURE TITLE SOURCE TERM ASSESSMENT REVISION 10 STEP ACTION/EXPECTED RESPONSE 1

INITIATE PROCEDURE:

By:

Date:

Time:

PAGE 2 of 13 RESPONSE NOT OBTAINED NOTE:

Unless otherwise indicated, the Radiological Assessment Director/

Radiological Assessment Coordinator should be consulted when requesting action or information.

Source term units are expressed in Ci/sec.

Source term calculations based on monitor readings should be used for initial assessment and to establish trends. Sampling should be performed to more accurately determine source term.

2 CHECK IF ACTUAL OR POTENTIAL FOR RELEASE FROM CONTAINMENT EXISTS 1£ event does NOT involve potential or actual containment release. THEN determine source term from any of the following:

Effluent sample: GO TO Step 4

Sample of Station Inventory:

GO TO Step 7 OR

Station monitors: GO TO Step 8.

NUMBER*

PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT STEP ACTION/EXPECTED RESPONSE 3

DETERMINE CONTAINMENT SOURCE TERM FROM ANY OF THE FOLLOWING:

Containment Air Sample: GO TO Step 9

Containment High Range Monitor:

GO TO Step 10 3

RESPONSE NOT OBTAINED NOTE:

Results of each pathway analysis should be recorded on separate worksheets if more than one pathway is sampled.

4 DETERMINE SOURCE TERM FROM EFFLUENT SAMPLE:

a) Request initiation of EPIP-4.24, GASEOUS EFFLUENT SAMPLING DURING AN EMERGENCY, for sampling of appropriate effluent pathway:

Ventilation Vent

Process Vent

Air Ejector(s) b) Get monitor reading:

Maximum:

Reading at time of sample:

c) Have Count Room analyze sample:

Request initiation of EPIP-4.26, HIGH ACTIVITY SAMPLE ANALYSIS, for high activity samples (STEP 4 CONTINUED ON NEXT PAGE) 10 PAGE of 13

NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT 10 STEP ACTION/EXPECTED RESPONSE 4

DETERMINE SOURCE TERM FROM EFFLUENT SAMPLE: (Continued) d) Record nuclide activity on, left column Add results to determine Noble Gas and Iodine concentration e) Continue if this is an initial source term assessment f) Check if sample taken at maximum monitor reading g) Get effluent flow rate (cfm) h) Record flow rate on Attachment 2 i) Record Noble Gas and Iodine concentration on Attachment 2:

Use corrected µCi/cc from Step 4.f (if required) j) Use Attachment 2 to determine Noble Gas and Iodine release rate. Ci/sec for each pathway k) Add Ci/sec for applicable pathways at end of Attachment 2 PAGE 4 of 13 RESPONSE NOT OBTAINED d) lE iodine sample NOT taken, THEN continue assessment RETURN TO Step 4.d when results are available.

e) GO TO Step 4.g.

f) lE sample NOT taken at time of maximum reading, THEN determine corrected µCi/cc for both Noble Gas and Iodine:

MAX READING

µCi/cc= CORRECTED READING AT TIME OF SAMPLE x

µCi/cc

lE correction was NOT required, THEN use activity from Attachment 1.

NUMBER PROCEDURE TITLE REVISION

--*** EPIP-4.09 SOURCE TERM ASSESSMENT STEP ACTION/EXPECTED RESPONSE 5

DETERMINE ODE. TEDE AND THYROID COE DOSE CONVERSION FACTORS BASED ON SAMPLE RESULTS:

a) Use Attachment 1 that was previously filled out for gross activity determination b) Do caltulations on Attachment 1 to determine the following:

DOE

TEDE

THY COE c) Determine TEDE/DDE ratio:

