Text

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EP II-4 Re Emergency Response Support Callout & EP II-5 Re Paging Emergency Response Personnel
	ML20076K413
Person / Time
Site:	Salem
Issue date:	07/26/1983
From:	; Public Service Enterprise Group
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML20076K404	List: ML20076K413;
References
	PROC-830726, NUDOCS 8309140330
	Download: ML20076K413 (65)
	v • d • e

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Figure 6-2-1

}))s EMERGENCY PLAN REVISION REQUEST FORM FIGURE 6-2.1

[)'9 ',

y SALEM GENERATING STATION MANUAL NO.

/d/

)

REVISION NO.

83-6 TO: b}

PLAN bk)

PTOCEDURES MANUAL b

TRAINING MANUAL REVISE YOUR COPY OF THE PLAN BY INSERTING THE ATTACHED SECTION(S) IN THE APPROPRIATE PLACE, AS SPECIFIED BELOW, AND DESTROYING THE OLD SECTION(S).

REVISIONS ARE IDENTIFIED BY A VERTICAL LINE IN THE RIGHT MARGIN.

Index - Vol. 1 and 2 EP II adds site support managers staff II minor changes based on EP II-4 revisions II new procedure EP IV - 111 )

) corrected signature page and includes vertical lines for EP IV - 302 )for revisions 6

-:d%

i

) \\

NOTE:

COMPLETE THE FOLLOWING INFORMATION AND RETURN THIS SHEET TO THE NUCLEAR EMERGENCY PLANNING ENGINEER, P.O. BOX 236, HANCOCKS BRIDGE, NEW JERSEY 08038.

MANUAL NO.

[0/

DATE THIS CHANGE ENTERED DATE THIS INFORMATION REVIEWED WITH SUBORDINATES:

SIGNATURE:

r309140330 830907 PDR ADOCK 05000272 F

PDR

SALEM CENERATING STATION EMERGENCY PLAN EMERGENCY PLAN PROCEDURES INDEX MAY 4 1983 SECTION I - ON-SITE PROCEDURES REv. so.

EP I-0 Accident Classification Guide......................

3 Part 1 Radiclogical Part 2 Operational Part 3 Fire / Natural / Security Part 4 Miscellaneous Flow Chart EP I-1 1

Notification of Unusual Event /Significant Event EP I-2 Alert 5

EP I-3 Site Area Emergency.

4 EP I-4 General Emergency.

4 EP I-5 Personnel Emergency.

4 EP I-6 Radioactive Spill.

I EP I-7 Station Fire I

EP I-8 Personnel Accountability 1

EP I-9 Search and Rescue Operations 1

E P I-10 Conducting an Inventory of Emergency Equipment I

EP I-al Commanications Equipment 1

ED I-12 Site Evacuation.

1 EP I-13 Post Accident Low 1

Pressure Inje: tion Monitoring.

EP I-14 Initiation of Recovery Operations.

I EP I-15 St able Ioda ne Thyroid Block ing 1

EP I-16 Recall of Evacuated Site Personnel I

EP I-17 Radiation Protection - Emergency Action 2

EP I-18 Operations Support Center Activation 1

EP I-19 Activation / Evacuation of the Techn2 cal Support Center.

I EP I-20 Notification of Emergency Support Staff.

1 0

SECTION II - 0FF-SITE PROCEDURES EP 11-1 Emergency Response Managet Preparation to Assume Responsabilittes.

EP II-2 Site Support 1

Manager Preparation to Assume Responsabilit aes EP 11-3 Radiological Support 1

Manager Preparation to Assume Responsibilitaes.

EP 11-4 1

Notification of Corporate Emergency Response Personnel EP II-5 2

Emergency Paging of Corporate Emergency Response Personnel EP II-6 Off-Site Administrative Support 2

EP !!-7 1

Testing of Emergency Procecure EP II-4 EP II-8 Emerge,ney Operat ions Fa cility Se t-Up.

O No. 101 U.S. NRC, Dir. of NRR Washington, D.C.

20555 Mr. S.A. Varga, Chie f, Ope r.

Reactors BR#1, Div. of Licensinc 1 of 3 Rev. 9 oce w - y

SECTION III - SECURITY EMERGENCY PROCEDURES n

R EV NT EP !!!-1 Opening of the Technical Support Center.

1 EP !!I-2 Opening of the Emergency Operettons Facility 2

EP III-3 Personnel Accountability 1

EP III-4 Site Evacuation - Security Support 1

EP III-5 Emergency vehicle Support........................

1 SECTION IV - RADI ATION PROTECTION / CHEMISTRY EMERGENCY PROCEDURES EP IV-101 TSC Initial Response 1

EP IV-102 control Room Initial Response.

1 EP IV-103 Control Point Initial Response 1

EP IV-104 TSC Evacuation 1

ES IV-105 Control Point and Equipment Evacuation 1

EP IV-100 ALARA Task Review and Emergency Esposure Authorization 1

EP IV-107 Radiation Monitor Evaluation 1

EP IV-108 Protective Action Recommendations.

2 EP IV-109 Plume Tracking by Helicopter 1

EP IV-110A Field Monitoring by TSC 2

EP IV-1108 Field Monitoring by EOF O

EP IV-III Effluent Dose Calculations 2

EP IV-112 Emergency Operations Facility - Radiological Assessment 0

EP IV-113 Computerized Dose Calculations 2

EP IV-13 4 Computerized Dose Calculations on Programmable Calculator.

O EP IV-115 Personnel and Vehicle Survey 1

EP IV-Il6 Fire Brigade Escort...........................

1 EP IV-117 Re-Entry Team Radiation Protection 1

EP IV-118 High Activity Sample Analysis.

2 EP IV-319 Personnel Decontamination........................

I EP IV-120 Equipment Decontamination.

1 EP IV-121 Containment Atmosphere Remote Sampling 1

EP IV-122 Emergency Staf fing Guide EP IV-201 Radiation Protection Senior Supervisor Response EP IV-202 Chemistry Senior Supervisor Response 1

EP IV-203 Administrative Assistant Response.

1 EP IV-204 Short Term Environmental Response.

1 EP IV-205 Material and Instruments Supervisor Response 1

EP IV-206 Dosimetry-Counting Room Supervisor Response...............

1 EP IV-207 Rad Waste Supervisor Response 1

EP IV-208 Dose Assessment - ALARA Supervisor Response.

1 s EP-IV-209'In-Plant Supervisor Response'.. '. '...

I EP IV-210 Procedures-Training Supervisor Pesponse.

1 EP IV-211 Radiation Protection Communications Guide................

1 EP IV-212 Radiation Protection Emergency Inventory Control 1

EP IV-301 Interim Post Accident Primary Coolant Sampling 2

EP IV-302 Emergency Sampling Procedure f or the Plant Vent 1

2 of 3 Rev. 9

h SECTION V - ENGINEERING DEPARTMENT EMERGENCY PROCEDURES REV. NE.

EP V-1 Notification of Engineering and Construction Department O

EP V-2 Corporate Engineering Support Manager Response (CHERC)

O EP V-3 Site Engineering Support Manager Response (EOF)

O EP V-4 Corporate Engineering Team Leader Response (CHERC)

O EP V-5 Corporate Quality Assurance Department Respor.se (CHERC) 0 EP V-6 Site Quality Assurance Department Response (EOF)

O EP V-7 Site Engineering Team Leader Response (TSC)

O EP V-8 Methods Department & Engineering Department Divisional Representatives Response (CHERC)

O SECTION VI - PLAN ADMINISTRATION EP VI-l Revision and Approval of Plans and Procedur s.

1 EP VI-2 Distribution of Plans and Procedures O

EP VI-3 Review of Plans and Procedures O

EP VI-4 Procedures Format O

EP VI-5 Conduct of Drills and Exercises I

SECTION VII - PUB' IC INFORM ATION E P VII-l Public Inf ormation Notification.

O EP VII-2 General Manager - Information Services Response.

O EP VII-3 Public Information Manager Response.

0 EP VII-4 Public Information Technical Liaison Response O

EP VII-5 Public Information Technical Assistant Response.

O EP VII-6 Internal Information O

EP VII-7 Media Relations.

0 EP VII-B Emergency News Center Activation /Pulbic Inf ormation Coordar.ator

Response

O ACDENDim Addendue 1 Master Phone List 4

FIGUSES Figure 1 (deleted)

Fagure 2 Cnemunications/ EOF Manning Board I

Fi gu re 3 operational Status Board O

Fi gu're 4 ' ' Pos t ' Acci' dent' RMS' As se's sment Data I

a..

Figure 5 Area / Process RMS Data O

Figure 6 Offsite Dose Summary O

Figure 7 (deleted)

Figure 8 (deleted)

Figure 9 (deleted) 3 of 3 Rev. 9

EP II-4 EMERGENCY PROCEDURE EP II-4 EMERGENCY RESPONSE SUPPORT CALLOUT l

Action Level This procedure shall be implemented for all events which have been classified as an Alert, Site Area Emergency or General Emergency.

Action Statements The Control Room /TSC Communicator shall:

1.

When directed by the Senior Shif t Supervisor / Emergency Duty Officer to initiate or activate the Emergency Response Support callout:

a.

For events classified as Alert, Site Area Emergency or General Emergency using Attachment 1 to this procedure, contact the Emergency Response Manager.

Read the Initial Contact Message form to the Emergency Response Manager.

Provide the Emergency Response Manager with a telephone number at whicn the Senior Shift Supervisor or Emergency Duty i

Officer may be reached, b.

For events classified as Site Area Emergencies, General Emergencies or if it has been decided to

. activate.the. Emergency:Opeations Faci.lity.for.an r

l Alert Event:

Contact the Load Dispatcher at (201) 430-5041, and use the following message:

i SGS Page 1 of 8 Rev. 3

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EP II-4 "This is the Communicator at Salem Generating Station.

Please contact the Emergency Response Support Managers."

The message is:

"This is a notification of an (Alert, Site Area Emergency, General Emergency).

Please report to the Emergency Operations Facility" (or other location if so' directed by the Senior Shift Supervisor / Emergency Duty Officer or Emergency Response Manager),

The Load Dispatcher shall:

1.

When contacted by the Communicator at Salem Generating station:

Log message to De given to support Managers on a.

Attac hment 2 (not included in all manuals) to this procedure.

D.

Contact the Support Managers listed on Attacnment 2 to this procedure.

During normal working hours use office pnone. numbers to contact Support Managers.

