ML20078P704

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures PEP-02.4 Re Emergency Control - Site Emergency & PEP-03.5.3 Re Plume Tracking by Actual Measurement

ML20078P704
Person / Time
Site:	Brunswick
Issue date:	05/13/1983
From:	Boyer L CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20078P684	List: ML20078P693 ML20078P704
References
PROC-830513-01, NUDOCS 8311080197
Download: ML20078P704 (74)

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& <J CAROLINA POWER & LIGHT COMPASY BRUSSWICK STEAM ELECTRIC PLAST UNIT 0 PLAST EMERGENCY PROCEDURES INTRODUCTION PLAST EMERGENCY PRCCEDURE PEP-01.0 VOLUME XIII.

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Rev. 005 I. '

Recc= ended Sy* _- mv Date: F 2!JJ Director '- Ad .rtjstrative Supper:

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Approved 3y: C CE J Due: Tb f D e Plant General innager

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l 8311080197 831103 PDR ADOCK 05000324 F PDR

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PEP-01.0 Pages Revision 1-5 3 6-8 4 9 5 10 4

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EXHIBIT 1.2-2 EMERGENCY RESPONSE ORGANIZATION (cont.)

5.c. Personnel Protection and Decontamination Team:

Leader: Supervisor - Radiation Control I Alternates: Foreman - Radiation Control Specialist , Radiation Control Interim: Radiological Control Director 5.d. Dose Projection Coordinator: Principal Specialist - Radiological Alternate: Project Specialist - ALARA Specialist - Radiation Control

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Interim: Radiological Control Director

6. E=ergency Com=unicator: Director - Regulatory Compliance Alternate: Regulatory Compliance Specialis:

Interim: Available Plan: Operator

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7. Represen:stive to State Emergency Response Team Headquarters: Senior Specialist - ALARA l Alternate: Technician II - Radiation Control l

8. Site Public Informatica 4 Coordinator: Manager - News Services Alternates: Vice President - Corporate Communications Director - Media Relations Interim: Plant General Manager or his designee

9. Emergency Response Manager: Vice President - Nuclear Operations Alternate: Manager - Corporate Quality Assurance

10. Administrative & Logistics Manager: Manager - Construction, Procurement Services l

Alternate: Assistant to the Group Execu:ive -

) Power Supply 3SEP/ PEP-01.0 9 Re.. 5 I

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CAROLINA P0k'ER & LIG'dT COMPAST BRUNS'4ICK STEAM ELECTRIC PLANT L3IT 0 .

EMERGENCY CCNTROL - UNUSUAL EVEST PLAST E.TRGENCY PRCCEDURE PEP-02.2 VOLLE XIII Rev. 004 r,.,.,,

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EXHIBIT 2.2-2 m

9-I.TIEDIATE NOTIFICATICN CHECKLIST FCR AN UNUSCAL EVENT Instructions:

1) The sequence of notification pricrity is shown on the chart below.

2) State and County Warning Points should be nctified by Automatic Ringdown phene (ARD). Be sure all three (3) parties are en the line before beginning =essage. If not operable, use telephone numbers provided. <

3) Notifica:ica of indicated organization / individual should be made within sixty (60) minutes frem the declaration of an Unusual Event.

4) Appendix A contains supplemental phone numbers for off-site individuals /

organinations not listed below.

CONTACT ORGANIZATICN/ INDIVIDUAL PERSON TIME TIS TO BE CON'7AC~ED CONTACTED CON ~ALisu 60 min. State Warning Poin:(1)

(ARD or 733-3861)

) 60 cin. Brunswick County Warning Point (ARD or 457-5101) 60 min. New Hanover Ccunty Warning Point (ARD or 762-5223) 60 =in. U.S. Coast Guard (343-4567 or 3I.3-4895) l 60 min. Nuclear Regulatory Cc= mission (Red Phene or Appendix A) 60 min. CPLL Corporate Headquarters (336-6253 or Appendix A)

NRC Residen: Inspector D. O. Myers Home 791-0245 Page 341-6374 i

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CAROLINA POWER & LIGHT COMPANY BRUSSWICK STEAM ELECTRIC PLANT ~

]i L3IT 0 EMERGENCY CONTROL - ALERT 4

PLAST EMERGENCY PROCEDURE PEP-02.3 1

W VOLUME XIII 4

Rev. 004 S

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IMMEDIATE NOTIFICATICN CHECKLIST FOR AN ALERT Instructions:

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The sequence of notifica:ica priority is shcun on the chart below.