TEDE

~~~-Ratio TEDE/DDE DOE d) Give source term results.

Ci/sec, and TEDE/DDE ratio to RAD or RAC 5

RESPONSE NOT OBTAINED a) Do Steps 4.a through 4,d GO TO Step 5.b.

10 PAGE of 13

NUMBER EPIP-4.09 STEP PROCEDURE TITLE SOURCE TERM ASSESSMENT ACTION/EXPECTED RESPONSE

~~

6 DETERMINE SITE BOUNDARY DOSE RATES BASED ON EFFLUENT SAMPLE RESULTS:

REVISION 10 PAGE 6 of 13 RESPONSE NOT OBTAINED a) Ask RAD or RAC if Site Boundary dose rate calculation based on effluent sample - DESIRED a) GO TO Step 13.

b) Record Sample TEDE DCF and Sample THY COE DCF from on to Attachment 3 c) Get effluent flow rate (cfm) for each affected pathway d) Record CFM on Attachment 3 e) Determine Stability Class and wind speed:

Ask RAD or RAC f) Use Attachment 3 Site Boundary X/0 value for appropriate Stability Class and divide by wind speed g) Record corrected X/0 value on calculation line for each affected pathway h) Do calculations to determine Site Boundary TEDE and THY COE dose rate. mrem/hr i) Give results to RAD or RAC j) GO TO Step 13

NUMBER EPIP-4.09 PROCEDURE TITLE SOURCE TERM ASSESSMENT REVISION 10 STEP ACTION/EXPECTED RESPONSE PAGE 7 of 13 RESPONSE NOT OBTAINED NOTE:

An error in calculation of gas volume may result due to water level in a tank. Water volume should be subtracted from design volume of the tank if the tank has water in it.

7 DETERMINE SOURCE TERM FROM STATION INVENTORY:

a) Check if release originated from a gas storage tank (e.g.,

Waste Gas Decay Tank, Volume Control Tank, etc.)

b) Have sample taken from appropriate tank c) Have Count Room analyze sample:

Request initiation of EPIP-4.26, HIGH ACTIVITY SAMPLE ANALYSIS. for high activity samples d) Record sample activity on. left column e) Use Attachment 1 to calculate gross Noble Gas and Iodine activity f) Determine release volume (in ft3):

. VOLUME (ft3) = Pl x V1 x T2

T2 Pressure before release. PSIA Pressure after release. PSIA Design volume of tank. ft3 Temperature before release. °K

= [(°F - 32)/L.8] + 273

= Temperature ~fter release. °K

= [(°F - 32)/1.8] + 273 (STEP 7 CONTINUED ON NEXT PAGE) a) RETURN TO Step 2.

1

--* r;==:!====::::;:::=========================:;:::::======:1 NUMBER EPIP-4.09 STEP PROCEDURE TITLE SOURCE TERM ASSESSMENT ACTION/EXPECTED RESPONSE 7

DETERMINE SOURCE TERM FROM STATION INVENTORY: (Continued) g) Determine release volume in milliliters (mls):

REVISION 10 PAGE 8 of 13 RESPONSE NOT OBTAINED x 2.832 E+4 mls VOLUME (ft3) x 2.832 E+4 VOLUME (mls) h) Record results on Attachment 3, Station Inventory section:

Noble Gas activity

Iodine activity

Volume of release in mls

Duration of release in seconds i) Use Attachment 3 to determine Noble Gas and Iodine release rate. Ci/sec j) Add Ci/sec from all pathways of concern at bottom of k) Give results to RAD or RAC

1) GO TO Step 13

'I l

NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT 10 PAGE 9 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE:

Effluent flow rates may not be needed for Kaman, Main Steam, AFWPT or Containment monitor calculations.

Kaman monitors are the primary method of assessment.

Should Kaman monitors be inoperable, then assessments should continue using Vent Vent or Process Vent Normal and/or High Range monitors.

~~8 DETERMINE SOURCE TERM FROM STATION MONITORS:

a) Get monitor readings and effluent flow rates (cfm) for release pathway(s) of concern:

VG-110, VG-131 and VG-123

GW-102, GW-130 and GW-122

SV-111

SV-211

Main Steam Readings

AFWPT readings

Unit 1 Containment: RMS-127 or -128

Unit 2 Containment: RMS-227 or -228 b) Record monitor readings and flow rates (where applicable) on Attachment 4 c) Determine accident type d) Determine status of effluent charcoal filtration e) Determine Monitor Conversion Factors (MCF) and Iodine Conversion Factors (Iodine CF) from Attachment 5 f) Record Conversion Factors on g) Do calculations on Attachment to determine Iodine and Noble Gas release rates, Ci/sec 4*

h) Add Ci/sec from all pathways of concern i ) Give results to RAD or RAC j) GO TO Step 13

. \\

NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT 10 PAGE 10 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE:

Source term is expressed as Curies in Step 9 below.

~~

9 DETERMINE SOURCE TERM FROM CONTAINMENT SAMPLE:

a) Ask RAD/RAC if a Containment Air sample is required b) Record sample results on, left column c) Determine gross activity for Noble Gas and Iodine (sum results) d) Record results on Attachment 2.

Containment Sample section e) Check release - IN PROGRESS (STEP 9 CONTINUED ON NEXT PAGE) a) lE containment air sample NOT required, THEN GO TO Step 10.

b) lE sample results NOT immediately available. THEN GO TO Step 10 AND RETURN TO Step 9.b when results are available.

e) GO TO Step 9.i

)

NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT 10

~ STEP ACTION/EXPECTED RESPONSE 9

DETERMINE SOURCE TERM FROM CONTAINMENT SAMPLE: (Continued)

I I

f) Record effluent flow rate (cfm) on Attachment 2 g) Use Attachment 2 to determine source term (Ci/sec) h) GO TO Step 11 (STEP 9 CONTINUED ON NEXT PAGE)

PAGE 11 of 13 I

I RESPONSE NOT OBTAINED I

I f) lE effluent flow rate NOT known, THEN do the following:

1) Ask Technical Support Team or Engineering Department for flow rate assessment

2) Get containment pressure (Pl, psia) and temperature n1. °K)

3) Calculate volume (mls):

1. 05E+ 12 X Pl

= VOLUME (mls)

T1. where T1

(°F - 32/1.8) + 273

4) Determine total Curies available for release:

NG

(µCi /ml) x Volume x 10-6 (mls)

NG Curies X ___ X 10-6 = __

Iodine

(µCi /ml) x Volume x 10-6 = Iodine (mls)

Curies X

X 10-6

5) GO TO Step 11.

NUMBER PROCEDURE TITLE REVISION EPIP-4.09 SOURCE TERM ASSESSMENT 10 PAGE 12 of 13 STEP ACTION/EXPECTED RESPONSE

.RESPONSE NOT OBTAINED 9

DETERMINE SOURCE TERM FROM CONTAINMENT SAMPLE: (Continued) i) Determine potential source term (Ci/sec):

1) Record 1.3 cfm for containment flow rate on

2) Use Attachment 2 to calculate Ci/sec

3) GO TO Step 11 10 DETERMINE SOURCE TERM FROM CONTAINMENT MONITOR:

a) Record dose rate (R/hr) from Containment High Range Monitor of affected unit:

Unit 1 Unit 2 RM-127 : ___ _

RM-227: ___ _

RM-128: __ _

RM-228: ___ _

b) Record number of hours since LOCA:

c) Use Attachment 6 to determine Curies (Ci) Noble Gas and Iodines in containment air available for release d) Determine release rate (Ci/sec):

____ Ci Noble Gas x 3.5E-8 = ___

.Ci/sec Noble Gas

____ Ci Iodine x 3.5E-8 = ___ Ci/sec Iodine e) Give results to RAD or RAC 11 CHECK IF MORE THAN ONE RELEASE PATHWAY INVOLVED GO TO Step 13.

NUMBER PROCEDURE TITLE EPIP-4.09 SOURCE TERM ASSESSMENT STEP ACTION/EXPECTED RESPONSE 12 RETURN TO STEP 2 13 TERMINATE EPIP-4.09 RETURN TO PROCEDURE IN EFFECT:

Give completed EPIP-4.09. forms and other applicable records to the Radiological Assessment Director/Radiological Assessment Coordinator

By:

Date:

Time:

-END-REVISION 10 PAGE 13 of 13 RESPONSE NOT OBTAINED

,*~

ATTACHMENT TITLE.

REVISION

... UMBE.R EPIP-4.09 NOBLE GAS, IODINE AND DOSE CONVERSION FACTOR WORKSHEET 10 ATTACHMENT 1

Sample Identification:

USING SAMPLE ANALYSIS RESULTS i--~-P-A_G_E~~~*

1 of 1 Sample Time:

.!iQI_(_;_

Total Noble Gas and Iodine activity, µCi/ml, are for use on Attachment 2.

Adjusted ODE. TEDE and THY COE are for use on Attachment 3.

NUCLIDE ACTIV.

EPA SAMPLE

µCi/ml DOE DOE DCF Kr-83M NA Kr-85 X 1. 3 Kr-85M X 93 Kr-87 X 510 Kr-88 X 1300 Kr-89 X 1200 Xe-131M X 4.9 Xe-133 X 20 Xe-133M X 17 Xe-135 X 140 Xe-135M X 250 Xe-137 X 110 Xe-138 X 710 TOTAL NOBLE CONTINUE GAS. µCi /ml :

ADDING DOWN I-125 X 6.3 I-129 X 4.8 1-131 X 220 1-132 X 1400 1-133 X 350 1-134 X 1600 I-135 X 950 TOTAL IODINE.

1DD£ DCF:

µCi /ml :

Completed by:

Date/Ti me:

EPA SAMPLE TEDE TEDE DCF X

1 X

1 CONTINUE ADDING DOWN X 4762 X 43750 X 241 X 3.5 X 43 X 1. 9 X 8.5 ITEDE DCF:

EPA THY DCF X 32 X 33 X 24.5 X 1. 6 X 14. 6 X 0.43 X 4.7 SAMPLE COE THY COE

.J

NUM.BER ATTACHMENT TITLE REVISION EPIP-4.09 SAMPLE EFFLUENT Ci/sec WORKSHEET 10 ATTACHMENT PAGE 2

1 of 1 Ci/sec MQN ITQR 1,J.Ci /ml CFM NQBLE GAS IQDrnE

.tl1il.;__

N.G.

X CFM X

4.72E-4 X

X 4.72E-4

!OD.

X CFM X

4.72E-4 X

X 4.72E-4 fi.;_

N.G.

x*

CFM X

4.72E-4 X

X 4.72E-4

!OD.

X CFM X

4.72E-4 X

X 4.72E-4 AIR EJECTOR /i.l:

N.G.

X CFM X

4.72E-4 X

X 4.72E-4

!OD.

X CFM X

4.72E-4 X

X 4.72E-4 AIR EJECTQR /i.2:

N.G.

X CFM X

4.72E-4 X

X 4.72E-4

!OD.

X CFM X

4.72E-4 X

X 4.72E-4 STATIQN I NHNTQBY; N. G.

X VOLUME ( ml s) X 1.0E-6 I SECONDS X

X 1.0E-6 I

!OD.

X VOLUME (mls) X 1.0E-6 I SECONDS X

X 1.0E-6 I __ =

CQNT8INMENT S8MPLE; N. G.

X CFM X

4.72E-4 X

X 4.72E-4

!OD.

X CFM X

4.72E-4 X

X 4.72E-4 SUM Ci/sec:

NG IQD Completed by:

Date/Time:

I NUMBER ATTACHMENT TITLE REVIS ION EPIP-4.09 SAMPLE EFFLUENT SITE BOUNDARY DOSE RATE WORKSHEET 10 ATTACHMENT PAGE 3

1 of 1 NOTE: TEDE and Thyroid CDE factors from Attachment 1 are to be applied to this worksheet.

X/Q, SITE BOUNDARY:

I STABILITY CLASS I

A B

C D

E F

G 4.82E-5 1.61E-4 3.28E-4 7.54E-4 1.20E-3 l.87E-3 2.44E-3 Wind speed Wind speed Wind speed Wind speed Wind speed Wind speed Wind speed Site Boundary Site Boundary TEDE DCF OR x/9.

TEDE THY. CDE MONITOR THY CDE DCF CFM WINDSPEED mrem/hr mrem/hr VENT:

TEDE X

CFM X

4.72E*l X

X/Q/WINDSPEED X

X

4. 72E* l X

THY CDE X

CFM X

4.72E*l X

X/Q/WINDSPEED X

X

4. 72E*l X

IT.;_

TEDE X

CFM X

4.72E*l X

X/Q/WINDSPEED X

X 4.72E*l X

THY CDE X

CFM X

4. 7 2E-l X

X/Q/WINDSPEED X

X

4. 72E-l X

AIR EJECTOR #.1:

TEDE X

CFM X

4. 72E-l X

X/Q/WINDSPEED X

X 4.72E*l X

THY CDE X

CFM X

4. 7 2E* 1 X

X/Q/WINDSPEED X

X

4. 72E- !

X AIR EJECTOR #.2:

TEDE X

CFM X

4.72E*l X

X/Q/WINDSPEED X

X

4. 7 2E* l X

THY CDE X

CFM X

4. 72E* l X

X/Q/WINDSPEED X

X

4. 72E* l X

STATION INVENTORY:

TEDE X

VOLUME (mls) X l.OE-3 / SECONDS X

X/Q/WINDSP.

X X

l.OE-3 /

X THY CDE X

VOLUME (mls) X l.OE-3 / SECONDS X

X/Q/WINDSP.

X X

1.0E-3 /

X CONTAINMENT SAMPLE:

TEDE X

CFM X

4. 72E* l X

X/Q/WINDSPEED X

X

4. 7 2E-l X

THY CDE X

CFM X

4.72E-l X

X/Q/WINDSPEED X

X

4. 72E-l X

Completed by:

SUM mrem/hr:

TEDE THY CDE Date/Time:

I

,,. N'UMBE~

ATTACHMENT TITLE REVISION

---EPIP-4.09 MONITOR Ci/sec WORKSHEET 10 ATTACHMENT PAGE 4

1 of 2

.!iQIL;_ Monitor Conversion Factors (MCF) and Iodine Conversion Factors (Iodine CF) are provided on Attachment 5).

Date: ____ ~; Time: ____ _

llE~I llENI

CPM VG-110:

µCi/sec VG-131:

µCi/cc VG-131:

mR/hr VG-123:

eBQCESS llENI

CPM GW-102:

µCi/sec GW-130:

µCi/cc GW-130:

mR/hr GW-122:

AJB f,lfCIQB*

CPM SV*lll: ----

X MCF X

CFM X

X X

1.00E-6 X 1.00E-6 X 4.72E-4 X

CFM X 4.72E-4 X

X MCF X

CFM X

X X

MCF X

CFM X

X X

1.00E-6 X

4.72E*4 X

CFM X

4.72E*4 X

X MCF X

CFM X

X x

MCF x

CFM X

X CPM x

MCF x

CFM SV-211: ----

X X

Ci/sec I

I H Ci/sec I

I I

Ci/sec I

I I

Ci/sec I

I I

__J Ci/sec I

I H Ci/sec I

I I

Ci/sec I

I I

Ci/sec I

I I

__J

=I Ci/sec

=I

=I Ci/sec

=I ISUM Ci/sec I

I I

L__ X --j I

Highest Ci/sec X I IODINE CF I (Att. 5): I =

I Highest Ci/sec X I IODINE CF (Att. 5):

IODINE NOBLE GAS Gilsec Gilsec r- = -jCi/sec NGI I

I I

I MINUS I

I I

Ci /sec loci. I I

I r = -jCi/sec NGI I

I MINUS I

I Ci/sec lod. I I

I I Ci/sec NG r = -l I

I MINUS I

I I

IODINE CF I I Ci /sec loci, I (Att. 5):

I= I I

I I

(