During off hours, weekends and company holidays use j.

home phone numbers to contact Support Managers.

l 1.

c.

.ci Tf ' unable't'o ' cont'ict one of' the' individuals listed

~

for a support Manager function using the office or home telephone number as directed in 1.b. above, implement procedure EP II-5, Paging Emergency Response Personnel.

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SGS Page 2 of 8 Rev. 3

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EP II-4 2.

Call the Communicator at Salem Generating Station at Newark ext. 8670 to report the status of the callout to the Senior Shif t Supervisor / Emergency Duty Of ficer.

3.

When contacted by a Support Manager, Technical Support Supervisor, or Team Leader with a request to page a member of their staff, implement procedure EP II-5

" Paging Emergency Response Personnel".

i The Technical Support Supervisor shall:

1.

Using Attachment 3 to this procedure:

a.

Contact a Technical Support Team Leader and instruct the person contacted to implement this procedure by making the calls shown in Attachment 4 to this procedure and then report to the Tech'nical Support Center (or other location if so directed by the Emergency Duty Of ficer).

5.

Contact an Operations Assessment (Core / Thermal / Hydraulics) Engineer and instruct the person contacted to report to the Technical Support Center (or other location if so directed by the Emergency Duty Officer).

The Technical Support Team Leader - TSC shall:

, 1.

,Using Attachment;.4 to,this procedure and, if-needed,-EP' II-5 (Paging of Emergency Response Personr.el), contact I

the Technical Support Team - TSC and instruct the l

persons contacted to report to the Technical Support l

Center (or as directed by the Technical Support Supervisor).

SGS Page 3 of 8 Re v.

3

EPII-4 The Emergency Response Manager shall:

1.

For emergencies classified as Alert events, discuss activation of the Emergency Operations Facility with the Senior Shif t Supervisor / Emergency Duty Of ficer.

2.

For emergencies classified as Site Area Emergencies or General Emergencies or if it is decided to activate the Emergency Operations Facility for an Alert event.

i

a. During normal working hours, using Attachment 5, contact the Support Managers and have them report to the Emergency Operations Facility.

These calls will also be made by the Load Dispatcher.

b. During off hours, report to the Emergency Operations Facility.

The Load Dispatcher will make all Support Manager calls.

The Site Support Manager shall:

1.

Using Attachment 6 to this procedure, activate Emergency Preparedness Support by contacting one representative.

If necessary, use Procedure EP II-5 (Paging of Emergency Response Personnel) for paging persons who cannot be reached at their office or home phone.

2.

Report to the Emergency Operations Facility (or as directed by the Emergency Response Manager).

l 3.

Implement procedure EP II-2.

l The Radiological Support Manager shall:

r,-

1.

Using Attachment 7 to this procedure, activate the Radiological Support Organization by contacting two representatives from Radiological Assessment Team #1.

If necessary, use procedure EP II-5 (Paging of Emergency Response Personnel) for paging persons who cannot be l

reached at their of fice or home phone.

SGS Page 4 of 8 Rev.

3.

EP II-4 a.

Instruct the persons contacted to implement this procedure by making the calls shown in Attachment 7 to this procedure and report to the Emergency Operations Facility (or as directed by the Emergency Response Manager).

2.

Report to the Emergency Operations Facility (or as directed by the Emergency Response Manager).

3.

Implement procedure EP II-3.

The Technical Support Manager shall:

1.

Using Attachment 8 to this procedure activate the Technical Support organization by contacting a Technical Support Team Leader - EOF, Licensing Support Team Leader, OA Team Leader, and Nuclear Fuel Team Leader.

If necessary, use procedure EP II-5 (Paging of Emergency Response Personnel) for paging persons who cannot be reached at their office or home phone.

Instruct the persons contacted to implement this a.

procedure by making the calls shown in Attachment 11 and 12 to this procedure and then report to the l

Emergency Operations Facility (or as directed by the Emergency Response Manager).

The Administrative Support Manager shall:

l 1.

Using Attachment 9 to this procedure activate the Admnistrative Support Organization by making the

_co,ntacts. listed.

a.

Instruct the persons contacted to report to the l

Emergency Operations Facility (or as directed by the Emergency Response Manager).

l j

SGS Page 5 of 8-Rev. 3

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EP II-4 2.

Report to the Emergency Operations Facility (or as directed by the Emergency Response Manager).

3.

Implement procedure EP II-6.

The Public Affairs Manager - Nuclear shallt 1.

Using Attachment 10 to this procedure activate the Public Affairs /Information Support organization by contacting a Public Information Manager and Public Affairs Technical Assistant and direct them to report the Emergency News Center.

I

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2.

Report to the Emergency Operations Facility (or as directed by the Emergency Response Manager).

3.

Implement procedure EP VII-1, Public Affairs Manager -

Nuclear Response.

The Public Information Manager shall:

1.

Using Attachment 10 to this procedure activate the Public Information Support organization by contacting a Public Information Technical Liaison and a Public Information Coordinator and direct them to report to the Emergency News Center.

2.

Report to the Emergency News Center (or as directed by the Public Af f airs Manager - Nuclear).

3.

Implement procedure EP VII-3, Public Information Manager tesponse..

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s SGS Page 6 of 8 Rev. 3 l

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EP II-4 Other Caergency Support Team Leaders shall:

1.

Using Attachment 11 or 12 to this procedure activate your organization by making the calls listed for your position.

a.

Instruct persons contacted to report to the Emergency Operations Facility (or as directed by the Emergency Response Manager).

2.

Report to the Emergency Operations Facility (or as directed by the Emergency Response Manager).

LIMITS ON__ AUTHORITY Personnel who have been assigned a responsibility to contact staff members shall be familiar with this procedure.

ATTACHMENTS Attachment 1 - Emergency Response Manager Callout Attachment 2 - Support Managers Callout - Load Dispatcher (not included in all manuals)

Attachment 3 - TSC Technical Support Leaders Callout Attachment 4 - TSC Technical Support Team Callout Attachment 5 - Support Managers Callout - ERM Attachment 6 - Emergency Preparedness Support Callout Attachment 7

Radiological Support Teams Callout Attachment 8 - EOF Technical Support Leader Callout Attachment 9 - Administrative Support Team Callout 0 - Public Affairs Support Team Callout

Attachment'll -DEOF Technical Support Team ~'Callou't

^

' 2 - Other Support Teams Callout SGS Page 7 of 8 Rev. 3

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EP II-4 Prepared By:

C.A.

Burge,,_ _

Reviewed By:.,,,,__ [

,,_4[/5]~fJ Department Head Date Reviewed By:

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Nuclear Emergency Planning Engineer Date I

Reviewed By:

4 3o g*3

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Stat [6n ~6tI51Ety Assurance Review Date

~~~~ ~~

73-d7/jfrequiredsee P VI-2)

SORC Meeting No.: X

_7 Jg g Date Approved By:

p[ g3 neral Man ger Salem Operations Date Approved By:

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g Manager - Nuclear Site Protection D' ate

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SGS 8 of 8 Rev. 3

EP II-4 i

ENERGENCY RESPONSE MANAGER CALIIXIT CALIER: CCNTROL ROO!/IEC CCNMUNICATOR

1) Contact the Emergency Response Manager and read the Station Status Checklist.

2) Provide the Emergency Response Manager with a telephone ntsnber at which the Senior Shif t Supervisor or Energency DJty Officer may be contacted directly.

3) If the Emergency Operations Facility is to be activated, contact the Incd Dispatcher and use the message provided in the appropriate Classification procedure (EP I-2, EP I-3 or EP I-4).

l EMEICENCY RESPONSE MANAGER (contact one)

Office Home Date/ Time R. A. Uderitz 4800 J. T. Boettger 4700 H. J. Midara 4300 R. A. Burricelli 4900 IIAD DISPAirHER

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Newark (201) 430-5041 SGS 1 of I hv. 3

EP II-4

'ISC TECINICAL SUPPORT LEADERS CALIDJT CALLER: TECINICAL SUPPORT SUPERVISOR Contact a Technical Support Team I.eader and an Operations Assessment Team member and direct them to report to the Technical Support Center.

If access to the Technical Support Center is restricted due to the energency or if an evacuation of the site has been ordered or is being considered, the Technical Support Team Isader, Technical Support Team and Operations Assessment Team may be directed to report to the EJnergency Operations Facility.

Office Hone Ihte/ Time 723ICAL SUPPORT TEAM LEADER - TSC R. T. Stanley 4888 H. Berrick 4854 OPERATIONS ASSESSMEt?T TEAM

. CORE THEPMAL B. Hall 4707 R. Brown 4720 ELECTRICAL L. Corleto 4708 M. Shedlock 4424 MECHANICAL F. Schnarr 4746 H. Berrick 4854 a

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SGS 1 of 1 l

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EP II-4 TSC TECWICAL SUPPORT TEAM CALImr CALIER: TECWICAL SUPPORT TEAM LEADER

'ISC Contact the Technical Support Team - TSC (one for each function) and direct them to report to the 1SC (or other location as directed by the Technical Support Supervisor).

Office Home Date/ Time TECHNICAL SUPPORT TEAM - 15C MECHANICAL H. Berrick 4854 M. Gibbons 4873 i

ELECTRICAL M. Shedlock 4424 R Diaz 4817 CCNTEIS M. Morroni 4820 L. Griffis 4836 DESIGN MECH.

W. Straubnuller 4905 D. Kline 3314 EIICTRIAL/COtfrEL V. Coviello 4908 W. Yip 4902 i

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e EP II-4

,j SUPPORT MANAGERS CALID.Tr CALIIR: ENERGENCY RESPONSE MANAGER Contact support snagers and direct them to report to the Emergency Operations Facility. 'these calls are also automatically mde by the Load Dispatcher. 'Ihey should be made as backup calls during normal wrking hours.

Office Home Date/ Time SITE SUPPORT MANAGER (contact one)

H. J. Midura 4300 F. Meyer 4543 E. J. Barradale 4582 P. A. Moeller 4400 C. P. Johnson 7-333-6726 FADIOIDGICAL SUPPORT MANAGER (contact one)

W. L. Britz 4546 R. P. Douglas 7-333-8258 J. Clancy 4571 J. Kotsch 4568 4

R. F. Yewjall 7-333-8449 N. C. Alle n 7-333-8345 TECHNICAL SUPPORT MANAGER (contact one) i D. J. Jagt 4702 L. A. Reiter 4887 R. L. Gura 4782 l

AININISTRATIVE SUPPORT MANAGER,(contact one)

I I

2. McKeever 4668 R. W. Baustsn 4485 W. W. Barnes 7-459-3807 I

SGS 1 of 1 Rev. 3 r

e EP II-4 ENEMENCY PREPAREDNESS SUPPORT CALI.OUT CALLER: SI7E SUPMRT MANAGER Contact one member of the Emergency Preparedness Organization and direct that this attachment be corpleted.

Office Hone Date/ Time

_ EMEEENCY PREPAREDNESS SUPPORT (CONTACT NE)

P. A. Moeller 4400 C. A. Sakenas 4575 C. A. 3 urge 4576 D. J. Godlewski 4570 SITE SUPPORT STAFF (CONTACT 3)

P. Ianders 7-459-3768 R. Best 7-459-3770 W. Grau 7-459-3844 T. Vehec 7-459-3877 C. Anderson 7-459-3864 A. Foehner 7-459-3874 K. Moore 7-459-3875 T. King 7-459-3863 J. Barglowski 7-459-3862 SGS 1 of 1 Rev. 3

e EP II-4 RADIOIDGICAL SUPPORT TEAM CALIfUT CALIER: RADIO!OGICAL SUPPORT MANAGER Contact two trembem of Padiological Assessment Team #1 Direct the first Radiological Assessment Team nember contacted to do the follwing:

1) Contact fcur field team wnbers,

2) Direct tt,e field team members to report to the EDF and then,

3) Report to the LOF.

Direct the second Radiological Assessment Team member contacted to do the follwing:

1) Contact the Radiological Support Conrunicators, t

2) Direct the ccr.runicators to report to the EDF and then,

3) Report to the EOF. Contact Radiological Assessment Tean No. 2 upon your arrival at the EDF.

Office Hctre Date/ Time RADIOIDGICAL ASSESSMENT TEAM NO.1 (contact two)

J. Clancy 4571 J. Kotsch 4568 H. Bergendahl 4569 D. Noce 4379 RADIOIDGICAL SUPPORT FIELD TEAM 2 (contact four)

D. Parks 7-459-3822 (

A. Horvath 7-459-3821

(

M. Pollack 7-459-3826 (

-J. Beatti'e 7-459-3906 (

K. Spaulding

7-459-3865 (

R. Horn 7-459-3804

(

RADIGILCICAL SUPPORT CCMMUNICA70RS (contact two)

~

F.

5' rase.11a 4722 T. Storey 4574 i

W. O'Donnel 4734 l

RADIOIDGICAL ASSESSMENT 7EAM NO. 2 (contact two)

~

R.F. Yewdall 7-333-8449 N.C. Allneri 7-333-8345 R.

Zeigler 7-333-8008 P.

Glennon 7-333-8463 l

l SGS 1 of 1 Rev. 3

EP II-4 EDF TECHNICAL SUPPORT LEADER CALILUT CALIIR: TECHNICAL SUPPORT MANAGER Contact team leaders and direct them to report to the Dnergency Operations Facility Office Home Dete/ Time TECHNICAL SUPPORT TEAM LEADER - EOF L. A. Niter 4887 R. L. Gura 4782 T. N. Taylor 4758 M. O. Bandiera 4874 H. B. Baranek 4781 NUCLEAR FUEL TEAM LEADER E. Ibsenfeld 4723 D. Hsu 4726 R. Blake 4725 OA TEAM LFADER A. Nassman 4780 M. Ibsenzweig 4818 D. Perkins 4403 LICENSING SUPPORT TEAM LEADER E. A. Liden 4743 R. Beckwith 4764 M. Banerjee 4747 c.

',. ~

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SGS 1 of 1 kv. 3

i I

EP II-4 ADtINSTRATIVE SUPPORT TEAM CALIDJr CALLER: AININISTPATIVE SUPPORT MANAGER Report to the Emergency Operations Facility and then contact the Administrative Support staff. Direct the personnel contacted to report to the Emergency Operations Facility.

l Office Horae Date/ Time TRAINIBC CErlIER SUPERVISION (contact one)

W. Barnes 7-459-4485 K. Shunun 7-459-3806

_ WORD PROCmsTNG (contact one)

B. Russell 7-459-3840 J. Parkell 7-459-3841 CONFIDENTIAL SECRET. ARIES (contact one) i L. Beard 4802 N. McMahon 4301 D. Ferguson 4703 PERSONNEL (contact one)

R. VonFischer 4683 J. Blauvelt 4686

- PURCHASItE/ MATERIAL CONTROL (contact one)

R. Moore 4678 D. Craig 4984 l

J. Tierney 4661 u.

l SGS 1 of 1 Rev. 3

e EP II-4 0 PUBLIC AFFAIFS SUPPORT TEAM CALIfXJr CALLER: PUBLIC AFFAIFS MANAGER - NUCLEAR l

Contact Public Information Manager end Public Affairs Technical Assistant and direct them to report to the i

Dnergency News Center i

Office Hone De te/ Time I

I PUBLIC INFOINATION MANAGER (contact one)

W. H. Derman 4480 L. Antonik 4480

~

B. Smith 7-333-7878 N. Brcwn 7-333-6017 Contact Puolic Infortnation Technical Liaison and Public i

Information Coordinator and direct them to report to the Dnergency News Center i

PUBLIC INFORGTION TECHNICAL LIAISON (contact one)

B. Gorman 4480 J. McCarthy 7-33.5-5864 J. Dillon 7-333-5863 C. Burge 4576 D. Gcxilewski 4570

- PUBLIC INFOFMATION COORDINATOR (contact one) i L. Antonik 4480 J. Reed 4480 R. Warfield 4480 PUBLIC AFFAIRS TECHNICAL ASSISTANT.(contact one) l<

o, Godlewh i '

'4576

("

C. Burge 4576

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J. Dillon 7-333-5863 (

l J.~ McCarthy 7-333-5864

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SGS 1 of 1

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EP II-4 1 EDF TECHNICAL SUPPORT TEAM CALIUR CALIIR: 'ITCle;1 CAL SUPPORT TEAM IEldG: - EOF Contact the Technical Support Team (one for each function) and direct then to report to the

)

Emergency Operations Facility i

I I

i TECHNICAL SUPPORT 'IIAM - EOF (contact one for each function)

Office HTe Dete/ Tine l

SYSTEMS SUPPORT T. N. Taylor 4758 M. O. Bandiera 4874 A. P. Graham 4885 e

PIANT SUPPOW R. L. Gura 4782 H. B. Baranek 4781 L. Imitz 4819 3

j-DESIGN SUPPORT A. 'Ih:xson 4910 1

E. Schmieder 4909 l

J. McFadden 4907

.n lE 1 of 1 Rev. 3 i

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EP II-4 2 OIHER SUPIORT TEAMS CALLOUT LICENSING, NUCLEAR FUEL AND CA, TEAM LEADER -

EME NENCY OPERATIONS FACILITY CALLER: LICENSING SUPPORT HAM LEADER Contact Licensing Team and direct them to report to the EOF.

Office Hcune

[hte/ rime i

LICENSING SUPPORT TEAM (contact one)

R. Beckwith 4743 M. Banerjee 4747 R. Patwell 4750 J. Balletto 4748 CALLER: NUCLEAR FUEL TEAM LEADER Contact Nuclear Fuel Team and direct them to report to the EOF.

NUCLEAR FUEL EAM (contact one)

D. Hsu 4726 R. Blake 4725 J.Iai 4735 F. Safin 4733 D. Rothrock 4736 CALLER: OA 'IEW LEEER Contact Of Team'and ' direct Ihem to re' port to the EDF.

OA TEAM (contact one)

LATER SGS 1 of 1 Rev. 3

EP II-5 i

EMERGENCY PROCEDURE EP II-5 PAGING EMERGENCY RESPONSE PERSONNEL ACTION LEVEL o

This procedure shall be used as guidance for initiating and responding to a page.