2) State and County Warning Points should be notified by Autc=atic Ringdown Phone (ARD). Se sure all three (3) parties are on the line before beginning the =essage. If not operable, use telephone number provided.

3) Notifica:ica of the crganization/ individual shculd be made within the time indicated after the declaration of an Alert.

4) Appendix A contains phene numbers for of f-site organizations / individuals not listed belcw.

CCNTACT CRGANI2ATION/INDIVIDCAL PERSON TIME TIME TO BE CCNTACTED CCNTACTED CONTACTED 15 ein. State Warning Point (ARD cr 733-3861) 15 =in. Brunswick County Warning Point

( ARD or 437-5101) 15 min. New Hanover County Warning Point (ARD or 762-3223) 60 =in. U.S. Coast Guard (343-4567 cr 343-4893) l 60 =in. U.S. Nuclear Regulatory Cc==ission (Red Phone or Jpnendix A) 60 min. CPSL Corporate Heedquarters (336-6233 or Appendix A)

INPO (404/953-0904)

NRC Residen: Inspec:c D. O. Myers He=e 791-0243

[ Page 341-6374 i

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CAROLINA PCWER & LIGhi CCMPANY -

BRCNS'n*ICK STEAM ELECTRIC PLAST L3IT 0 EMERGENCY CONTRCL - SITE EMERGENCY PIL T EMERGENCY PRCCEOURE PEP-02.4 5.nr.,e v.r,1 a U wn.e . 1 4

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1 EXHI3IT 2.4-2 IMMEDIATE NOTIFICATICN CHECKLIST FCR SITE EMERGENCY Instructions:

1. The sequence of notification priority is shewn on the chart belcw.

2. If S.E.R.T. headqua::ers is activated, DO NOT notify state, county, or Coast Guard warning points.

3. If S.E.R.T. is M activated, state and county warning points should be notified by Autceatic Ringdcwn Phone (ARD). If not operable, use phone nu=bers previded.

4 Notification of the organization / individual should be =ade within the time indicated after the declara:ica of Site Emergency.

Centac: Organisation/ Individual Person Ti=e Time To 3e Centacted Centacted Centacted S.E.R.T. Headquarters (if 13 minutes activated) (ARD or 762-8533)

State '4arning Point 15 minutes (ARD or 733-3361)

( 13 minutes Brunswick County k*arning Point (ARD or 437-3101)

New Hancver Ccunty 'iarning

. 15 minutes Point (A?l) or 762-3223)

U. S. Coas Guard 60 minutes (343-4367 cr 343-4893)

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Nuclear Regula:crf Cc= mission 60 minutes (Red Phene or Appendix A)

CPSL Corporate Headquarters 60 minutes (836-6233 or Appendix A)

IN?O (401-933-0901)

NRC Residen: Inspec:cr D. O. '4yers H:=e - 791-0243 Pa;e - 3al-637a 33',.

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CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT UNIT 0 EMERGENCY CONTROL - GENERAL EMERGENCY PLANT EMERGENCY PRCCEDURE PEP-02.5 VOLL5E XIII

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EXHIBIT 2.5-2 f

\ IMMEDIATE NOTIFICATION CHECKLIST FOR GENERAL EMERGENCY Instructions:

1) The sequence of notification priority is shcun on ue chart below.

2) If SERT Headquarters is activated do not notify State, County, or Coast Guard Warning Points.

3) If SERT Headquarters is not activated, State and County Warning Points should be notified by au cmatic ringdown phone, (ARD). If not operable, use phone numbers provided.

4) Notificarica of the organination/ individual should be made within the ti=e indicated after the Declaration of General Emergency.

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l CONTACT CRGANIZATICN/ INDIVIDUAL PERSON TIME l TIME TO 3E CCNTACTED CONTACTED CONTACTED 15 min. SERT Headquarters (If activated) (ARD or 762-8505) r i~ 15 min. State Warning Point (ARD or 733-3861) 15 min. Brunswick County Warning Point (ARD or 457-5101) 15 min. New Hanover County Warning Point (ARD or 762-5228) 60 min. U.S. Coast Guard (343-4567 or 343-4895) l 60 min. U.S. Nuclear Regulatory Cc==ission (Red Phone or Appendix A) 60 min. CPLL Corporate Headquarters (836-6253 or Appendix A)