,NUMBER ATTACHMENT TITLE EPIP...:4.09 MONITOR Ci/sec WORKSHEET ATTACHMENT 4

t:l81!l SIEAt:l

mR/hr X

valves MCF Ci/sec I

SUM OF Ci/sec MS-124:

X X

I MS-125:

X X

H MS-126:

X X

I MS-224:

X X

I X I MS-225:

X X

I MS-.226:

X X

I IODINE CF I

(Att. 5):

__J AElill...

mR/hr X

MCF Ci/sec I

Highest Ci/sec MS-129:

X I H MS-229:

X I

I X I I

I IODINE CF I

(Att. 5):

__J CONIAINt:lENI* ~

Monitor Conversion Factor includes 0.1% design basis leak rate.

RMS-127 RMS-227 RMS-128 RMS-228 R/hr IO!AL curiesLsec*

X X

MCF Ci/sec X I IODINE CF I

(Att. 5): I =

I Sum above results of applicable pathways for Iodine and for Noble gas.

Completed by: -----~~----

Date/Time: ____..__ ___ _

REVISION 10 PAGE 2 of 2 IODINE NOBLE GAS Cilsec

~

I r = -jCi/sec NGI I

I I

I MINUS I

I I

Ci/sec 1od.1 I

I r = -jCi/sec NGI I

I I

MINUS I

I I

I *Ci /sec 1od.1 I

I I

I r = -jCi/sec NGI I

I I

MINUS I

I I

Ci /sec Iod. I I

TOTAL I

ICi/se1: IODI I

I I

I I TOTAL I

!Ci/sec NGI I

I I

I

.. i NUMBER ATTACHMENT TITLE REVISION

EPIP-4.09 MONITOR CONVERSION FACTORS 10 ATTACHMENT AND IODINE CONVERSION FACTORS PAGE 5

1 of 1 MONITOR CONVERSION FACTORS (MCF):

I MONITOR MSLB I SGTR I FHA WGDT VCT I LOCA I PRI. GAS I LKD. ROTOR I NORMAL I SRF I VG-110

1. lE-11 I I.OE-111 l.lE-111 I 4.4E-121 9.9 E-111 l.lE-11 I I VG-123 I 2:28E-2 I 1.53E-21 5.66E-21 1.47E-31 1.62E-i I 3.66E-21 I GW-102 l1.01E-1ol l.31E-1oi I ------

I 1.38E-101 I GW-122 I s.arn-21 1. 74E-2 I 3.75E-21 I MS-1(2)24 I I

I I

I MS-1(2)25 I 5.6E+O I 4.5E+O I

3. 87E-1 2.2E+o I I MS-1(2)26 I I

I I

I MS-1(2)29 I 1. 2E+l I 1. 25E+l I l.9E+O 7.SE+o I I SV-111 I

I I

I.

I I

I sv-211 I 6.4E-9 I 6.6E-9 I I

3.9E-8 I 6.6E-9 3.6E-9 6.6E-9 I I RMS-1(2)27 I

I I

I RMS-1(2)28 I 7.3E*5 I 1.6E-4 I

I RRM-101 I ------

I -- -- - -

1.9E-111 2.6E-lOI IODINE CONVERSION FACTORS (IODINE CF):

MSLB I

SGTR I

FHA WGDT VCT I

LOCA IPRI. GAS I LKD. ~OTORI SRF I UNFILTERED I 1. 7E* l I 1. OE* 1 I 2. 4E-3 0

0 I 3.8E*l I 3.21E-2 I 2.55E*l 0

I FILTERED I 2.lE-3 I 1.2E*3 I 2.4E*4 I 0

0 I 3.SE-2 I 3.21E*3 I 0

-~

.NUMBER EPIP-4.09 ATTACHMENT 6

HOURS AFTER LOCA 0

HOURS AF-TER LOCA 1

ATTACHMENT TITLE REVISION MATRIX:

10 PAGE CHRRMS EVENT AVAILABLE CURIES 1 nf?

No letdown or sprays are assumed avat]able.

Containment Air concentration (µCi/cc)= Ci Cont. Air x l.96E-5.

RCS concentration (µCi/cc)= Ci Cont. Air x 3.83E-3.

Data is given for 0, 1, 2 and 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after LOCA occurs.

CHRRMS EVENT DESCRIPTION Ci N.G.

Ci HALOGEN RCS R/hr Cont. Air Cont. Air D. E. I-131

µCi/ml

1. 3£+6 100% NG, 50% HAL 7.2E+8 Ci 3.87E+8 Ci

1. 77E+5 Released to Cont. Air

µCi/ml

1. 3E+5 10% NG, 5% HAL 7.2E+7 Ci 3.87E+7 Ci

1. 77E+4 Released to Cont. Air

µCi/ml 1.3E+4 1% NG,.5% HAL 7.2E+6 Ci 3.87E+6 Ci 1.77E+3 Released to Cont. Air

µCi/ml 4.5E+4 100% GAP 2.16E+7 Ci l.55E+7 Ci 7.11E+3 Released to Cont. Air

µCi/ml 4.5E+3 10% GAP 2.16E+6 Ci l.55E+6 Ci 7.11E+2 Released to Cont. Air

µCi/ml 4.5E+2 1% GAP 2.16E+5 Ci 1.55E+5 Ci 7.llE+l Released to Cont. Air

µCi/ml

1. 54 1% Failed Fuel

1. 49E+4 Ci 5.05E+2 Ci 6.20E-l Primary Gas Release

µCi/ml CHRRMS EVENT DESCRIPTION Ci N.G.

Ci HALOGEN R/hr Cont. Air Cont. Air 5.0E+5 100% NG, 50% HAL 3.13E+8 Ci 2.38E+8 Ci Released to Cont. Air 5.0E+4 10% NG, 5% HAL 3.13E+7 Ci 2.38E+7 Ci Released to Cont. Air 5.0E+3 1% NG,.5% HAL 3.13E+6 Ci 2.38E+6 Ci Released to Cont. Air l.80E+4 100% GAP 9.33E+6 Ci 9.54E+6 Ci Released to Cont. Air l.80E+3 10% GAP 9.33E+5 Ci 9.54E+5 Ci Released to Cont. Air

1. 80E+2 1% GAP 9.33E+4 Ci 9.54E+4 Ci Released to Cont. Air

1. 3 1% Failed Fuel

1. 47 E+4 Ci 4.60E+2 Ci Primary Gas Release

r,--;-:::-.

~ NUMBE.R EPIP-4.09 ATTACHMENT 6

~-

HOURS AFTER LOCA 2

HOURS AFTER LOCA 4

ATTACHMENT TITLE REVISION MATRIX:

10 PAGE CHRRMS EVENT AVAILABLE CURIES

?

n.f ?

No Letdown or Sprays are assumed available.

Containment Air concentration (µCi/cc)= Ci Cont. Air x 1.96-5.

RCS concentration (µCi/cc)= Ci Cont. Air x 3.83-3.

Data is given for 0, 1, 2 and 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after LOCA occurs.

CHRRMS EVENT DESCRIPTION Ci N. G.

Ci HALOGEN R/hr Cont. Air Cont. Air 3.7E+5 100% NG, 50% HAL 2.75E+8 Ci

1. 97E+8 Ci Released to Cont. Air 3.7E+4 10% NG, 5% HAL 2.75E+7 Ci

1. 97E+7 Ci Released to Cont. Air 3.7E+3 1% NG,.5% HAL 2.75E+6 Ci l.97E+6 Ci Released to Cont. Air l.4E+4 100% GAP 8.24E+6 Ci 7.92E+6 Ci Released to Cont. Air l.4E+3 10% GAP 8.24E+5 Ci 7.92E+5 Ci Released to Cont. Air

1. 4E+2 1% GAP 8.24E+4 Ci 7.92E+4 Ci Released to Cont. Air

1. 2 1% Failed Fuel l.45E+4 Ci 4.28E+2 Ci Primary Gas Release CHRRMS EVENT DESCRIPTION Ci N. G.

Ci HALOGEN R/hr Cont. Air Cont. Air 2.BOE+5 100% NG, 50% HAL 2.36E+B Ci l.56E+B Ci Released to Cont. Air 2.BOE+4 10% NG, 5% HAL 2.36E+7 Ci l.56E+7 Ci Released to Cont. Air 2.BOE+3 1% NG,.5% HAL 2.36E+6 Ci 1.56E+6 Ci Released to Cont. Air 8.6E+3 100% GAP 7.17E+6 Ci 6.26E+6 Ci Released to Cont. Air 8.6E+2 10% GAP 7.17E+5 Ci 6.26E+5 Ci Released to Cont. Air 8.6E+l 1% 'GAP 7.17E+4 Ci 6.26E+4 Ci Released to Cont. Air

1. 0 1% Failed Fuel l.43E+4 Ci 3.83E+2 Ci Primary Gas Release

l N'dMBER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 38 (With 1 Attachment)

PAGE 1 of 7 PURPOSE To initially assess a potential emergency cond~~ion and initiate corrective actions.

ENTRY CONDITIONS Any one of the following:

1. Another station procedure directs initiation of this procedure.

2. A potential emergency condition is reported to the Shift Supervisor.

APPROVAL RECOMMENDED CHAIRMAN SNSOC SNSOC DATE

'l-3-11 APPROVAL APPROVAL*

EFFECTIVE

~C(L DATE DATE STATION MANAGER Form No. 723758(Apr 91)

'(

NUMBER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 38 PAGE 2 of 7 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION:

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

.N.O.I.E.:

The ERFCS is potentially unreliable in the event of an earthquake.

1 Therefore, ERFCS parameters should be evaluated for accuracy should an earthquake occur.

MAKE INITIAL ASSESSMENT:

a) Determine event category using, Emergency Action Level Table Index b) Review EAL Tab associated with event category c) Use Control Room monitors, ERFCS, and outside reports to get indications of emergency conditions listed in the EAL Table d) Verify EAL - EXCEEDED e) Record procedure initiation:

By:

Date:

Time:

f) Initiate a chronological log of events g) Declare position of Station Emergency Manager d) l.E EAL.N.QI exceeded, I1::!l.fi RETURN TO procedure in effect.

NUMBER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 38 STEP PAGE 3 of 7 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE:

Assembly, accountability and/or initiation of facility staffing may not be desired during certain situations (e.g.. security event, adverse weather), or may have already been completed.

These activities should be implemented as quitkly as achievable given the specific situation.

2 CHECK CLASSIFICATION -

ALERT OR HIGHER:

a) Sound emergency alarm and make announcement on station Gai-Tronics system as follows:

"(Emergency classification) has been declared due to~~~~

b) Check if emergency assembly and accountability - PREVIOUSLY CONDUCTED c) Repeat Steps 2.a and 2.b GO TO Step 3.

b) Continue announcement as follows (when appropriate):

"All emergency response personnel report to your assigned stations.

All other personnel report to your Emergency Assembly Area".

NUMBER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 38 PAGE 4 of 7 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION:

All further instructions should be continued through unless otherwise directed to hold.

3 INITIATE SUPPORTING PROCEDURES:

a) Direct Emergency Communicators to initiate the following:

1) EPIP-2.01, NOTIFICATION OF STATE AND LOCAL GOVERNMENTS

2) EPIP-2.02, NOTIFICATION OF NRC b) Check if classification announcement made using Gai-Tronics system b) Notify the following to initiate controlling procedures:

HP Shift Supervisor:

EPIP-4.01, RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE

Security Shift Supervisor:

EPIP-5.09, SECURITY TEAM LEADER CONTROLLING PROCEDURE

NUMBER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 38 I

PAGE 5 of 7 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4

CHECK TSC - ACTIVATED 1£ TSC 1iQI activated, THEN do the following:

5 INITIATE EPIP FOR EMERGENCY CLASSIFICATION IN EFFECT:

Notification of Unusual Event -

EPIP-1.02, RESPONSE TO NOTIFICATION OF UNUSUAL EVENT

A 1 e rt -

EPIP-1.03, RESPONSE TO ALERT

Site Area Emergency -

EPIP-1.04, RESPONSE TO SITE AREA EMERGENCY

General Emergency -

E PIP -1. 05 ;** RfS*PONS E- *fO --GENERAL EMERGENCY a) Have STA report to the Control Room.

b) Notify Operations Manager-On-Call (OMOC) or Superintendent Operations.

c) Evaluate initiation of Operations Department directive for augmenting staff resources during Emergency Plan activation.

d) Evaluate having Radiological Assessment Director report to the Control Room.

NUMBER PROCEDURE TITLE EPIP.-1.01 EMERGENCY MANAGER CONTROLLING STEP ACTION/EXPECTED RESPONSE 6

NOTIFY OFFSITE AUTHORITIES OF EMERGENCY TERMINATION:

a) State and local governments (made by LEOF or CEOF when activated) b) NRC 7 TERMINATE EMERGENCY:

a) Make termination announcement to station personnel that addresses the following:

Emergency termination

Deactivation of facilities

Selective release of personnel

Completion and collection of procedures

Recovery PROCEDURE RESPONSE NOT OBTAINED b) Check if initiation of re-entry/recovery procedure -

REQUIRED b) GO TO Step 8.

c) GO TO EPIP-6.01, RE-ENTRY/

RECOVERY GUIDELINE REVISION 38 PAGE 6 of 7

NUMBER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 38 PAGE 7 of 7 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8

TERMINATE EPIP-1.01:

Give completed EPIPs, forms and other applicable records to the Emergency Procedures Coordinator in the TSC

Give to STA

Completed By:

Date:

Time:

-END-Notify Records Management that u*sed EPI Ps require replacement.

\\

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT PAGE INDEX 1

1 of 38 CAUTION:

Declaration of the highest 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.

1.

2.

3.

4.

5.

6.

7.

8.

9.

10.

11.

12.

13.

IF EVENT CATEGORY IS:

GO TO I.Aa Safety, Shutdown, or Assessment System Event...................... A Reactor Cool ant System Event...................................... B Fuel Failure or Fuel Handling Accident............................ C Containment Event................................................. D Radioactivity Event............................................... E DELETED Loss of Secondary Cool ant......................................... G Electrical Failure................................................ H Fi re.............................................................. I Security Event.................................................... J Hazard to Station Operation....................................... K Natural Events.................................................... L Mi scel l*aneous... Abflormal *Events..................................... M

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB A)

PAGE SYSTEM SHUTDOWN, OR ASSESSMENT 1

CONDITION/APPLICABILITY

1.

Inability to reach required unit operating condition within T.S. time limits ABOVE CSD CONDITION