Data Pager's Require User To Enter Phone Number Using A Touch Tone Phone.

Action Statements - Section I

{!aking a Page - Data Pagers The Load Dispatcher shall:

1.

Using Attachment 2 (not included in all manuals) to Procedure EP II-4, page Support Managers who could not be contacted at their home phones.

a) Dial the telephone number listed for the individual (s).

b) Wait for access tone (redial if busy).

c) Immediately after access tone dial (touch tone) 201-430-6313 and hang up.

d) Repeat steps a-c for all persons to be paged.

e) Record requests for paging and the results on Attachment 1 (not included on all manuals) to this procedure.

2.

Using Attachment 1 (not included in all manuals) to this procedure, page personnel as requested by the Support Managers, Technical Support Supervisor, or Team Leaders.

Other Emergency Response Personnel shall.:

.a 1.

When you need to page a person (s) who cannot be contacted at either their of fice or home phones, contact the Load Dispatcher at (201) 430-5041 and use the following message:

SGS Page 1 of 4 Rev. 3

1 EP II-5 a) This is (your emergency duty title) at Salem Generating Station.

Please page (name of person to be paged)

The message is:

This is a notification of an (Alert, Site Area Emergency, General Emergency).

Please report to your energency duty station.

Action Statements - Section II Responding to Page - Data Pagers All Emergency Response Personnel shall:

1.

If a telephone number is shown on the data pager call number shown to receive message:

a) If the number shown is 201-430-6313, an official emergency response page, call the Load Dispatcher.

The call will either be answered by the Senior Electric Dispatcher-Supervising or recorded messages will be heard until the Senior Electric Dispatcher-Supervising is free to answer the call.

All calls will be answered in the order in which they are received.

Upon contacting the Senior Electric Dispatcher-Supervising, the individual being paged should give the Load Dispatcher his name and the Emergency Pesponse Group to which he belongs.

The Senior Electric Dispatcher-Supervising will then read the message to the caller.

.s.,

b) If only four digits are shown the number should be an internal extension.

Call (609) 935-6000 and ask for the extension.

SGS Page 2 of 4 Re v.

3 l

EP II-5 c) If the number is in the (609) code area the area code number may have been omitted and the display may show only the seven digit telephone number.

2.

If the pager is activated and no number is shown this may be a false page.

Emergency Response Managers and Support Managers should call the Load Dispatcher at (201) 430-6313 to determine if a page was made.

All other personnel may ignore these pages.

Action Statements - Section I4 I Responding to Page - Standard Pagers All Emergency Response Personnel shall:

1.

Call the predetermined response number for your group to receive messages.

J If your predetermined response number is (201) 430-6313, the call will either be answered by the Senior Electric Dispatcher-Supervising or recorded messages will be heard until the Senior Electric Dispatcher-Supervising is free to answer the call.

All calls will be answered in the order in which they are received.

Upon contacting the Senior Electric Dispatcher-Supervising, the individual being paged should give the Load Dispatcher his name and the Emergency Response Group to which he belongs.

The Senior Electric Dispatacher-Supervising will then read the message to the caller.

a SGS Page 3 of 4 Rev. 3 1

EP II-5 Prepared By:

C.

A.

Burge Reviewed By:

l'Ih///

,fa

/t/f/ E 6 /9fEJ IDepartment Head Date Reviewed By:

[

/I C

d t/f/P3

.w Nuclear (mergencyPlanni Engineer Date' Reviewec By:

(.[M / es Station Quality Assurance Review Date 7

o 8d SORC Me3 ting h

at[

7!LS~!h~3 u

Vg-Approved By:

f Gebral Manage'r - Salem Operations Da' t e 7

[ [J Approved By:

Manager - Nuclear Site Protection

'Date r.

SGS Page 4 of /

Rev. 3

i EP II-8 EMERGENCY PROCEDURE EP II-8 EMERGENCY OPERATIONS FACILITY SET-UP ACTION LEVEL This procedure shall be implemented for events classified as Site Area and General Emergency, or if it has been decided to activate the Emergency Operations Facility (EOF) for an Alert event.

Note Keys for the EOF are available from the security guard at the Nuclear Training Center.

ACTION STATEMENTS 1.

When contacted by the Site Support Manager, the Emergency Preparedness Staff member will notify the individuals listed in EP II-4, Attachment 12, to report to the Emergency Operations racility (EOF).

2.

The furniture in the multi-purpose room shall be arranged in accordance with the floor pian on Attachment 1 to this procedure.

3.

Telephones should be removed from the cabinets and placed on the appropriate tables as indicated on Attachment 1.

Check all telephone connections to assure that service is available.

4.

Support materials located in the emergency lockers, along the wall in the state /. federal. agency area, will be distrib.uted to 1

.a the appropriate Response Manager's area by each manager's support staff.

SGS

_Page 1 of 2 Rev. 0 1

_ __ _ __ _. _ _ _ o

LP II-8 Prepareo by:_.

Reviewea by:

OIM A/ &F 6 [9!/ 3 j

e e

Department neaa Date b f9ff.3 keyLewea by.

'A L

' /

0 y

Nuclear Emergency Planning Engineer Date heviewo by:

4 f43 83 1

btation Quall';y Assurance heview Date (it requireo see EP VI-2) bOhC hee No :

A;_

2 4!h l

/

Date N

7 Y 63 approvec by:

(j v

I

/

v oenVral hanager - balem operations uate MO approvec by:

hanager - Nuclear bite Protection Date

.. v,

LPil-6bi 2 Page 2 ot 4 hev. U

. - _ =

0 ATTAONDTP 1 FNEICDJCY OFFSITE FACILITY LAYCUT AT SALFR FRJCLPAR TRAINI?C CDfrER

1. -935-7996

17. Salem Co. hotline (389187) 33.

2.

935-7997

18. tku Castle Co. hotline (389190) 34.

FUSP hotline (389186) 3.

935-8560 exc. 3760

19. Ctsnberland Co. hotline (389188) 35.

DEPO hotline (388420) 4.

935-8560 3761

20. Kent Co. hotline (389189) 36.

935-5002 5.

935-8560 3889

21. 935-7884 37.

935-5003 6.

R. Smith hotline (519295)

22. 935-7995 38.

935-7608 7.

935-7152

23. NBC/HPN hotline 39.

935-7605 8.

935-7356

24. NRC/DJS hotline 40.

935-7999 9.

935-7680

25. 935-7453 41.

935-7988

10. SSM/CR/TSC hotline (389195)

26. 935-7509 42.

935-7783

11. 935-7733

27. 935-7508 43.

RSM/PSC hotline (389191)

12. SSM/PSS hotline'(389193)

28. 935-7676 44.

13. 935-8560 ext. 3762

29. 935-7609 45.

935-1688

14. Prod. Dept. hotline (389196)

30. 935-7607 46.

Rad. data line (389510)

15. NJSP hotline (389186)

31. 935-7606

16. NANAS 32.

s 1

I

e n

9.

i

.t g_

[

Data Center

(-

O b W '- b la lb U-i Rad Support Com s.

l

'-l 0 44D N!

Rad Assessment C

0

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DE

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PAM

~ nQ ASM C2 1 67Tl

'r_. r NJ

~

ERM 2( g j bD 2Y JJ 1

0 b 43{

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Q 3p D v

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TSM SSM j

Conference Room l g" lj3 (j

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(j D

FEMA j g ;

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1 L.14 0[

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(;

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7 28 t.

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~1 19_2E2:1 a_

EMERGENCY OPERATIONS FACILITY PUBUC SERVICE ELECTRIC AND CAS COMPANY

EP IV-l l l EMERGENCY PROCEDURE EP IV-Ill EFFLUENT DOSE CALCULATIONS ACTION LEVEL This procedure shall be implemented upon the request of the Senior Shift Supervisor /EDO/ERM or the Radiation Protection staff.

The calculations shall normally be performed by the Radiation Protection personnel in the TSC or the Radiological Assessment Staff at the EOF.

At the TSC, the primary individuals responsible for the initial calculations will be the Shift Radia-l tion Protection Technician (Shift RPT) and the REP /ALARA Super-visor.

LIMITS OF AUTHORITY Projected off-site dose estimates should be made available to the Senior Shif t Supervisor /EDO/ERM, and the Radiation Protection Supervisor (RPS) or the Radiological Support Manager (RSM).

Transmittal of the projected doses shall require the prior approval of the Senior Shift Supervisor, RPE, or RSM.

If re-entry into an affected area is required for effluent determination, consideration shall be given to the potential for encountering high dose rates.

Approval of the Radiation Protec-tion Supervisor and the EDO shall be obtained prior to entering the penetration areas.

c.

4 ATTACHMENTS i

No. 1 - Xu/O Value Determination No.

2-(a) & (b) Noble Gas / Iodine Dose Conversion Factor (K) vs. Decay Time I of 27 Rev. 3

. ~_

-,., ~.

EP IV-111 T

ATTACHMENTS (cont.)

No. 3 - R4 3 Concentration Conversion Factor vs. Decay Time No.

4-Def ault Values for Low /High Plant Vent Monitors No. 5 - Containment Monitor R4 4 Response vs. Dispersion Factor i

No. 6 - Survey Meter Response vs. Main Steam Activity No. 7 - Unit Analysis of Off-Site Dose Calculations No. 8

-Dose Calculation Sheet No. 9 - Liquid Release Calculations ACTION STATEMENTS

1. Contact the Control Room and obtain a briefing on the incident and identify the probable pathways for release of 1

1 radioactive material.

2.

Determine which sections of this procedure are appropriate for the particular release.

TYPE OF RELEASE PAGE A. Releases from PLANT VENT (Elevated Release)

1. Unit #1 3

2.

Unit #2 7

B. Unmonitored releases from: (Ground Release) 11

1. POWER OPERATED RELIEFS

2. AUTOMATIC RELIEFS

3. STEAM DRIVEN AUX FEEDWATER PUMPS C.

Releases due to CONTAINMENT LEAKAGE 14 (Ground Release)

D.

Release Rate Calculation

E.

Liquid Release Calculation

.y

.e, 4

1

See top left corner of Attachment 8 for release rate l

determination calculation.

2 of 27 Re v.

3

EP IV-lll A.1 PLANT RELEASE FROM UNIT NO. 1 A.l.1 Establish contact with the Control Room.

f A.1.2 Record the following plant parameters for subsequent calculations.

VALUE AT

' PARAMETER NUMBER SELECTED TIME

a.

Low Range Gaseous I R-41C cpm Ralease Rate b.

Medium Range Gaseous Ralease Rate IR-45B uCi/cc c.

High Range Gaseous I R-4 5C uCi/cc Release Rate d.

Backup High Range R-4 3 mR/h r o.

Iodine Release Rate 1R-41B 1.PRESENT MONITOR READING cpm (Cx) time (Tx) ii. PREVIOUS MONITOR READING cpm (Co)

' time (To) f.

Plant Vent (1) Flow cfm Rate ag.aTemp (2)(4) at t

C*

i Elevation (ft)

h. Flevation ft

i. Wind Speed (3) (4) (5) mph

j. Wind Direction (4) (5) k.

Shutdown Time hr L

Transport Distance for mi calculation

' NOT8S:

(1)

If plant vent flow rate is. unobtainable or cannot be estimated, assume 125,0,00.cfm.

4

.., s t :

~..

(2)

If the (300C)-(33C) is unobtainable to determine the t use the

( 150' *C )-( 3 3' *C ) reading.

If this is unavailable refer to Note 4 and and note chosen elevation.

(

If the wind speed is unobtainable, assume 5 mph.

Use Elevation 300' data for an elevated release.

Use Elevation 33' data for a ground release.

3 of 27 Rev. 3 F-w--

e 7-

--+'f'

+

yw

+-

h r-

+

w y+ww-e wy--'g-e---y+

r--

p

EP IV-lll p) Cackup meteorological data f rom Wilmington Airport (302-323-2280 or NAWAS J'

Lino) including wind speed, wind direction and estimated stability class.

the estimated stability class is not available, assume conditions to be

.ctble.

5) Avsrage data over 15 minute period using the strip chart recorder from tha control room.

.l.

PLANT RELEASE FROM UNIT NO. 1 (continued)

NOBLE GAS CONTRIBUTION TO WHOLE BODY DOSE RATE

.l.3a Low range or default value (Attachment 4)

Noble Gas 1 R-40 ) ( Pl a n t Vent Flow Ra te ) (Xu /0 ) ( Dose Convers ion Fa c to r ) ( 3.15 E-5 ) =

mrem (Wind Speed) hr s

)(b

)(c

)(d

) ( 3.15E-5 ) =

mrem (e

)

hr 1.3b Medium or High Range (lR4 5B or 1 R4 5C )

Noble Gas lR-4 5B or C) ( Plant Vent Flow Rate)(Xu/0)(Dose Conv. Factor)(1.05E3)=

mrem (Wind Speed) hr i

)(b

)(c

)(d

)(1.05E3)=

mrem (e

)

hr

,1.4 High Range (R43)

Noble Gas R-43)(Plant Vent Flow Rate)(Xu/0)(Dose Conversion Factor)(1.05E+3)=

mrem (Wind Speed)(Concentration Conversion Factor) hr

)(b

)(c

)(d

)(1.05E+3)=

mrem (e

)(g

)

hr NOTE

a. 1R-41C in cpm or 1R45B(C) in uCi/ce,or equivalent epm value from attachment 4.

b. Plant vent flow rate in ft 3/ min.

c.

Xu/O from Attachment 1.

(1/m2)

d. Dose conversion factor from Attachment 2(b).

mrem /hr uCi/m3 e.

Wind speed in miles per hour.

f.

R-4 3' reading in mR/h r.

g. Concentration conversion factor in mrem /hr Attachment 3 uCi/cc Calculated By Date Time viewed By Date Time 4 of 27 Re v. 3 -

l EP IV-Ill A.1 PLANT RELEASE FROM UNIT NO. 1 (continued)

IODINE CONTRIBUTION TO THYPOID DOSE COMMITMENT A.l.5 Determine the rate of increase of iodine activity.

a) Low Range Monitor 1R-41B cpm =Cx-Co=(

)-(

)=(

) cpm =(

) cpm min Tx-To (

)-(

) (

) min min NOTE Refer to Step A. I. 2(e).

QR b) Using Default Values Use Attachment 4 to determine the appropriate equivalent cpm / min.

cpm / min A. I. 6 Equation f or 50 year thyroid dose commitment rate during ex-posure period, cpm Iodine ni n (Plant Vent Flow Ra te ) (Xu/0 ) ( Dose Convers ion Factor ) (3. 35E-7 ) =

mrem (Wind Speed) hr

~~

(a

)(b

)(c

)(d

)3.35E-7)=

mrem (e

)

hr NOTE a.

cpm / min from Step A.l.5 (a or b).

3

b. Plant vent flow rate in ft / min.

c. Xu/O from Attachment 1.

(1/m2)

d. Dose conversion factor from Attachment 2(b).

mrem /hr uCi/m3

e. Wind speed in miles per hour.

n Calculated By Date Time Reviewed By Date Time 5 of 27 Re v.

3

O 6

+

4 EP IV-111 A.1 PLANT RELEASE FROM UNIT NO. 1 (continued) i IODINE CONTRIBUTION TO THYROID DO'E COMMITMENT (continued)

A. l. 7 To chtain dose commitment, multiply dose commitment rate by the 14ours exposed to that rate, (e.g., 15 mrem /hr X 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months exposure = 75 mrem-50 year dose commi tment).

i i

}

i 1

i i

o N ' g.i d

1~

.g a

g.

,,s*

Calculated By Date Time Reviewed By Date Time l

l 6 of 27 Rev. 3 l

l

~ _ - -

EP IV-lll A.2 PLANT RELEASE FROM UNIT NO. 2 A.2.1 Contact the Control Room and obtain the following plant parameters for subsequent calculations.

PRESENT MONITOR METER READING AFTER PREVIOUS MONITOR VALUE AT PARAMETER NUMBER TIME, TX READING SELECTED TIME

c. I.ow Range Gaseous 2R-41C Relcese Rate cpm

b. Medium Range Gaseous 2R45B Relocse Rate uC1/cc

c. High Range Gaseous 2R4 5C Relocse Rate uC1/cc

-d.

Back-up Migh Ra nge R-43 mR/h r

o. Iodine Release Rate 2R-41B cpm (Cx) cpm (Co) time (Tx) time (To)

.f.

nt Vent (1) riow to cfm g.

T2mpl 2)(4) t C'

h. Elevetion ft

1. Wind Speed (3)(4)(5) mph

j. Wind Direction (4)(53 (from)

'k. Shutdown Time hr

1. Trentport Distance for Calculation mi

,NOTESg (3) If plant vent flow rate is unobtainable or cannot be estimated, a s s ume 125,000 cfm.

!(2) If the (300'*C)-(33C) is unobtainable to determine the t use the (150C)-( 3 3C) reading. If this is unavailable refer to Note 4.

(3) If the wind apeed is unobtainable, assume 5 mph.'-

~

Use Elsvation 300' data for an elevated release.

Use Elevation 33' data for a ground release.

l(4) Backup meteorological data from Wilmington Airport (302-323-2280 or NAWAS Line) including wind cpe:d, wind direction and an estimated stability class. If the estimated stability class is not cvellable, assume conditions to be stable.

(5 trcge data over 15 minute period using the strip chart recorder from the control room.

7 of 27 Re v.

3

j EP IV-lll A.2 PLANT RELEASE FROM UNIT 2 (continued)

WHOLE BODY DOSE RATE DUE TO NOBLE GAS A.2.2a Low range or default values (Attachment 4)

I Noble Gas (2R-41C)(Plant Vent Plow Est e )( xu/0)( Dose convers ion Factor t f 2. 8E-5) mrem /h r

=

(noind Speed)

(a

)(b

)(e

)(d

) ( 2. 8 E-5 )

mrem /hr l

=

(e

)

1 A.2.2b Medium or High Range (2R45B or 2R4 5C)

Noble Gas (2R45 B or C)(Plant Vent Flow Rate)(Xu/0)(Dose conv. ra et o r ) ( 1. 0 5 E 3 ) =

mrem /h r (W.nd speed)

(a

)(b

)(c

)Id

) i 1. 0 5 E 3 ) =

mrem /hr (e

)

O,,,R, A. 2. 3 High Range (R-43)

Noble Gas (R-43)1 Plant Vent Flow Rate )(Xu/0)(Dose conversion Factor )(1.05E+3 )

mrem /hr

=

(Wind Speed)(Concentration Conversion Factor)

(f

)(b

)Ie

)id 1(1.05E+3)

=

(#

)(g mrem /hr

)

NOTE

a. 2R-41C in cpm or 2R45B(C) in uCi/cc, g equivalent cpm value from Attachment 4.

3

b. Plant vent flow rate in ft / min.

c. Xu/O value from Attachment 1.

(1/m2)

d. Dose conversion factor from Attachment 2(a).

mrem /hr uCi/m5

e. Wind speed in miles per hour.

f. R-43 reading in mR/hr.

g. Concentration conversion factor in mrem /hr Attachment 3.

uCi/cc Calculated By Date Time R2 viewed By Date

' Time 8 of 27

.Rev.

3

EP IV-111 4.2 PLANT RELEASE FROM UNIT 2 (continued)

THYROID DOSE COMMITMENT DUE TO IODINE A.2.4 Determine the rate of increase of iodine activity.

a) Low Range Monitor 2R-41B Cx-Co = (

l- (

)

S252 Tx!To

(

lepm = (

)g

=

man i

(

)-(

)

(

1 min man NOTE Refer to Step A.l.2(e).

O,,,R b) Using Default Values Use Attachment 4 to determine the appropriate equivalent epm / min.

cpm / min A.2.5 Equation for 50 year thyroid dose commitment during exposure period.

2 Iodine man (Plant Vent Flow Rate)( Xu/Ol(Dose Conversion Factorl( 3. 35E-7) mrom/hr

=

(Wind Speed)

(a

)(b

)(e

)(d

)(3.35E-7) mrem /h r

=

(e

)

NOTE a.

cpm / min from Step A.2.4 (a or b).

3

b. Plant vent flow rate in ft / min.

c. Xu/Q.from Attachment 1.-(1/m2}s

d. Dose conversion factor from Attachment 2(b). mrem /hr uCi/m3

e. Wind speed in miles per hour.

Cclculated By Date-Time Reviewed By Date Time 9 of 27 Rev.

5

EP IV-111 A.2 PLANT RELEASE FROM UNIT 2 (continued)

THYROID DOSE RATE DUE TO IODINE (continued)

A.2.6 To obtain dose commitment, multiply dose commitment rate by i

the hours exposed to that rate, (e.g., 15 mrem /hr X 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months exposure = 75 mrem-50 year dose commitment).

l I

i 5

i i

I i

I Calculated By Date Time Reviewed By Date Time 10 of 27

. Re v. 3 l

O

+

EP IV-Ill B.

RELEASE RATE DETERMINATION FROM UNMONITORED STEAM RELEASE POINTS B.1 If control room personnel have determined a primary leak exists in one or more steam generators by one or more of the following indications:

a) Air Ejector High Radiation Alarm b) Uncontrolled increasing level in steam generator c) Increasing steam pressure in one steam generator d) High Activity alarm in the steam generator blowdown system with or without an isolation then the Senior Shif t Supervisor shall initiate monitoring of the affected steam lines upstream of the isolation valves to estimate the microcurie content per cc of steam in the affected steam lines.