2.

Loss of Function needed for unit HSD condition ABOVE CSD CONDITION SYSTEM SHUTDOWN 2 of 38 INDICATION CLASSIFICATION Intentional reduction NOTIFICATION.OF in power, load, or UNUSUAL EVENT temperature IAW T.S. Action Statement - HAS COMMENCED T.S. Action Statement time limit for condition change -

CANNOT BE MET a) Inability to attain the m1n1mum required heat sink as indicated by loss of the following:

Main Feedwater System

Auxiliary Feedwater SITE AREA EMERGENCY

Auxiliary Feedwater Crosstie b) Loss of High Head flowpath as indicated by loss of the following:

_Normal Charging System

- - H*i*gh-Head *S*I**-System

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT SYSTEM 1

CONDITION/APPLICABILITY

3.

Loss of cooling function

. needed for Cold Shutdown arid Refueling Condition CSD & RSD

4.

Failure of a safety or relief valve to close after pressure reductiQn ALL CONDITIONS (TAB A)

SHUTDOWN, OR ASSESSMENT SYSTEM EVENT INDICATION

Secondary System cooling capability - UNAVAILABLE

Loss of any of the following systems:

Service Water

Component Cooling

Residual Heat Removal

RCS temperature GREATER THAN 140° F

RC.S.

RCS pressure - LESS THAN 2000 psig Overpressure Mitigation System - ENABLED PAGE 3 of 38 CLASSIFICATION ALERT NOTIFICATION OF UNUSUAL EVENT

Any indication after lift or actuation that Pressurizer Safety or PORV - REMAINS OPEN

Flow - NON-ISOLABLE

-* -MA-IN--STE*AM Excessive flow through Steam Generator Safety or PORV as indicated by rapid RCS cooldown rate - GREATER THAN 50° F per hour

NUMBER ATTACHMENT TITLE EPIP-1.01 EMERGENCY ACTION LEVEL TABLE ATTACHMENT (TAB A)

SYSTEM SHUTDOWN, OR ASSESSMENT 1

CONDITION/APPLICABILITY

5.

Failure of the reactor to trip (ATWT)

POWER OPS & HSD

6.

Trip following ATWT that takes the reactor subcritical POWER OPS & HSD SYSTEM EVENT I ND I CATION

Reactor trip setpoint and coincidences - EXCEEDED

Automatic reactor trip from RPS - FAILED

Manual reactor trip from Control Room - FAILED

Reactor trip setpoint and coincidences - EXCEEDED

Automatic reactor trip from RPS - FAILED

Manual reactor trip -

REQUIRED

Manual reactor trip from Control Room - SUCCESSFUL REVISION 38 PAGE 4 of 38 CLASSIFICATION SITE AREA EMERGENCY ALERT

NUMBER ATTACHMENT TITLE*

REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB A)

PAGE

. SYSTEM SHUTDOWN, OR ASSESSMENT 1

SYSTEM EVENT 5 of 38 CONDITION/APPLICABILITY INDICATION

7.

Loss of plant communications

Station PBX phone system -

CLASS I FI CATION NOT! FI CATION OF

. UNUSUAL EVENT capability FAILED ALL CONDITIONS

8.

Inability to monitor a significant transient in progress ABOVE CSD CONDITION

Station Gai-Tronics system -

FAILED

Station UHF radio system -

FAILED

Most (>75%) or all j

visual annunciator alarms on panels "A" to "K" - NOT AVAILABLE

All computer monitoring capability (e.g., plant computer, ERFCS) - NOT AVAILABLE

Significant transient - IN PROGRESS (e.g., reactor SITE AREA EMERGENCY trip, SI, turbine runback >25%

thermal reactor power, thermal power oscillations >10%)

AND

Inability to directly monitor

- - -any****one**of--the***f o*l l owi11g **using Control Room indications:

Subcriti cal ity

Core Cooling

Heat Sink

Vessel Integrity

Containment Integrity

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB A)

PAGE SYSTEM SHUTDOWN, OR ASSESSMENT 1

CONDITION/APPLICABILITY

9.

Unplanned loss of safety system annunciators with compensatory indicators unavailable or a transient in progress ABOVE CSD CONDITION

10. Unplanned loss of most or all safety system annunciators for greater than 15 minutes ABOVE CSD CONDITION

11. Evacuation of Main Control Room with control NOT established within 15 minutes ALL CONDITIONS

12. Evacuation of Main Control Room required ALL CONDITIONS SYSTEM EVENT INDICATION

Unplanned loss of most

(>75%) or all visual annunciator alarms on panels "A" to "K" for GREATER THAN 15 minutes

All computer monitoring capability (e.g., plant computer, ERFCS) - NOT AVAILABLE 6 of 38 CLASSIFICATION ALERT Significant transient - INITIATED OR IN PROGRESS (e.g., reactor trip, SI, turbine runback >25%

thermal reactor power, thermal power oscillations >10%)

Unplanned loss of most

(>75%) or all visual annunciator al~rms on panels "A" to "K" for GREATER THAN 15 minutes Evacuation of the Control Room with stable shutdown control NOT established within 15 minutes Evacuation of the Control Room with stable shutdown control established within 15 minutes NOTIFICATION OF UNUSUAL EVENT SITE AREA EMERGENCY ALERT

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TABB)

PAGE REACTOR COOLANT SYSTEM EVENT 1

7 of 38 CONDITION/APPLICABILITY INDICATION CLASSIFICATION SITE AREA EMERGENCY

1.

RCS leak rate exceeds makeup capacity ABOVE CSD CONDITION

2.

RCS leak rate limit -

EXCEEDED ABOVE CSD CONDITION

3.

Leak rate requ1r1ng plant shutdown IAW T.S.

ABOVE CSD CONDITION

Primary system leak (LOCA)

- IN PROGRESS

Safety Injection - REQUIRED

RCS subcooling based on Core Exit Thermocouples -

LESS THAN 30° F RCS inventofj cannot be maintained based on pressurizer level or RVLIS indication

Primary system leak determined to be -

GREATER THAN 50 gpm

Pressurizer level can be -

RESTORED AND MAINTAINED Intentional reduction in power. load. or temperature IAW T.S. 3.1.C leakage limit Action Statement - HAS COMMENCED ALERT NOTIFICATION OF UNUSUAL EVENT

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TABB)

PAGE REACTOR COOLANT SYSTEM EVENT 1 '

CONDITION/APPLICABILITY

4. Steam generator tube rupture with loss of offs ite power ABOVE CSD CONDITION

5.

Excessive Primary to Secondary leakage with loss of offsite power ABOVE CSD CONDITION

6.

Gross Primary to Secondary leakage ABOVE CSD CONDITION 8 of 38 INDICATION

Steam generator tube rupture - IN PROGRESS CLASSIFICATION SITE AREA EMERGENCY

Offsite power to unit specific Transfer Buses (Unit 1: D & F; Unit 2: E & F) -

NOT AVAILABLE

Atmospheric steam release from*ruptured Steam Generator - OCCURRING OR REQUIRED

Intentional reduction ALERT in power, load. or temperature IAW T.S.

3.1.C.6 leakage limit Action Statement - HAS COMMENCED AND

Offsite power to unit specific Transfer Buses (Unit 1: D & F; Unit 2: E & F) -

NOT AVAILABLE

Steam Generator tube ALERT rupture - IN PROGRESS

.A..!iP.

---. -Sa*f e-ty **I rrj-ec-ti on - --RE{)U I RED

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB B)

PAGE REACTOR COOLANT SYSTEM-fVENT 1

9 of 38 CONDITION/APPLICABILITY INDICATION CLASSIFICATION GENERAL EMERGENCY

7.

Loss of 2 of 3 fission product barriers with pote~ti al loss of 3rd barrier ALL CONDITIONS Any two of a), b) or c) exist and the third is imminent:

a) Fuel cl ad integrity failure as indicated by any of the following:

RCS specific activity -

GREATER THAN OR EQUAL TO 300 µCi/gm dose equivalent I-131 OR 5 or more core exit thermocouples -

GREATER THAN 1200° F

.QR CHRRMS (Inside) Containment High Range Radiati~n Monitor:

RM-RMS-127 or -227, RM-RMS-128 or -228:

GREATER THAN 2 X 103 R/hr OR Outside Containment High Range Radiation Monitor:

RM-RMS-161 or -261, GREATER THAN 6.3 x 102 mR/hr b) Loss of RCS integrity as indicated by any of the following:

PORV failed open OR Loss of reactor coolant c) Loss of containment integrity as indicated by any of the following:

Containment pressure GREATER THAN 60 psia and NOT decreasing

.QR Release path to environment -

EXISTS

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TABB)

PAGE REACTOR COOLANT SYSTEM EVENT 1

CONDITION/APPLICABILITY

8.

Fuel failure with steam generator tube rupture ALL CONDITIONS 10 of 38 INDICATION Any two of a). b) or c) exists and the third is imminent:

CLASSIFICATION GENERAL EMERGENCY a)

Fuel cl ad integrity failure as indicated b) by any of the.following:

RCS specific activity GREATER THAN OR EQUAL TO 300 µCi/gm dose equivalent I-131 OR 5 or more core exit thermocouples -

GREATER THAN 1200° F

.QR High Range Letdown Radiation Monitor:

1-CH -RM -118.

2-CH-RM-218:

GREATER THAN 7.0xl06 cpm S/G tube rupture as indicated by both of the following:

Safety Injection - REQUIRED

.Af:ill

Steam generator tube rupture -

IN PROGRESS c)

Loss of Secondary integrity associated with ruptured S/G pathway as indicated by:

Steam discharge to atmosphere Loss of secondary coolant outside containment - IN PROGRESS

NUMBER ATTACHMENT TITLE EPIP-1.01 EMERGENCY ACTION LEVEL TABLE ATTACHMENT (TAB C)

FUEL FAILURE OR FUEL HANDLING ACCIDENT 1

CONDITION/APPLICABILITY

1.

Core damage with possible loss of coolable geometry ABOVE CSD CONDITION INDICATION a) Fuel clad failure as indicated by any of the following:

RCS Specific activity GREATER THAN 60 µCi/gm dose equivalent I-131 High Range Letdown Radiation Monitor:

1 -CH -RM -118,

2-CH-RM-218:

GREATER THAN l.4xl06 cpm b) Loss of cooling as indicated by any of the following:

5 confirmed core exit thermocouples -

GREATER THAN 1200° F Core delta T - ZERO Core delta T - RAPIDLY DIVERGING REVISION 38 PAGE 11 of 38 CLASSIFICATION SITE AREA EMERGENCY

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 AHACHMENT (TAB C)

PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT 1

12 of 38 CONDITION/APPLICABILITY INDICATION CLASSIFICATION ALERT

2.

Severe Fuel Clad Damage ABOVE CSD CONDITION

3.

Fuel cl ad damage indication ABOVE CSD CONDITION

RCS specific activity GREATER THAN 300 µCi/gm dose equivalent 1-131 i~igh Range Letdown

~adiation Monitor:

Either of the following indications occur within 30 minutes and remain for at least 15 minutes:

1-CH-RM-118, 2-CH-RM-218:

GREATER THAN 5.8 x 104 cpm

Intentional reduction NOTIFICATION OF in power, load, or UNUSUAL EVENT temperature IAW T.S. 3.1.D reactor coolant activity limit Action Statement -

HAS COMMENCED Q.R High Range Letdown Radiation Monitor:

Either of the following indications occur within 30 minutes and remain for at least 15 minutes:

1-CH - RM -118,

- - - - ---2-CH-*RM-*H8-:

GREATER THAN 5.8 x 103 cpm

NUMBER ATTACHMENT TITLE EPIP-1.01 EMERGENCY ACTION LEVEL TABLE ATTACHMENT (TAB C)

FUEL FAILURE OR FUEL HANDLING ACCIDENT 1

CONDITION/APPLICABILITY

4.

Probable large radioactivity release initiated by LOCA with ECCS failure leading to core degradation ABOVE CSD CONDITION INDICATION

Loss of reactor or seco~dary coolant -

IN PROGRESS

RCS specific activity -

GREATER THAN 300 µCi/gm dose equivalent 1-131 REVISION 38 PAGE 13 of 38 CLASSIFICATION GENERAL EMERGENCY CHRRMS {Inside) Containment High Range Radiation Monitor:

5.

Probable large radioactivity release initiated by loss of heat sink leading to core degradation ABOVE CSD CONDITION RM-RMS-127 or -227, RM-RMS-128 or -228:

GREATER THAN 2 x 103 R/hr

High or Low Head ECCS flow - NOT being delivered to the core (if expected by plant conditions)

Loss of Main Feedwater System and Condensate System

Loss of Auxiliary Feedwater System

-**-*-RHR -System * -

NOT OPERABLE GENERAL EMERGENCY

NUMBER ATTACHMENT TITLE EPIP-1.01 EMERGENCY ACTION LEVEL TABLE ATTACHMENT (TAB C)

FUEL FAILURE OR FUEL HANDLING ACCIDENT 1

CONDITION/APPLICABILITY

6.

Probable large radioactivity release initiated by failure of protection system to bring reactor subcritical and causing core degradation ABOVE CSD CONDITION

7.

Probable large radioactivity release initiated by loss of AC and all feedwater ABOVE CSD CONDITION INDICATION