This action is required if the potential exists for a relief valve lifting, a power operated relief being opened or the operation of the steam driven Aux. Feed Pump attached to the affected Steam Generator (11 & 13)(21 & 23).

B.2 If R46 monitors are f unctional, uCi/cc activities can be determined for each steam line directly from the display and recorded in Step B.6.

If these monitors are inoperable, i

measurements must be made with a portable survey meter, and the procedure listed in B.3 through B.5 must be implemented.

B.3 Before Radiation Protection personnel enter the penetration areas to measure the contact dose rate on the affected steam lines, the Senior Shift Supervisor /EDO and the Senior Representative from Radiation Protection will evaluate and determine the potential for encountering high radiation areas

~

in'the penetrat' ion" areas due't'o'a: '

a) Reactor malfunction resulting in fuel damage b) LOCA resulting in fission product release to containment causing radiation streaming through containment penetration.

11 of 27 Re v.

3

EP IV-lli B.4 If any of the above conditions are present, specific action points must be established in accordance with EP I-17 to determine the following requirements.

a) Total dose accumulation f or operation b) Maximum dose rate tield to enter c) Types of dosimeters and instruments to use d) Type of protective clothing and equipment to be used B.5 Enter af fected penetration area or location and measure the contact dose rate on the affected steam line or Aux. Feed Pump exhaust line.

a) The contact dose rate measurement can be made with any dose rate instrument having a range of 0.1 to at least 10,000 mR/hr.

b) If it is expected that the background in the af fected penetration area will be greater than 10 mR/hr a dose rate instrument with a shielded probe should be used.

c) Dose rates should be taken at the indicated location marked on each steam line.

d) Record below the contact dose rate on pipe.

mR/h r,

line, location B.6 Use the contact dose rate, corrected for background radiation to determine the uCi/cc concentration in the pipe of concern f rom Attachment 6, or record the reading directly f rom the R46 monitor.

uCi/cc B.7 Use the following flow rates to determine steam release rates:

a) Power operated relief valve 450,000 lb/hr b) Relief Valve 800,000 lb/hr each c) Aux. Feed Pump exhaust 50,000 lb/hr 12 of 27 Re v. 3 I

B.

RELEASE RATE DETERMINATION FROM UNMONITORED STEAM RELEASE POINTS

^

(continued)

B.8 Multiply the uCi/cc f rom B.5 and the proper flow rate in lb/hr from B.6 to determine the release rate in uCi/sec.

( uCi/cc) (1 b/h r) ( 3. 3 ) = uCi/sec (a

)(b

)(3.3) uCi/sec

=

a.

uCi/cc from Step B.6.

b.

Ib/hr from Step B.7.

3.9 Whole body dose rate due to noble gas releases mrem /h r = ( uCi/sec) ( Xu/0) ( DCF ) ( 2. 22 )

(Wind Speed - El. 33')

mrem /h r = (a

)(b

)(c

)(2.22)

(d

)

NOTE a.

uCi/sec from B.S.

b. Xu/O in 1/m2 from Attachment 1.

c. Dose conversion factor from Attachment 2(a). mrem /hr uCi/m2

d. Wind speed in miles per hour (EL. 33').

B.10 Document total run time for the steam driven Aux. Feed Pump.

B.11 Document the total period of time the relief and power operated relief valves were open on the affected steam generator.

B.12 The number of times the relief and power operated relief valves are open on the affected steam generators are limited as per Emergency Instruction I-4. 7.

.,7 Calculated By Date Time Reviewed By Date Time i

f 13 of 27 Re v.

3

[

a EP IV-Ill C.

RELEASES PROM CONTAINMENT LEAKAGE NOTE This dose determination assumes a design basis containment leak rate (La).

Actual containment leak rates may be more or less.

This dose determination is a postulation and should be used as such.

Field monitoring results are preferable.

C.1 Contact the control room and obtain the reading on the high range containment radiation monitor R-44.

R/hr C.2 Using Attachment No.

5, correlate the meter reading to the vertical axis and determine the base X/O from the horizontal

axis, base X/O C.3 De te rmine the actual Xu/O using Attachment 1.

actual Xu/O C.4 Determine the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months dose.

(Actual Xu/0)(2.22) 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months dose in rem

=

(Wind Speed - EL. 33')(Base X/0)

(a

)(2.22)

=

rem (b

)(c

)

NOTE

a. Acutal Xu/O from Attachment 1.

b. Windspeed in miles per hour (EL. 33').

c. Base X/O from Attachment 5 (correlated to containment monitor).

-i Calculated By Date Time Reviewed By Date Time 14 of 27 Re v.

3

o EP IV-111 NOTE Forward all completed forms to the Nuclear Emergency Planning Engineer.

Attach other completed EP's or attachments used.

Prepared By:

N/J [bf Reviewed By*

76 83 Department Head Date deviewed By:

/3(vs /_.48/ M M

7 F 3 Nucleah Emergency PlanniIg Engineer Date A

) ! b !b 3*

Reviewed By:

Station Quality Assurance Review date (if required see EP VI-2) 7!6!I')

SORC Meeting No.:

hS'h /

^'I

~

Date Approved By:

2/ 3 General Manger - Salem Operations Date Approved By:

1

//

Manager - Nuclear Site' Protection Da te l

I i

,15 of.27 Re v.

3

a ATTACHMENT 1 Xu/O VALUE DETERMINATION S310ct the Xu/O values that correspond to the stability class as determined by the a temperature, distenc3 from the site and the release point (ground or elevated).

1.

"9E THE TEMPERATURE VALUE FPOM THE METEOROLOGICAL TOWER TO DETERMINE STABILITY CLASS.

Prima ry Ins t rument NOTE 300 ft. - 33 ft. temperature ('C)

UNSTABLE IS 1 -1.3*C UNSTABLE NEUTRAL STARLE NEUTRAL IS > -1. 3 *C 1 -0. 5'C

-1.3

-0.5 STABLE IS > -0. 5'C Backup Instrument NOTE 150 f t. - 33 ft. temperature ('C)

UNSTABLE IS 1 -0.6*C UNSTARLE N EUTRAL STABLE NEUTRAL IS > -0. 6

C 1 -0. 2

C STABLE IS

> - 0. 5 ' C

-0.6

-0.2 2.

DISTANCE CROUND LEVEL RELEASE ( E-6 /m 2 )

ELEVATED LEVEL RELEASE ( E-6 /m2)

METERS MILES UNSTABLE NEUT RAL STA3LE UNSTABLE N EUTRAL STABLE 1000 0.62 15 61.39 244.8 16.5 42.3 1270 MEA 0.79 9.95 41.5 227 11.4 37.4 2000 1.2 4.64 22.49 168.0 5.43 24.4

.086 3000 1.9 2.32 12.20 113.3 2.75 14.7

.506 4000

2. 5 1.42 7.86 81.7 1.69 9.91 2.49 5000 3.1

.968 5.58 62.3 1.15 7.19 5.32 6000 3.7

.708 4.21 49.5

.846 5.50 7.94 7000 4.4

.543 3.32 40.5

.650 4.37 9.89 8000 4.9

.432 2.70 34.0

.517 3.57 11.1 8045 LP2 5.0

.42 2.5 33.3

.512 3.54 11.2 9000 5.6

.353 2.25 29.0

.422 2.99 11.8 10000 6.2

.294 1.91 25.2

.352 2.54 12.1 11000 6.8

.250 1.65 22.1

.299 2.20 12.2 12000 7.5

.215 1.44 19.6

.258 1.93 12.0 13000 8.1

.187 1.27 17.6

.225 1.70 11.7 14000 8.7

.165 1.13 15.9

.198 1.52 11.4 15000 9.3

.146 1.02 14.4

.176 1.37 11.0 16000 EPZ 9.9

.131

.952 13.2

.157 1.24 10.5 I

MEA - Minimum Exclusion Area LPZ - Low Population Zone EPt - Er.orgency Planning Zone

~

"v.nlue of Xu/O for 1000 meters distance = 4.36E-16/m2

~

- Value of Xu/O for 1270 meters distance = 1.10E-12/m2 Df-*anco Xu/Q =

E-6/m2 (ground)

Xu/O =

E-6/m2 (elevated) 16 of 27 Rev. 3

Attacivy 2(a)

Att. 2ra).

~

0.6 -

BASED ON EPA-520/1-75-001 3200 AWW THERML AT E4WILISA!WM HOTE: INOROWTH OF GASEOUS DMUGHTERS INCLilCIO IN 00$E RATES 1

0.8 A.

Time f ran shutdown to time of release in hours - =

hr B.

Time for transport = (Desired Distance)/(Wind Speed)

R R

(

mil /(

mph)

O.4

=

/

hr' C.

Total decay time = (Step A) + (Step B)

N R

I I+I I

/

hr y

D.

Correlate the total decay time (hours following shutdown) l C

t the curves to detemine the dose corwersion factors 0.3 2

3 for Noble Gas.

4

/

o M

u 3 0.2 l

0.2 1

l:

!ie I

N I

I O

I I

l l

I 0.00 g

10 20 30' 40 50 60 gt n

4 TOTAL DECAY TIME - liOUliS e

w

^

r Att. 2 (10 Attt ment 2. (6)

ICDINE D;CF FCLLOUING CEACTOR SHUTDOUM BASED OH EPA-580/1-75-001s 3800 MU THERMAL AT EQUILIBREAIM BRCF*8 FROM REO GUIDE 1.109 8900 MORMALIZED TO I-131 CONC OF 1 UCI/M**3 i

I-TOT DRCF=8988.1-(50.089t?)+(i.8783*T**8)-(0.040035tT**3)

+(5.3469E-4*T**4)-(8.3757E-887*85) 8800 l

M 8700 R

I-707 DRCFs NORMALI2ED TO 1 UCI/M**3 I-131 l

)8800 H

A.

Time from shutdown to time i

R i

i

/ 8500 of release in hours

=

g U

hr i

i o

C B.

Time for transport = (Desired Distance)/(Wind Speed)

{

g IB400

(

mi)/(

mph) 04 g

hr

=

i

,8300 C.

Total decay time = (Step Al u

g

+ Step a) l 3

I I+I I

l

)

hr 8800 C rrelate the total decay time (hours following shutdown) to the curves to determine the dose conversion factors i

8100 -'

i 8000 1

1 l

l h

1D00 I

U I

I I

l U

> p, 0

10 20 30 40 50 80

E E

TOTAL DECAY TIME - IlOURS l

Et:

w

55 --

R-43 CONCENTRATION CONVERSION FACTOR FOLLOWING SHUTDOWN BASED ON EPA-520/1-75-0013 3200 MU THERMAL AT EQUILIBRItW HOTE: INGROUTH FROM PARENT ISOTOPES NOT INCLUDED 45 i

40 i

M

$ 35 H

I R

/ 30 U

wn C

6 I 25 i

/

C C

o 20 I

l 15 l

10 5 -!

i I

I I

I l

l l

g 00 10 20 30 40 50 60

(

HOURS FOLLOUING SHUTDOUN

.H a

uf0-

)

1

e O

i ATTACHMENT 4 DEFAULT VALUES FOR LOW /HIGH PLANT VENT MONITORS Read the below accident description and determine which case is applicable.

From the table select the appropriate release rates (cpm).

DEFAULT I LOCA WITH FUEL MELTING A LOCA assuming severe core damage - fuel melting (Regulatory Guide 1.4 assumptions) 100% of noble gases and 25% of the iodines contained in the core are assumed released to the containment.

The d

containment initially leaks at the maximum design leak rate.

1 DEFAULT II LOCA WITHOUT FUEL MELTING Primary coolant leaks at a rate fast enough to increase the temperature of the core to the point where there'is damage to the fuel rods.

For this case, it is assumed that all the gap activity j

(the gases contained between the fuel and fuel rod) is released to i

the containment.

The containment is assumed to initially leak at the maximum design leak rate.

In this accident, it is up to the i

Senior Shift Supervis'or or Emergency Duty Officer (EDO) to assume that there has been no fuel melting.

If there is any question, a DEFAULT I LOCA should be assumed.

1 DEFAULT III DECAY TANK RUPTURE This procedure is used only if actual radiological monitoring equipment is unavailable for release evaluation (monitors out of l

service, read off scale, etc.).

DEFAULT IV FUEL HANDLING ACCIDENT i

Any activity occurring as a result of a fuel handling accident is i

normally drawn into the Fuel Handling Building Ventilation System i

and vented to the plant vent for release.

The process monitors are used to monitor these releases, however, should these monitors be out of service or of f scale, this technique is used to evaluate off-site dose.

i DEFAULT V STEAM GENERATOR TUBE RUPTURE The activity released during a minor tube rupture can be determined using vent monitors and normal procedures.

This procedure addresses the steam generator tube rupture as analyzed in the FK$R.

This accident.is. set apart from others because o' the' inability to consult radiation monitors to determine the activity release rate.

Therefore, this is the primary procedure to determine the activity release rate resulting from a steam generator tube rupture.

20 of 27 Rev. 3

i EP IV-lll ATTACHMENT 4 (continued) l EQU1 VALENT IODINE EQUIVALENT NOBLE GAS ACTIVITY INCREASE RATE j

ACCIDENT CLASS RELEASE RATE CPM CPM / MIN UNIT 1 UNIT 2 UNIT 1 UNIT 2 i

I(l) 2.42 E5 4.34 E6 9.35 E6 9.73 E6 II(l) 7.82 E2 1.40 E4 1.45 E5 1.51 E5 I

III(l) 1.25 ES 2.24 E6 NO RELEASE NO RELEASE IV(1) 9.9 E4 1.78 E6 1.22 E6 1.27 E6 V(2) 1.42 E4 2.54 ES 3.3 E6 3.50 E6 (1) Use actual or estimated plant vent flow (cfm) as provided in the procedure.

(2) Def ault V is assumed not released through the plant vent so use a flow of 125,000 cfm for this calculation.

I r

J q

g N

A

/

4 i

I 21 of 27 Rev. 3 i

EP IV-lli ATT. 5 ATTACHMENT 5

(

CONTAINMENT MONITOR (R-44 VS DISPERSIO'N FACTOR j'

DISERSION FACTOR WQ - SEC/b 10-5

.104 10-3 10-2 Y A'IER'-_.~_

- A m._iBFiW u::-ren=aw-i.v...

4 s.v...

a

- nm

= = = = = -

7

..~_.

9

~

J-%,_ w.

q a

m n

- m

.. - ~- - w

- -==---p-4 39 23 g

- s w.=_

,.m T

--+--- -

2._

=-_

1

~ ~ _

r x

i l Y=15 2 x g $

=^

%s=e=+==,_ = :e : _::-_w m5h =--

22= m --

~

2 3 " :-

c==---

_r

,a;

= _ = _

.( 5 a: = =

M m!GM*g

!d ENEj4 s!fli 75 6 :-

5 r

m:w 4

ia(7 -

=m-

_r

=

3 h

8 cr x

l l

's a

1 h

105g g;;;77g g _ g g g q_g =mg--

- __ E

- = _

,g= = + _ --_ = -.

-_ = -

S T.-

T

~

m-xm-3

-======.w===.====------

m_

MQm"-?_ *2" L'" E T '"$13 $E ?f_g =-54 i- " "*

-~

m

==- - - - - -

>Z7*

4 m ---

e=

- * = = = - - - -

=_

I

_m I

1 1

1 l

ROIE l(

OFFSITE DOSE OF 1 REM IN 24 HOURS FOLLOWING A LOCA AS DETERMINED BY R-44 RESPONSE AND X/0.

Page 22 ef 2 7 Rev. 3

l n zv-m m.s l

l l

ATTACHMENT 6 SURVEY lETER RESPONSE YS, PAIN STEAM LINE CONCENTRATION 10-3 10-2 10-1 100 101 102

,,,,,e

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-L E-CONCENTRATION IN PAIN STEAM LINES

]

vCr/cc a 1005 PSIA

v a

"T0 CONVERT TO vCrA. MULTIPLY BY 1.20E4 Page 23 of 27, Rev. 3 O

...n

,.,..-a

,v-

EP IV-Ill i

ATTACHMENT 7 UNIT ANALYSIS OF OFF-SITE DOSE CALCULATIONS A.l.3a. Unit 1 Low Range Noble Gas (41C)

(cpm uCi/cc

)(ft3 2.832E4cc. I min)( 1 )(mrem /hr) 3.33E7 cpm (min )

ft3 60 see m

uCi /m3 = 3.15E-5 l

2 (mph 0.45 m/sec) mrem /hr mph A.l.4 Unit 1 High Range Noble Gas (R-43 or R-45*)

(A.I.3b")

(m r/h r) ( f t >

2.832E4cc 1 min) ( 1 )(mrem /hr) min ft3 60 see m

uCi/m3 2

1.05E3 mrem /hr

=

(mph. 0.4 5 m/sec ) (mr/hr )

mph uCi/cc A.l.6 Unit 1 Iodine (41B)

(cpm uCi/cc

)(ft3 2.832E4cc I min)( 1 )(mrem /hr) min 3.13E9 cpm / min min ft3 2

60 see m

uCi/m3 = 3.35E7 l

(mph 0.45 m/sec) mrem /hr mph A.2.2a Unit 2 Low Range Noble Gas (41C)

(cpm uCi/cc ) (ft 3 2.832E4cc 1 min)( 1 )(mrem /hr) 3.75E7 cpm min ft3 2

60 see m

uCi /m3

= 2.8E-5 (mph 0.45 m/sec) mrem /hr mph A.2.3 Unit 2 High Range Noble Gas ( R-4 3 o r R-4 5 * )

(A.2.2b")

(mr/h r) ( f t3 2.832E4cc.

1 min)( 1 )(mrem /hr) 7~

min ft>

60 see m

uCi/m>_

1.05E3 mrem /hr

=

(mph 0.45 m/sec)(mr/hr) mph uCi/cc A.2.5 Unit 2 Iodine (41R)

(cpm uCi/cc

)(ft 3 2.832E4cc.

1 min)( 1 )(mrem /hr) min 3.13E9 cpm / min min ft3 2

60 see m

uCi/m3

= 3. 3 5E-7 (mph 0.45 m/sec) mrem /h r mph B. 7 _ Release Ra te From Unmonitored B.8 Whole Body Dose Rates Steam

_From Release Rate 1.20E4 cc/lb 3.3 (uCi ( 1 )(mrem /hr)

=

2 3.6E3 sec/hr see m

uCi/m3

= 2.22 (mph 0.45 m/sec) mph Since 1/2P-45 read directly in uCi/cc, unit analyses for R-43 i

~

are identical except that the mr/hr/uci/cc conversion factor, need not be applied.

l 24 of 27 Re v.

3 l

~

e EP IV-III oost CAttutAre0= In tT A t t,or ing R.eei ng _

cchment 8

moni ses5 - imiit ing CALC. Daft CALC. TIE RELEASE Raft AitcPwtRIC DISPERSION CCSI (D88'. FACTOR 005t 70 emm AT Mion 156 AT LEnflON & liffE7ttst CEF o

Twt LT ation M 8/sec-.

oec/m3

--w m/m e..

OF lesTtats?

(See Att. I, y 1y.991) eCl/d (See Att. 2, Ivell t)

=

Q p-Senelt seeseese 5teht(Ity t e safine. Tn rols Does mate en M e 0 * (x/Q3 e gxr; v

Jesse e sees a

g a

Fies Ground er te Unit mate tievetedt e

(

) (

l (

) e Constant g (A eCi/sec esc /o DCF Dase e te s

tu /oH2.221 3 te)

(el (nr./hr lOtAmsts Huas PLAsif pf eine speed een f

I (

) (

) e da it IbsIS is oe f ecato ese Att, e F. av.lti g st A 1

)(ir.22)

tel e v2 aCl/sec sec/o3 UCP pose note

(

)

(el (el 0t.

J

(

)

(

)

(e) i WJ eenst sent fles =

aCl/sec

(

) (

l

ll8 C) efe

$ LP2 (

)(2.22) e (el e EP2 o l/sec sec/e3 CEF Dose m te ese more a

(

)

(e)

(t) g9*2 (I GAS: 19 RelC. R490. end R4SC are out of service

(

) (

l

mee R43 channet, use Att. 3. EP tv.llt e EPZ (

H 2.??).

til e_

C#/sec sec/m3 DCF Dase mete for I f orm (Remember te dieles by I ters).

(

)

(a)

(g) 8 '3*

19 R43 la of fecolo ese Att. 4. F tv.Ill 4

(

H 2.22) e (g) sembte Gas

whole Oedy Dose Rete o M

Q (X/gl (0:F) d(

l (

l

(b)

(

l a

coast sent flee e ecl/sec

(

) (

)a C

(jl efe e IE A act/see sec/m3 DCF Dase Rete ese siete au/0 (I-4/m2)

(b er c)

(el foresAr)

Creund

)

.(

) 14.72t2B *

(b)

(

) (

)*

/cc woat flee eCl/sec eC/

0 LP2 nCl/sec sec/m3 CEF Du e Sete B er C cf m

$300-1 1.3 a.C.S (b er c)

(el 4ta i

30 ft. nestet neut stab Je (

) (

l (4.72t23 =

(b)

(

) (

)=

Qr coast

.ent flee ecl/sec IEA 9.91 41.5 227 0 EPZ aC1/see sec/m3 OCF Dree Rete 0

(Il ef e l

,Lt 2.,2

,2.20 113.,

piAm

'm AftsosPwtRIC RELitF WALVES

(

? (

) (

l*

l LPZ 0.42 2.5 33.3 4_

ecI/sec sec/m3 GF Done m te i

7 Ties e hours e

(b er el (g) 89 EPZ 0.13 0.95 13.2

..======.=..===.*==...===.==.==..3=

p

...=..**.===.

eheie See. Dase. Containema+ teme,

a Reesrinne e ap/h, e Att 4. (P IV.Ill list conc.

uCl/cc mu/;_ (E-4/.21 4 IE A (

),(

3 Elevated (tese I/Q) (X/geEa3 Res in 24 nes.

(

I (3.33 (

l (c)

(s) eCl/cc th/hr e uCl/sec ac/

g.1,3 from e6 eve er R46 0300

>.0.5 t LPZ (

le f I*

30 ft, unstet neu t stet nG CDwfasseott sosseTURS 70 ESTimpTE WF51TI DOSt (tese */gl (t/geus23 Res in 24 hrs, tel

? LIAEAGE. 458 Att. S. EP sv.llt.

IE A 82.4 42.2 e

8 (PZ (

le (

le (e) 2.aslLE 3.12 17.26 0.793 (see. K/03 (x/getP2) Ass an 24 hrs.

- Sese I/g ta ylete (f*

ar &

IR le 24 heure LPZ 0.57 4.06 14.3 l

4_

(

le (

l*

y N us i t I sjl.1.421-54 unit 2 (j)

1.29t.$

EPZ 0.179 1.49 13.0 (Bese x/g) (z/ge _ )

Res in 24 nes.

For Ut t t I t h ) e 1.318 73 telt 2 (h) e S.Sft.7 (g)

Oses the eclease rete sees reasonettet if Stgi. If the eine seeme (eph) sad stability Stes: If the Weie boey sese rete escoees 0.5 rem /hr sneelstry een take e secole of tse sent, hos not ches96e you any see the esse etert the R98 If the tnyreld sese rete..

esepero tno6r roertes iCl/cc eelue with the toises le oneseguent est.slettesis, semes 7.5 cm/hr esort the R9s. The crees Col.

first toe forme seawe, autoted ere future seses. List the errival i.sSt.i2/4

,,.e.or all solo gette.e.

e Olec*erges enlan en ene e.orage escase 1 Cl/sec os00 C /m ) se seei.,se..re c..e,.c.on.

eers, oema.rves enini

. o.e,s e c.e.

Arr e.ei fles (,re ).,1.

is..

. to incetro. een.s >

7 eC /s.c (25 eCi/wel se i in..r.

,er (eine see in n>

1 ene.

92 29 a 'tio r er *0 to get erri..,ime in minu,es.

n 25 of 27 Rev.

3

EP IV-lli ATTACHMENT 9 LIOUID RELEASE CALCULATION In the event of a radioactive liquid release to the Delaware River, the following procedures should be used.

A.