Reactor nuclear power after trip remains -

GREATER THAN 5%

RCS pressure GREATER THAN 2485 psig and NOT decreasing OR Containment pressure and temperature -

RAPIDLY INCREASING

Loss of all onsite and offsite AC power REVIS ION 38 PAGE 14 of 38 CLASS I FI CATION GENERAL EMERGENCY GENERAL EMERGENCY

Turbine Driven Auxiliary Feedwater Pump - NOT OPERABLE

Restoration of either of the above NOT LIKELY within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

NUMBER ATTACHMENT TITLE EPIP-1.01 EMERGENCY ACTION LEVEL TABLE ATTACHMENT (TAB C)

FUEL FAILURE OR FUEL HANDLING ACCIDENT 1

CONDITION/APPLICABILITY

8.

Probable large radioactivity release initiated by LOCA with loss of ECCS and containment cooling

9.

ABOVE CSD CONDITION Major fuel damage accident with radioactive release to containment or fuel buildings ALL CONDITIONS INDICATION

Loss of reactor or secondary coolant -

IN PROGRESS

High or Low Head ECCS flow NOT being delivered to the core (if expected by plant conditions)

.A..N..!2

Containment RS sump temperature - GREATER THAN 190° F and NOT decreasing OR All Containment Spray and Recirculation Spray Systems - NQT OPERABLE

Water level in reactor vessel during refueling -

BELOW TOP OF CORE

.QR Water level in Spent Fuel Pit verified - BELOW TOP OF SPENT FUEL AND

*--.*Ve rifled-damage** to irradiated fuel resulting in readings on Ventilation Vent Kaman Monitor:

RM-VG-131 REVIS ION 38 PAGE 15 of 38 CLASSIFICATION GENERAL EMERGENCY SITE AREA EMERGENCY GREATER THAN 4.2 x 107 µCi/sec

NUMBER ATTACHMENT TITLE EPIP-1.01 EMERGENCY ACTION LEVEL TABLE ATTACHMENT (TAB C)

FUEL FAILURE OR FUEL HANDLING ACCIDENT 1

CONDITION/APPLICABILITY INDICATION

10.

Fuel damage accident with release of radioactivity to containment or fuel buildings ALL CONDITIONS

Verified accident involving damage to irradiated fuel

HP confirms fission product release from fuel Readings on Ventilation Vent Kaman Monitor:

RM-VG-131 REVISION 38 PAGE 16 of 38 CLASSIFICATION ALERT GREATER THAN 2.8 x 105 µCi/sec

11.

Loss of cask/fuel containment barriers or accidental criticality ALL CONDIT IONS*

12.

Spent Fuel Storage Facility accident ALL CONDITIONS

Verified loss of all cask/

fuel containment barriers

HP confirms fis~ion product release

Verified Spent Fuel Storage Cask seal leakage

.QR Spent Fuel Storage Cask dropped or mi s*handl ed ALERT NOTIFICATION OF UNUSUAL EVENT

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT 1

CONDITION/APPLICABILITY

1.

Extremely high Containment radiation, pressure and temperature ABOVE CSD CONDITION

2.

High Containment radiation, pressure and temperature ABOVE CSD CONDITION (TAB D)

PAGE CONTAINMENT EVENT 17 of 38 INDICATION

Outside Containment High Range Radiation Monitor:

CLASSIFICATION GENERAL EMERGENCY RM-RMS-161 or -261, GREATER THAN 3.0 X 103 mR/hr

.QR CHRRMS (Inside) Containment High Range Radiation Monitor:

RM-RMS-127 or -227, RM-RMS-128 or -228:

GREATER THAN. 9 x 103 R/hr A.N..P.

Containment pressure - GREATER THAN 45 psia an~ is NOT DECREASING OR Containment temperature -

GREATER THAN 280° F

Outside Contatnment High Range Radiation Monitor:

RM-RMS-161 or -261, GREATER THAN 6.3 x 102 mR/hr OR SITE AREA EMERGENCY CHRRMS (Inside) Containment High Range Radiatjon Monitor:

RM-RMS-127 or -227, RM-RMS-128 or -228:

GREATER THAN 2 x 103 R/hr

--AND

Containment pressure - GREATER THAN 23 psia and NOT decreasing Containment temperature -

GREATER THAN 200° F

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT 1

CONDITION/APPLICABILITY

3.

High Containment radiation, pressure and temperature ABOVE CSD CONDITION (TAB D)

CONTAINMENT EVENT '

INDICATION

Outside Containment High Range Radiation Monitor:

RM-RMS-161 or -261 GREATER THAN 24 mR/hr PAGE 18 of 38 CLASSIFICATION ALERT CHRMMS (Inside) Containment High Range Radiation Monitor:

RM-RMS-127 or -227, RM-RMS-128 or -228:

GREATER THA~ 1.54 R/hr

Containment pressure -

GREATER THAN 17.7 psia Containment temperature -

GREATER THAN 150° F

NUMBER ATTACHMENT TITLE EPIP-1.01 EMERGENCY ACTION LEVEL TABLE ATTACHMENT 1

CONDITION/APPLICABILITY

1.

Release imminent or in progress and site boundary doses projected to exceed 1.0 Rem TEDE or 5.0 Rem Thyroid COE ALL CONDITIONS

2.

Release imminent or in progress and site boundary doses projected to exceed 100 mrem TEDE or 500 mrem Thyroid COE ALL CONDITIONS (TAB E)

RADIOACTIVITY EVENT INDICATION HP assessment indicates actual or projected doses at or beyond Site Boundary - GREATER THAN 1.0 Rem TEDE or 5.0 Rem Thyroid COE HP assessment indicates actual or projected doses at or beyond Site Boundary - GREATER THAN 100 mrem TEDE or 500 mrem Thyroid COE REVISION 38 PAGE 19 of 38 CLASSIFICATION GENERAL EMERGENCY SITE AREA EMERGENCY

NUMBER ATTACHMENT TITLE EPIP-1.01 EMERGENCY ACTION LEVEL TABLE ATTACHMENT 1

CONDITION/APPLICABILITY

3.

High radiation or airborne contamination levels indicate a severe degradation in control of radioactive material ALL CONDITIONS (TAB E)

RADIOACTIVITY EVENT INDICATION a) Valid unexpected readings on any of the following monitors have increased by a factor of 1000:

Control Room Area

Auxiliary Building Control Area

Auxiliary Building Drumming Area

Decontamination Building Area

Fuel Pit Bridge Area

New Fuel Storage Area

Laboratory Area

Sample Room Area RM-RMS-157 RM-RMS-154 RM-RMS-155 RM-RMS-151 RM-RMS-153 RM-RMS-152 RM-RMS-158 RM-RMS-156 b) Surry Radwaste Facility reports valid unexpected readings on any of the following monitors have increased by a factor of 1000:

Control Room

.. l RRM-121

Chemistry I

RRM-122 Laboratory

Local Control I

RRM-129 Panel

Bitumen Control I

RRM-130 Room I

I I

I REVISION 38 PAGE 20 of 38 CLASSIFICATION ALERT

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT 1

CONDITION/APPLICABILITY

4.

Effluent release GREATER THAN 10 times ODCM allowable limit ALL CONDITIONS (TAB E)

PAGE RADIOACTIVITY EVENT 21 of 38 INDICATION CLASSIFICATION a)

Any of the following monitors ALERT indicate valid readings above specified value for GREATER THAN 15 minutes:

Vent Vent Kaman RM-VG-131 GREATER THAN 2.84 x 105 µCi/sec

Process Vent Kaman RM-GW-130 GREATER THAN 1.7 x 107 µCi/sec

Discharge Tunnel RM-SW-120 or

-220 GREATER THAN 3.3 x 105 cpm b)

HP assessment (sample results or dose projections) indicates GREATER THAN.. 10 times ODCM allowable 1 i mi t

.D.R c)

Surry Radwaste Facility Monitor GREATER THAN 10 times ODCM allowable limit as determined by HP:

RRM-101: Ventilation Stack Noble

* * ** G*a-s*-mon*i-to-r

.D.R RRM-131: Liquid Effluent Monitor

NUMBER EPIP-1.01 ATTACHMENT 1

ATTACHMENT TITLE EMERGENCY ACTION LEVEL TABLE (TAB U RADIOACTIVITY EVENT REVISION 38 PAGE 22 of 38 CONDITION/APPLICABILITY INDICATION CLASS I FI CATION NOTIFICATION OF UNUSUAL EVENT

5.

Effluent release GREATER THAN ODCM allowable limit ALL CONDITIONS a)

Any of the following monitors indicate valid readings above specified value for GREATER THAN one hour:

Vent Vent Kaman RM-VG-131 GREATER THAN 2.84 x 104 µCi/sec

Process Vent Kaman RM-GW-130 GREATER THAN 1.7 x 106 µCi/sec

Discharge Tunnel RM-SW-120 or

-220 GREATER THAN 3.3 x 104 cpm b)

HP assessment (sample results or dose projections) indicate GREATER THAN 100% ODCM allowable 1 imit c)

Surry Radwaste Facility Monitor GREATER THAN 100% ODCM allowable limit as determined by HP:

-* ***RRM-*t{H-:

Venti1*a*tiDn *Stack Noble Gas monitor

.QR RRM-131: Liquid Effluent Monitor

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB G)

PAGE LOSS OF SECONDARY COOLANT 1

CONDITION/APPLICABILITY

1.

Major Secondary line break with Primary to Secondary leakage GREATER THAN 50 gpm and fuel damage indicated ABOVE CSD CONDITION 23 of 38 INDICATION

Uncontrolled loss of secondary coolant - IN PROGRESS CLASSIFICATION SITE AREA EMERGENCY AND RCS specific activity

> 300 µCi/gm D.E. I-131

.QR High Range Letdown Radiation Monitor on affected pathway 1 -CH - RM -118

2-CH-RM-218:

> 7.0 x 106 cpm

Condenser Air Ejector Radiation Monitor on affected pathway 1-SV-RM-111, 2-SV-RM-211:

> 1 x 107 cpm

.QR Vent Vent Kaman Monitor I RM-VG-131 > 1.1 x 107 µCi/sec

.QR Steam Generator Slowdown Radiation Monitor on affected pathway 1-SS-RM-112 or -113, 2-SS-RM-212 or -213:

GREATER THAN 1 x 107 cpm

.QR Main Steam Line High Range Radiation Monitor on affected pathway RM-RI-MS-124 or

-224 RM-RI-MS-125 or

-225 RM-RI-MS-126 or

-226 GREATER THAN 1.94 mR/hr

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT (TAB G)

PAGE LOSS OF SECONDARY COOLANT 1

CONDITION/APPLICABILITY

2.

Major Secondary line break with Primary to Secondary leakage GREATER THAN 10 gpm ABOVE CSD CONDITION

3.

Major Secondary line break ABOVE CSD CONDITION INDICATION a) Uncontrolled loss of secondary coolant -

IN PROGRESS b) Condenser Air Ejector Monitor 1 -S V - RM -111.

2-SV-RM-211:

GREATER THAN 1 x 107 cpm Vent Vent Kaman Monitor RM-VG-131 GREATER THAN 2.84 x 105 µCi/sec 24 of 38 CLASSIFICATION ALERT Steam Generator Blowdown Radiation Monitor on affected pathway 1-SS-RM-112 or -113, 2-SS-RM-212 or -213:

GREATER THAN 1 x 107 cpm Uncontrolled loss of secondary coolant - IN PROGRESS NOTIFICATION OF UNUSUAL EVENT

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 ATTACHMENT 1

AB I ITV

1.

Loss of offsite and onsite AC power.for more than 15 minutes ALL CONDITIONS (TAB H)

ELECTRICAL FAILURE The following conditions exist for GREATER THAN 15 minutes:

Offsite power to unit specific Transfer Buses PAGE

?S of :rn C A SITE AREA EMERGENCY-(Unit 1: D & F; Unit 2: E & F) -

NOT AVAILABLE

Station Service Buses A, B, & C - Of-ENERGIZED A1iQ

Emergency Buses H & J -

DE-EN ERG I ZED CAUTION:

EAL A.2 is duplicated below for cross-reference/comparison to EAL H.2 on the following page:

Loss of Function needed for unit HSD condition ABOVE CSD CONDITION a) Inability to attain the minimum required heat sink as indicated by loss of the following:

Main Feedwater System A1iQ

Auxiliary Feedwater A1iQ SITE AREA EMERGENCY

Auxiliary Feedwater Crosstie

.QR b) Loss of High Head flowpath as indicated by loss of the following:

Normal Charging System AND

High Head SI System

NUMBER EPIP-1.01 ATTACHMENT 1

ATTACHMENT TITLE EMERGENCY ACTION LEVEL TABLE (TAB H)

REVISION 38 PAGE 26 of 38 CONDITION/APPLICABILITY 2..

Loss of all offsite and ons ite AC power ALL CONDITIONS

3.

Loss of offsite power or onsite AC power capability ALL CONDITIONS ELECTRICAL FAILURE INDICATION CLASSIFICATION

Offsite power to unit ALERT specific Transfer Buses (Unit 1: D & F: Unit 2: E & F) -

NOT AVAILABLE

Station Service Buses A, B, & C - DE-ENERGIZED

.A..N..D.

Emergency Buses H & J -

DE-EN ERG I ZED

Offsite power to unit NOTIFICATION OF specific Transfer Buses UNUSUAL EVENT (Unit 1: D & F: Unit 2: E & F) -

NOT AVAILABLE Unit Main Generator and both Emergency Diesel Generators -

OUT OF SERVICE

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 AT1"ACHMENT 1

CONDITION/APPLICABILITY

4.

Loss of all onsite DC power for GREATER THAN 15 minutes ALL CONDITIONS

5.

Loss of all onsite DC power ALL CONDITIONS (TAB H)

ELECTRICAL FAILURE INDICATION The following conditions exist for GREATER THAN 15 minutes:

All Station Battery voltmeters - ZERO (0) VOLTS

No light indication available to Reserve Station SerVice Breakers 1501, 15El and 15Fl PAGE 27 of 38 CLASSIFICATION SITE AREA EMERGENCY

All Station Battery ALERT voltmeters - ZERO (0) VOLTS

No light indication available to Reserve Station Service Breakers 1501, 15El, and 15Fl

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ATTACHMENT 1

CONDITION/APPLICABILITY

1.

Fire resulting in degradation of safety* systems ABOVE CSD CONDITION

2.

Fire potentially affecting station safety systems ABOVE CSD CONDITION

3.

Fire lasting GREATER THAN 10 minutes ALL CONDITIONS I i ACTION LEVEL TABLE (TAB I)

FIRE INDICATION

Fire which causes major degradation o.f a safety system function required for protection of the public

Affected systems are caused NOT to be operable as defined by T.S. 1.0.D and T.S. 3.0.2 Fire which has potential for causing a safety system NOT to be operable as defined by T.S. 1.0.D and and T.S. 3.0.2 38 PAGE 28 of 38 CLASSIFICATION SITE AREA EMERGENCY ALERT Fire in the Protected Area NOTIFICATION OF or Switchyard which is UNUSUAL EVENT not under control within 10 minutes after Fire Brigade -

DISPATCHED

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 AT'fACHMENT 1

CONDITION/APPLICABILITY

1.

Loss of Station physical control ALL CONDITIONS

2.

Imminent loss of physical Station control ALL CONDITIONS

3.

Ongoing Security compromise ALL CONDITIONS

4.

Bomb potentially affecting

station safety systems ALL CONDITIONS

5.

Security threat, unauthorized attempted entry, or attempted sabotage ALL CONDITIONS (TAB J)

PAGE SECURITY EVENT 29 of 38 INDICATION CLASSIFICATION

Shift Supervisor has been GENERAL informed that the Security EMERGENCY force has been neutralized by attack, resulting in loss of physical control of station Shift Supervisor has been informed of intrusion into one or more Vital Areas which are occupied or controlled by an aggressor Supervisor Security Shift has notified the Shift Supervisor of imminent intrusion into a Vital Area Supervisor Security Shift has notified the Shift Supervisor of a confirmed un-neutralized intrusion into the Protected Area Shift Supervisor notified of a verified bomb discovered on or near a safety related system

---Sup*ervi sor--Se*cur; ty **Stiift has initiated applicable Security Contingency Plan Implementing Procedure SITE AREA EMERGENCY ALERT ALERT NOTIFICATION OF UNUSUAL EVENT

NUMBER ATTACHMENT TITLE EPIP-1.01 EMERGENCY ACTION LEVEL TABLE AHACHMENT 1

CONDITION/APPLICABILITY

6.

Bomb threat or discovery ALL CONDITIONS (TAB J)

SECURITY EVENT INDICATION

Shift Supervisor notified of a bona fide bomb threat Shift Supervisor notified of bomb discovery within the Protected Area REVISION 38 PAGE 30 of 38 CLASSIFICATION NOTIFICATION OF UNUSUAL EVENT

i.

NUMBER ATTACHMENT TITLE EPIP-1.01 EMERGENCY ACTION LEVEL TABLE AT*TACHMENT (TAB K)

HAZARD TO STATION OPERATION 1

CONDITION/APPLICABILITY INDICATION

1.

Aircraft damage to vital pl ant systems ABOVE CSD CONDITION

2.

Aircraft crash on the facility ALL CONDITIONS

3.

Aircraft crash or unusual aircraft activity ALL CONDITIONS

4.

Severe explosive damage ABOVE CSD CONDITION

5.

Explosion damage to facility ALL CONDITIO-NS

6.

Onsite explosion ALL CONDITIONS Aircraft crash adversely affects vital structures by impact or fire

Aircraft crash within the Protected Area or Switchyard

Confirmed notification of aircraft crash within the site boundary Unusual aircraft activity in the vicinity of the site as determined by the Shift Supervisor or Supervisor Security Shift Explosion which results.

in severe degradation of any systems required for safe shutdown Unplanned explosion resulting in damage to plant structure

* * * **** or-eq-lt'i pment--t:hat **affects plant operations Confirmed report of unplanned explosion within Protected Area or Switchya rd REVISION 38 PAGE 31 of 38 CLASS I FI CATION SITE AREA.

EMERGENCY ALERT NOTIFICATION OF UNUSUAL EVENT SITE AREA EMERGENCY ALERT NOTIFICATION OF UNUSUAL EVENT

NUMBER ATTACHMENT TITLE EPIP-1.01 EMERGENCY ACTION LEVEL TABLE ATTACHMENT (TAB K)

HAZARD TO STATION OPERATION 1

CONDITION/APPLICABILITY

7.

Entry of toxic or flammable gases or liquids into plant vital areas other than the Control Room ABOVE CSD CONDITION

8.

Entry of toxic or flammable gases or liquids into plant facility ALL CONDITIONS

9.

Onsite or nearsite release of toxic or flammable liquids or gases ALL CONDITIONS INDICATION

Uncontrolled release of toxic or flammable agents into Vital Areas

Evacuation of Vital Area other than Control Room - REQUIRED Loss of a safety system function required for protection of the public Uncontrolled release of toxic or flammable agent which causes:

Evacuation of personnel from plant areas AND

Safety related equipment to be rendered inoperable Unplanned release of toxic or flammable agents which may affect safety of station personnel or equipment REVISION 38 PAGE 32 of 38 CLASS I FI CATION SITE AREA EMERGENCY ALERT NOTIFICATION OF UNUSUAL EVENT

NUMBER EPIP-1.01 AT'TACHMENT 1

CONDITION/APPLICABILITY

10. Severe missile damage to safety systems ABOVE CSD CONDITION

11. Missile damage to safety related equipment or structures ABOVE CSD CONDITION

12. Turbine failure with penetration POWER

13. Turbine rotating component failure with no casing penetration POWER & STARTUP ATTACHMENT TITLE EMERGENCY ACTION LEVEL TABLE (TAB K)

HAZARD TO STATION OPERATION INDICATION Missile impact causing severe degradation of safety systems required for unit shutdown Notification of missile impact causing damage to safety related equipment or structures Failure of turbine/

generator rotating equipment resulting in casing penetration Failure of turbine/*

generator rotating component resulting in unit trip REVISION 38 PAGE 33 of 38 CLASS I FI CATION SITE AREA EMERGENCY ALERT ALERT NOTIFICATION OF UNUSUAL EVENT

NUMBER ATTACHMENT TITLE EPIP-1.01 EMERGENCY ACTION LEVEL TABLE ArTACHMENT 1

CONDITION/APPLICABilITY

1.

Earthquake GREATER THAN DBE levels ABOVE CSD CONDITION

2.

Earthquake GREATER THAN QBE levels ALL CONDITIONS

3.

Earthquake detected ALL CONDITIONS (TAB L)

NATURAL EVENTS INDICATION

Earthquake which activates the Event Alarm on the Strong Motion Accelerograph

Safety related systems are significantly degraded by earthquake AP-37.00, SEISMIC EVENT, calculations indicate horizontal motion of 0.15g or GREATER

Confirmed earthquake which activates Event Alarm on the Strong Motion Accelerograph

Safety related equipment is rendered inoperable by earthquake AP-37.00, SEISMIC EVENT, calculations indicate horizontal motion of 0.07g or GREATER Confirmed earthquake which activates the Event Alarm on the Strong Motion Accelerograph REVIS ION 38 PAGE 34 of 38 CLASSIFICATION SITE AREA EMERGENCY ALERT NOTIFICATION OF UNUSUAL EVENT

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 AT*TACHMENT 1

CONDITIONS/APPLICABILITY

4.

Tornado striking facility ALL CONDITIONS

5.

Tornado within Protected Area or Switchyard ALL CONDITIONS

6.

Sustained winds above Design Basis Conditions (105 MPH)

ALL CONDITIONS

7.

Hurricane force winds occurring or projected onsite within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ALL CONDITIONS

8.

Hurricane force winds projected onsite within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ALL CONDIT-IONS (TAB L)

PAGE NATURAL EVENTS 35 of 38 INDICATION CLASSIFICATION Tornado visually detected ALERT striking structures within the Protected Area or Switchyard Tornado visually detected within Protected Area or Switchyard 15-minute average wind speed exceeds 105 mph

15-minute average wind speed exceeds 73 mph

.QR Sustained hurricane force winds (GREATER THAN 73 mph) projected onsite within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

"Inland High Wind Warning for Hurricane Force Winds" in effect for Surry County Sustained hurricane force winds (GREATER THAN 73 mph) projected onsite within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months NOTIFICATION OF UNUSUAL EVENT SITE AREA EMERGENCY ALERT NOTIFICATION OF UNUSUAL EVENT

NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 38 AHACHMENT 1

9.

CONDITION/APPLICABILITY Flood or low water level above design levels ALL CONDITIONS

10.

Flood or low water level near design levels ALL CONDITIONS

11. Flood or low water level ALL CONDITIONS (TAB L)

NATURAL EVENTS INDICATION

Flood in the James River - GREATER THAN

+27 feet MSL (station operating level)

Water level in the James River - LESS THAN

-9 feet MSL as indicated by loss of*tmergency SW Pump suction PAGE 36 of 38 CLASSIFICATION SITE AREA EMERGENCY

Flood in the James ALERT River - GREATER THAN

+21 feet MSL (Emergency Service Water Pump House entrance is at +21 1/6 feet) but LESS THAN +27 feet MSL (Site Area Emergency criteria)

.QR Water level in Surry Power Station Intake Canal - LESS THAN

+23 1/2 feet and decreasing

Flood in the James NOTIFICATION OF River - GREATER THAN UNUSUAL EVENT

+12 feet MSL (CW pump motors and entrance to the CW pump pits are at

+12 1/2 feet MSL) but LESS THAN +21 feet MSL (Alert

--criteria)

Water level in Surry Power Station Intake Canal (CW-LI-101, -201)

- LESS THAN +23 1/2 feet and NOT increasing

NUMBER ATTACHMENT TITLE EPIP-1.01 EMERGENCY ACTION LEVEL TABLE Al'TACHMENT (TAB M)

MISCELLANEOUS ABNORMAL EVENTS 1

CONDITION/APPLICABILITY

1.

Any major internal or external event which singly or in combination cause massive damage to station facilities or may warrant evacuation of the public ALL CONDITIONS

2.

Station conditions which may warrant notification of the public near the site ALL CONDITIONS

3.

Station conditions which have the potential to degrade or are actually degrading the level of safety of the station ALL CONDITIONS INDICATION Shift Supervisor/

Station Emergency Manager judgement Shift Supervisor/

Station Emerg~ncy Manager judgement REVISION 38 PAGE 37 of 38 CLASS I FI CATION GENERAL EMERGENCY SITE AREA EMERGENCY ALERT

NUMBER ATTACHMENT TITLE EPIP-1.01 EMERGENCY ACTION LEVEL TABLE ATTACHMENT (TAB M)

MISCELLANEOUS ABNORMAL EVENTS 1

CONDITION/APPLICABILITY

4.

Station conditions which warrant increased awareness of state and/

or 1 oca 1 authorities ALL CONDITIONS INDICATION Shift supervisor judgment that any of the following exist:

Unit shutdown is other than a controlled shutdown Unit is in an uncontrolled condition dur~ng operation OR A condition exists which has the potential for escalation and, therefore, warrants notification REVISION 38 PAGE 38 of 38 CLASSIFICATION NOTIFICATION OF UNUSUAL EVENT

I:.-.

NUMBER EPIP-3.02 PURPOSE PROCEDURE TITLE ACTIVATION OF TECHNICAL SUPPORT CENTER (With 15 Attachments)

Provide guidance to TSC personnel.

ENTRY CONDITIONS Any one of the following:

REVISION 20 PAGE I of 3 I. Declaration of an Alert, Site Area Emergency or General Emergency.

2. Entry from another EPIP.

3. Direction by the Station Emergency Manager.

APPROVAL RECOMMENDED SNSOC APPROVAL APPROVAL EFFECTIVE DATE DATE

'"3-7-'!i:)

~{,--tl~~

o;;7 If~ ~Jr;_Q_

CHAIRMAN SNSOC STATION MANAGER Form No. 723758(Apr 91)

NUMBER PROCEDURE TITLE REVISION EPIP-3.02 ACTIVATION OF TECHNICAL SUPPORT CENTER 20 STEP PAGE 2 of 3 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE:

The first person to report to the TSC should implement this procedure and then give it to the Emergency Administrative Director upon his/her arrival.