Water Sample Activity Determination A 20 cc sample is taken and placed in a small beaker.

The sample is placed on top of the SAM 2 detector.

The breaker's geometry would be similar to the geometry for counting a charcoal cartridge.

The total gross activity is determined as follows:

1)

Multiply the total cpm by 80 to get a reading in dpm.

The efficiency of the SAM-2 is approximately 1.25%, hence the ratio of the disintegration rate in dpm to the count rate displayed is 80.

2)

Multiply the reading in dpm by 4.5 E-7 cc to obtain a reading in uCi.

3)

Divide the reading in uCi by 20 cc to determine the activity in uCi/cc.

Multiply this concentration by lE+9 to determine pCi/1.

4)

The following information would be recorded:

a.

Location of sample taken:

b.

Date. Time Sample Counted:

c.

Gross Activity pCi/l:

d.

Date. Time Sample Taken:

B.

Dose Determination The basic equation to calculate the dose conversion factor for a given nuclide is:

26 of 27 Rev. 3 u

EP IV-lll Dose Conversion Factor =2.13 x 10 6 (Eg + Eb/2)

(mrem /hr per pCi/1)

Where:

Eg = average gamma energy per disintegration (MeV)

Eb = average beta energy per disintegration (MeV)

Boating:

For boating activities, the above equation can be modified to the following:

Dose Conversion Factor = 1.07 x 10 6 Eg (mrem /hr per pCi/1)

In this equation adjustments account for the physical geometry and the beta shielding afforded by the boat hull.

An additional reduction factor for gamma shielding is also appropriate hut such a factor will not be included due to the uncertainty of boat design.

Using normalized dose conversion factors:

Immersion = Normalized x Total isotopic x Exposure x Dilution Dose dose conver-concentration Time Factor (mrem) sie n f actor (pCi/l (hr)

(m.am/hr per pCi/l of the weighted isotopic (mixture)

Where:

The normalized dose conversion factors are:

Water Immersion (Swimming):

Gamma whole-body doses =

1. 44 x 10 6 mrem /hr per pCi/1 Beta-gamma skin doses =

1.72 x 10 6 mrem /hr per pCi/1 Boating:

Gamma whole-body dose = 7.21 x 10 7 mrem /hr per pCi/l 27 of 27 Re v. 3

-=

6 EP IV-302 EMERGENCY PROCEDURE EP IV-302 EMERGENCY SAMPLING PROCEDURE FOR THE PLANT VENT

/

ACTION LEVEL This procedure is for taking a grab sample from either Unit l's or Unit 2 's High Range Plant Vent Monitor System for a gaseous effluent sample (R45).

These systems are located in buildings which are in back of and against the walls of the containment building and fuel handling building for each unit they serve.

A sample may be requested by the Control Room or by the EDO from the TSC after R41 has alarmed and R45 sampling pump has started and is monitoring the plant vent.

RESPONSIBLE INDIVIDUAL Chemistry sampling team as directed by the EDO shall implement this procedure.

APPARATUS Sample Rigs 1.

Noble gas sampling rig.

A.

Johnson gas bomb 100cc or equivalent small volume gas sample container.

B.

Tygon hose C.

Poly bucket with broom stick handle attached.

2.

Particulate and Charcoal Filter Sampling Rig (P/C holder).

A.

P/C holder with flexible hose and quick disconnects.

B.

Charcoal filter cartridge.

C... Particulate. filter.

Page 1 of 8 Rev. 2

O L

EP IV-302 PRECAUTIONS 1.

All samples are collected to be treated as highly radioactive material and efforts should be made to reduce exposure from the samples after they are collected.

NOTE If samples are to be stored prior to or after counting, the samples should be stored in a suitable area which will not cause significant change to background radiation levels on counting instruments.

If the storage of samples cause radiation levels high enough to have the storage a rea designated as a high radiation area then the area should be capable of being locked to reduce inadvertent exposure of pe:sonnel or the sample should be relocated to a suitable locked storage area.

2.

A Radiation Exposure Permit is required during the sampling operations (in accordance with EP-IV-106).

Radiation protection will determine the dose rates in the vicinity of the R45 building and will evaluate whether entry, for the purposes of drawing a sample, is advisable.

3.

Extremity dosimetry may be required for the individual handling the sample bomb and system valves.

4.

The control room should be notified when the sample is going to be drawn and that this activity may affect R45 readings because of the by-passing of tne R45 monitor to d raw the grab sample.

5.

The sampling team showo be informed by the EDO or designee of where the sample is to be taken for counting prior to obtaining the sample.

Page 2 of 8 Rev. 2 iM

- o EP IV-302 NOTE

Normally, the Chemistry Counting Room would De designated the " hot" lab.

In the event of an accident, the Radiation Protection Counting Room is more likely to retain a low background.

The EDO shall inform the sample team where samples are to be delivered.

ACTION STATEMENTS Section A - Noble Gas Sample 1.

Contact the Control Room and inform them that the Plant Vent Grab Sample is going to be taken.

2.

After the survey of the exterior and interior of the building housing the Sampling System and dose rates are established, enter the building to draw the sample.

3.

Shut valves 1, 2, 3& 4.

Open valve 5 ( Figure 1).

4.

Install the Johnson bomb and tygon hose between valves 1 and 2.

Open the stopcocks to the Johnson Sampling Bomb.

5.

By-pass the R45 monitor by switching Sample Selector to the manual mode.

6.

Start the grab sample pump and purge the line for 5

minutes.

Monitor the area for possible incraasing Raciation.

Page 3 of 8 Rev. 2 t

EP IV-302 NOTE Radiation exposure during the Grab Sample System purge may be minimized by leaving the area, after the pump is started, and the by-pass line has been shut-off, and not returning until the sample is to be secured.

7.

Open valves 1 & 2 and shut valve 5 in that order.

The sample bomb is now lined up to the Plant Vent for a Grab Sample.

8.

At the end of the 5 minutes, secure the pump, shut the upstream stopcock on the Johnson Bomb and then the downstream stopcock.

Finally, shut valves 1 and 2 and open 5.

9.

Return the sample selector switch to normal.

10. Remove the Johnson Gas bomb and place it in the bucket with the long handle.

Carry the sample with the sample bucket extended away from the body.

11. Remove sample to the designated counting area for analysis.

12. Contact control room and report that the sampling is completed and the R45 system has been returned to normal operation.

13. After the Noble Gas sample has been analyzed, the necessity for other types of samples shall be evaluated by the EDO.

' Sect' ion' 'B

' Pa rticu~la't'e/ Iodine Sampl f ng 1.

Install the P/C holder with flexible hoses to the quick disconnects in the by-pass line of the R45 Plant Vent monitoring system.

Page 4 of 8 Rev. 2

s EP IV-302 NOTE Insure that the direction of flow is in the correct direction (i.e.,

through particulate filter then the charcoal filter) 2.

Record the flow meter reading on the by-pass line before taking sample.

NOTE Prepare to monitor the radiation levels on the P/C holder.

i 3.

Place the Manual / Accident Controller Switch (on the wall) to manual for 10 seconds (longer if specifically requested and dose rates allow) and release the switch.

4.

Record the final gas flow meter reading on the by-pass line.

5.

The Radiation Protection team member will survey the P/C holder to datermine how and if the holder can be removed.

6.

As per the direction of the Radiation Protection team member, remove the P/C holder by the quick disconnects and place the holder in the bucket.

7.

Transport the sample to the designated counting room with the bucket extended as far as practical from the bodies of the. team, members.

8.

Contact the control room to report that the iodine / particulate sample has been obtained and that the sampling ef fort has been completed.

Page 5 of 8 Rev.

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EP IV-302 9.

After the particulate, and charcoal samples have been

analyzed, the necessity for additional samples will be evaluated by the EDO.

NOTE Forward all completed forms to the Nuclear Emergency Planning Engineer.

Attach any referenced completed EP's or attachments.

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Page 6 of 8 Rev. 2

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EP IV-302 Prepared By:

e Reviewed By:

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Department Head yte Reviewed By-k_##l 1

7 P3 NucleardEmergencyPlanning/ngineer Date a-1[4 fb Reviewed By:

Station Quality Assurance Review

'Date (if requiredg ee EP VI-2) 7!6!I3 SORC Meeting No.: _ kS-hI -

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w Date Approved By:

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General 4(anageY - Salem" Operations Date Approved By:

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Manager - Nuclear Site Protection

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Page 7 of 8 Rev. 2

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Page 8 of 8 Rev. 2

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ML20076K413

Contents

Text

Response

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