1 INITIATE PROCEDURE:

By:

Date:

Time:

2 GIVE PERSONNEL BADGE NUMBERS TO SECURITY FOR ACCOUNTABILITY USING SEQUENTIAL BADGE LIST 3 SET UP TSC EQUIPMENT USING ATTACHMENT 2 4 INITIATE ENTRY/EXIT LOG USING ATTACHMENT 1 NOTE:

Some of the directors may be in the Control Room with the SEM.

Minimum staff positions shown on the facility staffing board must be filled prior to TSC activation.

5 DETERMINE STATUS OF MINIMUM REQUIRED TSC STAFF POSITIONS 6 NOTIFY SEM OF TSC STAFFING AND EQUIPMENT STATUS

NUMBER PROCEDURE TITLE REVISION EPIP-3.02 ACTIVATION OF TECHNICAL SUPPORT CENTER 20 STEP ACTION/EXPECTED RESPONSE 7 WHEN SEM ANNOUNCES THAT THE TSC IS DEACTIVATED, THEN SECURE TSC:

a) Return TSC to original status using Attachment 3 b) Get completed Attachments~

Attachment 2, Set-up TSC

Attachment 3, Secure TSC

Attachment 5, TSC Resource Request Log

Attachment 13, Data Sheet for Injured Persons

Attachment 14, Plant Announcements

Attachment 15, Shift Rotation Schedule 8 TERMINATE EPIP-3.02:

Give completed EPIP-3.02, forms and other applicable records to the Emergency Procedures Coordinator

Completed by: -------

Date: ----

Time: ----

-END-PAGE 3 of 3 RESPONSE NOT OBTAINED

NUMBER ATTACHMENT TITLE REVISION EPIP-3.02 TSC ENTRY AND EXIT LOG 20 ATTACHMENT PAGE 1

1 of 1 Enter name, badge number and time of arrival of personnel in the appropriate columns below.

As personnel exit the TSC, enter departure time in the far right column. New line entries should be made for returing personnel. Continue this log on additional pages as required.

NAME BADGE#

TIME IN TIME OUT (use 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months time)

Logkeeper's Name: ----------

Page_ of_

Date: ----

NUMBER ATTACHMENT TITLE REVISION EPIP-3.02 SET-UP TSC 20 ATTACHMENT PAGE 2

1 of 3

1.

Secure blast door to Unit 1 alleyway.

2.

Distribute supplies from TSC cabinet {refer to diagram on page 3):

a.

Emergency procedure binders.

{Binders are marked according to emergency positions/teams.)

b.

Contents of emergency folders.

{Folders are marked according to emergency positions/teams.)

c.

Dominion Resources Telephone Directory.

{Emergency Administrative Director, Emergency Operations Director, Emergency Procedures Coordinator, Radiological Assessment Director and Emergency Communicator Office.)

3.

Set-up equipment:

a.

Turn public address system "on" using the power switch on the BOGEN amplifier in the Computer Room telephone cabinet {See diagram on page 3).

b.

Adjust brightness on ERFCS terminal screens.

c.

Adjust clock time to synchronize with ERFCS time display.

d.

Start P-250 Alarm and Utility printers.

{Ask OSC for assistance from Instrument Technician if unable to start.)

4.

Check equipment:

a.

Verify telecopier tur.ned on and check paper level.

b.

Verify photocopier turned on and check paper level.

c.

Verify aperture card reader/printer on.

{Warm up if necessary.)

d.

Verify PBX system is in service by checking sample of telephones.

e.

Verify "Normal" light on radiation monitors lit.

NUMBER ATTACHMENT TITLE EPIP-3.02 SET-UP TSC ATTACHMENT 2

5.

Record discrepancies and efforts taken to resolve them below:

6.

Close out Attachment 2:

Completed by:----------

Date:

Time:

REVISION 20 PAGE 2 of 3

NUMBER EPIP-3.02 ATTACHMENT

'2 TELEPHCl\\lE CABINET BOGEN AMPLIFIER SWITCH ATTACHMENT TITLE SET-UP TSC TECHNICAL SUPPORT CENTER PROGRAMMER NRC COMPUTER ~%

RXM D E§ EADa LEGEND:

EMD: EMERGENCY MAINTENANCE DIRECTOR RAD: RADIOLOGICAL ASSESSMENT DIRECTOR EPC: EMERGENCY PROCEDURES COORDINATOR EC:

EMERGENCY COMMUNICATOR SEM: STATION EMERGENCY MANAGER EOD: EMERGENCY OPERATIONS DIRECTOR ETD: EMERGENCY TECHNICAL DIRECTOR EAD: EMERGENCY ADMINISTRATIVE DIRECTOR REVISION 20 PAGE 3 of 3 DCSE ASSESSMENT TEAM DCSE ASSESSMENT TEAM OPERATIONS SUPPORT

&EC TECHNICAL SUPPORT TEAM C=:l C:J TSC LIBRARY

NUMBER ATTACHMENT TITLE REVISION EPIP-3.02 SECURE TSC 20 ATTACHMENT PAGE 3

1 of 1

1.

Restock procedure sets and emergency folders.

2.

Verify Operations has realigned ventilation system to normal mode in accordance with O-OP-VS-007, TECHNICAL SUPPORT CENTER VENTILATION.

3.

Open blast door to Unit 1 alleyway.

4.

Return (five) Dominion Resources Telephone Directories to TSC Cabinet.

5.

Turn off P-250 Alarm and Utility printers.

6.

Reduce brightness on ERFCS terminal screens.

7.

Turn public address system switch "off" using the power switch on the BOGEN amplifier in the Computer Room telephone cabinet (see diagram on, page 3).

8.

IE seal on TSC Emergency Kit broken, THEN notify Radiological Protection Department that O-HSP-EP-001, EMERGENCY PLAN RADIATION INSTRUMENTS AND EMERGENCY KITS INSPECTION, must be performed.

9.

Clean status boards and maps.

10.

Initiate work requests on any equipment malfunctions.

11.

Record any discrepancies and efforts taken to resolve them:

12.

Clo~e out Attachment 3:

Completed by:

Date:

Time:

NUMBER ATTACHMENT TITLE REVISION EPIP-3.02 EMERGENCY ADMINISTRATIVE DIRECTOR GUIDELINE 20 ATTACHMENT PAGE 4

1 of 2

1.

Verify organization:

a.

Administrative Support Team:

Administrative Support Team Leader TSC Recorder Clerks Safety/Loss Prevention Representative (in OSC)

b.

Security Team:

Security Shift Supervisor (Team Leader)

Security Officers Security Control System Operators Administrative Security Officers

2.

Assist in logistics of TSC activation and operation.

3. Advise SEM on fire protection, security, administrative, logistical support and medical response/first aid activities.

4.

Provide clerical and records support, including operating telecopier for sending messages provided by Emergency Communicators.

5.

Ensure TSC Logkeeper maintains chronology of key events, including status changes, management decisions in response to event assessment, etc.

6.

Ensure TSC accountability is maintained.

7.

Direct Security Team on:

Personnel Accountability Access Control LEOF Activation Liaison with Local Law Enforcement Agencies (LLEAs)

8.

Keep Security Team Leader informed about status of event, radiological conditions, potential for escalation, etc.

9. lE Security Officers at traffic control radiological

concerns, THEN ensure LLEAs Services (DES) liaison at LEOF are advised.

points are relocated due to and Department of Emergency

10. Periodically verify TSC at positive pressure as indicated on pressure gauge when ventilation system is operating in Emergency Mode.

11. Coordinate acquisition of equipment, supplies and personnel. Offsite support should be coordinated through the LEOF.

Use EPIP-3.02,, TSC RESOURCE REQUEST LOG, to track status.

NUMBER ATTACHMENT TITLE REVISION EPIP-3.02 EMERGENCY ADMINISTRATIVE DIRECTOR GUIDELINE 20 ATTACHMENT PAGE 4

2 of 2

12. Coordinate waiver of Nuclear Power Station General Employee Training with LEOF Services Coordinator for offsite agencies called in to assist in emergency response.

13. Keep station personnel informed about the status of the event and their expected actions using Instant News and maintaining contact with non-emergency response facility emergency assembly areas. Refer to Section 2, Emergency Assembly Areas, of the Emergency Telephone Directory for a list of emergency assembly areas and phone numbers.

14. Get information regarding any injury and ensure it is forwarded to the LEOF.

Use EPIP-3.02, Attachment 13, DATA SHEET FOR INJURED PERSONS.

15. Make event declaration announcements using the Gai-Tronics system (Channels 1,

2, 3 or 4) when directed by the Station Emergency Manager. ( SEM).

Use EPIP-3.02, Attachment 14, PLANT ANNOUNCEMENTS.

16. Ensure arrangements are made for relief of personnel under your cognizance:

Administrative Support Team Security Team Fire Team First Aid Team

17. Coordinate station shift relief:

a.

Determine relief requirements for the. following:

1.

Each position posted on TSC Staffing Board (unless directed otherwise. by SEM)

2.

Support staff requirements from Emergency Directors

b.

Identify standby personnel (personnel who are available but not filling positions as primary responders)

c. Develop shift relief schedule:

Consider implementation of a split shift turnover (stagger turnover times by discipline)

Use EPIP-3.02, Attachment 15, SHIFT ROTATION SCHEDULE

d.

Ask SEM to approve schedule

e.

Give instructions to standby personnel who are not presently needed (e.g., send home or remain on standby)

f.

Notify refief shifts:

1. Consider asking LEOF for assistance in notification

2.

Notify relief personnel of the following:

Reporting time Ingress route to station Reporting location

NUMBER ATTACHMENT TITLE REVISION EPIP-3.02 TSC RESOURCE REQUEST LOG 20 ATTACHMENT PAGE 5

1 of 1 I ITEM #:

I NAME OF ITEM/SERVICE:

REQUESTED BY:

I SOURCE/CONTACT:

STATUS ON I

(Date / Time)

STATUS ON I

(Date/ Time)

STATUS ON I

(Date/ Time)

'ITEM #:

I NAME OF ITEM/SERVICE:

REQUESTED BY:

I SOURCE/CONTACT:

STATUS ON I

(Date/ Time)

STATUS ON I

(Date/ Time)

STATUS ON I

(Date/ Time)

I ITEM #:

I NAME OF ITEM/SERVICE:

REQUESTED BY:

I SOURCE/CONTACT:

STATUS ON I

(Date/ Time)

STATUS ON I

(Date/ Time)

STATUS ON I

(Date/ Time)

NUMBER ATTACHMENT TITLE REVISION EPIP-3.02 EMERGENCY TECHNICAL DIRECTOR GUIDELINE 20 ATTACHMENT PAGE 6

1 of 1

1.

Verify organization (Technical Support Team):

a.

Technical Support Team Leader

b.

Operational Advisor

c.

Reactor Engineer

d.

Mechanical Engineer

e.

Electrical Engineer

2.

Notify Westinghouse (NSSS Vendor) point-of-contact.

Refer to Emergency Telephone Directory.

3.

Use ERFCS to assess emergency conditions. Refer to ERFCS User Reference Guide as necessary.

4.

Determine whether any data collect,on needs exist beyond those normally satisfied by the 150-minute capacity ERFCS Historical File, which is normally activated when a trip signal is received.

5.

Analyze and develop solutions to engineering and reactor physics problems.

6.

Assist in development of procedures.

7.

Interface with NRC and aid in resolution of questions concerning licensing requirements.

8.

Ensure arrangements are made for relief of Technical Support Team.

NUMBER ATTACHMENT TITLE REVISION EPIP-3.02 EMERGENCY OPERATIONS DIRECTOR GUIDELINE 20 ATTACHMENT PAGE 7

1 of 2

1.

Establish communications with Control Room.

Get operational status update.

Provide oversight and direction on response activities.

2.

Consider dispatching an individual to monitor Emergency Operations Communications Network in OSC and to interface with the OSC Director on operational matters.

The TSC ventilation system is designed to automatically align for emergency operation when Safety Injection (SI) occurs.

The Control Panel is located on the 27' level of the Service Building behind the Lunch Room.

The top half (labeled MONITOR ROOM) is dedicated to the TSC Emergency Ventilation System.

3.

Verify TSC on emergency ventilation (unless determined not necessary):

a) b)

c) 1£ SI occurred, THEN direct verification of ventilation system alignment using O-OP-VS-007, TECHNICAL SUPPORT CENTER VENTILATION (Section 5.2)

Dispatch individual to verify indications on TSC Ventilation Control Panel:

A0D-VS-VS-l32A (Emergency Supply Fan Filter Inlet) - OPEN AOD-VS-VS-132B (Emergency Supply Fan Outlet) - OPEN l-VS-F-150 (TSC Emergency Supply Fan) - ON l-VS-AC-150A (TSC Monitor Room Air Handling Unit) - ON l-VS-F-151 (Return Air Fan) - ON 1£ manual alignment of TSC ventilation for emergency operations is

required, THEN direct performance of O-OP-VS-007, TECHNICAL SUPPORT CENTER VENTILATION (Section 5.2).

WHEN TSC ventilation can be returned to normal alignment, THEN direct performance of O-OP-VS-007, TECHNICAL SUPPORT CENTER VENTILATION (Section 5.3).

4.

Verify avai~ability of standby-Operations personnel.

Request additional personnel as required. Consider staging a share of Operations personnel in the OSC to support damage control response activities.

5.

Use ERFCS to access emergency conditions.

Refer to ERFCS User Reference Guide as necessary.

6.

Evaluate status of unaffected unit.

NUMBER ATTACHMENT TITLE REVISION EPIP-3.02 EMERGENCY OPERATIONS DIRECTOR GUIDELINE 20 ATTACHMENT PAGE 7

2 of 2

7.

Assess events for reportability.

8.

Provide status change data and recommendations to SEM.

9.

Assist in procedure development.

10.

Sound emergency alarms when necessary.

11.

Ensure arrangements are made for relief of:

a.

Control Room personnel (including on-shift STA)

b.

Standby Operations personnel

ATTACHMENT TITLE NUMBER EPIP-3.02 STATION EMERGENCY MANAGER GUIDELINE ATTACHMENT 8

1.

Verify emergency response organization:

a.

TSC staff (Emergency Administrative Director)

b.

Operations staff (Emergency Operations Director)

c.

OSC staff (Emergency Maintenance Director)

d.

HP and Chemistry (Radiological Assessment Director)

e.

Security staff (Emergency Administrative Director)

2.

Upon arrival at TSC:

a.

Complete turnover with interim SEM.

b.

Declare activation of facility to staff.

c.

Identify yourself as SEM.

d.

Provide initial status report/briefing.

3.

The following responsibilities may NOT be delegated:

a.

Classifying the emergency.

REVISION 20 PAGE 1 of 1.

b.

Notifying NRC, State and local governments of emergency status.

4.

c.

Recommending protective measures.

d.

Authorizing emergency exposure.

When the LEOF is activated:

a.

Transfer responsibility for notifying State and local governments of emergency status and recommending offsite protective measures to the Recovery Manager.

b.

Notify TSC staff that the above responsibilities have been transferred to the Recovery Manager.

5.

Ensure timely notifications are made to offsite authorities.

6.

Approve temporary procedures and changes as required. Procedures may be changed at the discretion of the SEM during emergency conditions.

7.

Use ERFCS to assess emergency conditions and response actions. Refer to ERFCS User Reference Guide..

8.

Periodically reference EPIP-1.01, EMERGENCY MANAGER CONTROLLING PROCEDURE, to-assess and manage the emergency.

9.

Ensure arrangements for relief of emergency response personnel through emergency directors.

10.

If TSC is determined to be uninhabitable, consult with RAD about relocation to alternate facilities, e.g., Control Room, ESGR.

NUMBER ATTACHMENT TITLE REVISION EPIP-3.02 20 ATTACHMENT EMERGENCY PROCEDURES COORDINATOR GUIDELINE PAGE 9

1 of 1

1.

Assist SEM in review and adherence to controlling procedures.

2.

Monitor Emergency Action Level entry conditions.

3.

Ensure procedures are initiated as required.

4.

Ensure SEM periodically updates TSC staff on:

a.

Emergency Status

b.

Mitigation goals and techniques

c.

Direction of overall response

5.

Ensure Emergency Communicators make periodic updates to offsite authorities.

6.

Track and hold completed procedures and logs until TSC deactivation.

7.

Collect procedures, ensure they are properly completed and made available for preparation of the Summary Report to the State, and ensure subsequent review by SNSOC. The Summary Report to the State is due within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of the declaration of a Notification of Unusual Event; or, 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months following termination of an Alert, Site Area Emergency or General Emergency.

NUMBER ATTACHMENT TITLE REVISION EPIP-3.02 RADIOLOGICAL ASSESSMENT DIRECTOR GUIDELINE 20 ATTACHMENT PAGE 10 1 of 2

1.

Direct Radiological Protection response using EPIP-4.01, RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE.

2.

Use ERFCS to assess emergency conditions. Refer to ERFCS User Reference Guide.

3.

Verify organization:

a.

Dose Assessment Team

b.

Offsite Monitoring Team

c.

Evacuation Monitoring Team

d.

Inplant Monitoring Team

e.

Onsite Monitoring Team

f.

Sample Analysis Team

g.

Personnel Monitoring and Decontamination Team

h.

Chemistry Team

4.

Direct activities of:

a.

b.

c.

d.

Radiation Protection Supervisor Dose Assessment Team Offsite Monitoring Teams Chemistry Team

5.

Consider sending an individual to OSC to monitor Radiological Protection Communications Network, keep OSC Director informed about radiological conditions, and brief Damage Control Teams.

6.

WHEN LEOF is activated, THEN do the following:

a.

Direct Dose Assessment Team Leader to brief LEOF Radiological Assessment Coordinator (RAC).

b.

Transfer direction of Offsite Monitoring Teams to RAC.

c.

Ensure LEOF assumes HPN communications.

d.

Confer with RAC for consensus on accident type (to yield consistency in dose assessments).

7.

Determine release status and evaluate offsite dose assessment data.

8.

Periodically ~pdate thB SEM, JSC staff and Radiological Protection Communications Network:

Radiological status Dosimetry requirements Personal protective measures (i.e., restricted areas, areas requiring respiratory protection)

Emergency exposure KI administration

NUMBER ATTACHMENT TITLE REVISION EPIP-3.02 RADIOLOGICAL ASSESSMENT DIRECTOR GUIDELINE 20 ATTACHMENT PAGE 10 2 of 2

9.

Make recommendations for onsite and offsite protective measures to SEM.

10.

Ensure HP coverage or RWP available for damage control activities.

11.

Assist in development of procedures.

12.

Ensure relief available for Radiological Protection personnel.

NUMBER ATTACHMENT TITLE REVISION EPIP-3.02 20 ATTACHMENT EMERGENCY MAINTENANCE DIRECTOR GUIDELINE PAGE 11 1 of 1

1.

Verify organization:

Assistant Emergency Maintenance Director:

2.

Control emergency maintenance activities using EPIP-5.08, DAMAGE CONTROL GUIDELINE.

3.

Maintain communications with OSC.

4.

Keep Damage Control Task Status Board up-to-date.

5.

Periodically update SEM and TSC staff on emergency maintenance activities.

6.

Assist in procedure development.

7.

Ensure arrangements are made for relief of Assistant Emergency Maintenance Director.

NUMBER ATTACHMENT TITLE REVISION EPIP-3.02 GUIDELINES FOR EMERGENCY COMMUNICATORS 20 ATTACHMENT PAGE 12 1 of 1 NOTE:

The following ERFCS data groups list selected parameters for emergency situations.

Refer to ERFCS User Reference Guide for additional instruction as necessary.

1.

2.

3.

NUMBER 35 36 37 38 39 74 78 79 80 81 82 GROUP ERDSl-1 ERDSl-2 ERDS2-1 ERDS2-2 COMERDS-1 MIDAS-MET UNTl-PLNT UNT2-PLNT UNTl-RAD UNT2-RAD COMMON-RAD DESCRIPTION UNIT 1 EROS POINTS UNIT 1 EROS POINTS UNIT 2 EROS POINTS UNIT 2 ERDS POINTS COMMON EROS POINTS MIDAS MET INPUTS UNIT 1 EMERGENCY PLANT STATUS UNIT 2 EMERGENCY PLANT STATUS UNIT 1 CALCULATED RAD MONITORS UNIT 2 CALCULATED RAD MONITORS COMMON CALCULATED RAD MONITORS The ERFCS Emergency Communicator screens can be accessed by typing EMCOMM and pressing the grey button labeled LAST.

NRC Communicator:

Continue notifications IAW EPIP-2.02, NOTIFICATION OF NRC.

Use ERFCS to get plant parameter data.

lE the ERFCS fails, THEN get information from the Plant Status Communicator.

State and Local/LEOF Communicator:

Continue notifications IAW EPIP-2.01, NOTIFICATION OF STATE AND LOCAL GOVERNMENTS, until LEOF assumes this responsibility.

IE ERFCS fails, THEN get information from Plant Status Communicator.

Radiological information should be obtained from the Radiological Assessment Director or Dose Assessment Team.

Ensure completed message forms are transmitted to the LEOF and CERC (after activated) via telecopier. Ask for Administrative Support Team assistance if needed.

Maintain continuous communications with lEOF following transfer of responsibility for State and local notifications.

Plant Status Communicator:

Maintain TSC Parameter Status Board. Enter parameters of interest.

. IE ERFCS fails in the TSC, THEN get information from Control Room.

IF ERFCS is not available to the LEOF°, THEN establish a conference network to share information.

NUMBER ATTACHMENT TITLE REVISION EPIP-3.02 DATA SHEET FOR INJURED PERSONS 20 ATTACHMENT PAGE 13 I of I NAME OF INJURED PERSON:

EMPLOYER:

DATE/TIME OF INJURY:

DESCRIPTION OF EVENT:

SUMMARY

OF INJURIES:

EXPOSURE/CONTAMINATION INFORMATION:

TRANSPORT INFORMATION:

a.

Transported to:

b.

Mode of transport:

c.

Time departed station:

d.

Expected time of arrival at medical facility:

REMARKS:

NUMBER ATTACHMENT TITLE REVISION EPIP-3.02 PLANT ANNOUNCEMENTS 20 ATTACHMENT PAGE 14 1 of 1 CAUTION:

Gai-tronics Channel 5 broadcasts in the Control Room only.

NOTE:

Soundfog of the Emergency Alarm has to be coordinated with the Emergency Operations Director.

1.

2.

3.

Message content should be conveyed to the Control Room by the Emergency Operations Director because Gai-tronics announcements on Channels 1, 2, 3 and 4 are not broadcast in the Control Room.

Evacuation announcements are in EPIP-5.05, SITE EVACUATION.

Announcements should address the emergency classification, reason for the classification, status information and instructions for personnel.

Write out announcement below:

ATTENTION ALL PLANT PERSONNEL - ATTENTION ALL PLANT PERSONNEL...

HAS BEEN DECLARED DUE TO -------

( Emergency Classification)

Get approval:

Announcement approved by on (date/ time)

Make announcement:

a.

Read approved announcement using Gai-tronics.

b.

Note date/time announcement made:

NUMBER ATTACHMENT TITLE REVISION EPIP-3.02 SHIFT ROTATION SCHEDULE 20 ATTACHMENT PAGE 15 1 of 2 NOTE: The TSC shift relief complement is normally the full staff organization (positions listed below).

The Station Emergency Manager has the authority to modify this organization. Space is provided for Emergency Directors to establish additional support staff requirements, as desired.

FIRST SHIFT SECOND SHIFT EMERGENCY

RESPONSE

POSITION NAME NAME Station Emergency Manager Emergency Procedures Coordinator Emergency Operations Director NRC ENS Emergency Corrvnunicator TSC-to-LEOF* Communicator Plant Status Communicator Emergency Technical Director Technical Support Team Leader Electrical Engineer Mechanical Engineer Reactor Engineer Operational Advisor Emergency Maintenance Director Asst. Emergency Maintenance Director (continued on next page)

NUMBER ATTACHMENT TITLE REVISION EPIP-3.02 SHIFT ROTATION SCHEDULE 20 ATTACHMENT PAGE 15 2 of 2 FIRST SHIFT SECOND SHIFT EMERGENCY

RESPONSE

POSITION NAME NAME Radiological Assessment Director Dose Assessment Team Leader Dose Assessment Team Member Emergency Administrative Director Administrative Support Team Leader Administrative Support Team Clerk Administrative Support Team Clerk Administrative Support Team Clerk Technical Support Center Recorder ADDITIONAL/MISCELLANEOUS:

ML18151A623

Text

SUMMARY

RESPONSE

RESPONSE

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