INP0 (401/953-0904)

NEC Residen: Inspector D. O. Myers Hc=e 791-0245 Page 341-6374 i

SSEP/ Vol. XIII/ PEP-02.5 12 Rev. 4

n CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAll ELECTRIC PLANT L3IT 0 INITIAL DCSE PROJECTIONS PLANT EMERGENCY PROCEDURE: PEP-03.4.1 VOLC11E XIII Rev 004 Reccc= ended By: M Date: f// t/5J Director - Ad: gistrative Support Approved By: , hs Date: C!/_7 /P3 General Manage)r /

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3.1 Obtain a copy of Exhibit 3.4.1-1 (Initial Dose Projection Record Sheet) and record time and your initials in column 1.

3.2 Record in column 2 whether this calculation is for whole body or thyroid dose projections. Recall that thyroid dose projections should caly be made using this procedure if there is reasonable assurance that significant quantities of iodine are being released.

3.3 Determine wind speed, wind direction, and stability class using one of the following five methods listed in order of preferred use.

Record in column 3 of Exhibit 3.4.1-1.

NCTE: USE UPPER WIND SPEED AND DIRECTICS FCR A STACR RELEASE; CTHERWISE USE LOWER WIND SPEED AND DIRECTICS.

3.3.1 f operable, use the plant computer cr ESRC computer to obtain the wind speed, wind direction, and stability class.

3.3.2 Call E&RC and request meteorological data in accordance with PEP-02.6.20, Exhibit 2.6.20-1.

3.3.3 Call National Weather Service for area conditions (PEP Appendix A-4).

3.3.4 Call corporate meteorologists and request assistance from

( meteorological section (PEP Appendix A-4).

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3.3.5 If there is no meteorological data readily available, a general estimate of the current Atmospheric Stability Class can be made by visual observation, using the following table:

Sunny Cloudy Cloudy Clear Day Day Night Night light wind or calm 3 C E F ,

(1 4 m/sec or 8.9 mph) i

=oderately strong wind C D D D

(> e m/sec or 8.9 mph) l SCTE: Assume Stability Class D whenever it is raining, m_

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3.5.2.3 For WHOLE BCDY DOSE PROJECTION, calculate total release in curies /second = specific activity

(- (C1/cc) x flow rate (SCF/ min) x 28,300 (cc/SCF) x 0.0167 (min /sec).

OR 3.5.2.4 For THYROID DOSE PROJECTION, calculate total release in curies /second = specific activity (Ci/cc) x ficw rate (SCF/ min) x 28,300 (cc/SCF) x 0.0167 (min /sec) x .15.

3.5.2.5 Record the results of either 3.5.2.3 or 3.5.2.4 in column 5 of Exhibit 3.4.1-1.

3.5.3 If the high range gaseous effluent monitors for the Stack or the Turbine Building Vents are not indicating a release, refer to PEP-03.6.1 to calculate a source term based on one of the low range effluent monitors. Record the appropriate source term in column 5 of Exhibit 3.4.1-1.

3.6 Determine Dose Ccaversion Factor 3.6.1 Use Table 3.4.1-3 to determine the Whole Body or Thyroid Dose Conversion Factor (DCF). Record the appropriate DCF in colu=n 6 of Exhibit 3.4.1-1.

TABLE 3.4.1-3 3

DOSE CONVERSION FACTORS (Rem /hr)/(Ci/m )

Accident Condition Whole Body Thyroid Unknown / unidentified 287 7.49E+5 Major damage to fuel cladding 287 7.49E+5 RCS leaks or steam line leaks 133 1.25E+6 but no major cladding failure l Accidental discharge of waste gas 43 2.06E+6 Fuel handling accident 19 2.94E+6

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CAROLINA POWER & LIGHT COMPANY BRCSSWICK STEAM ELECTRIC PLANT USIT 0 WHOLE BODY COSE PROJECTIONS PLAST EMERGENCY PROCEDURE: PEP-03.4.2 VOLUME XIII Rev 004

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_1_ =

1 exp [ -1 3*}

Q no ou 2 ,o

(~ y z z where X/Q = Atmospheric Dispersion Factor, sec/m*.

2 = 3.1415 u = average wind speed, m/sec.

H = release emission height (100 m for stack releases, 0 m for ground level re-leases).

o = horizontal dispersion coefficient, m; (see Exhibit 3.4.2-6).

o = vertical dispersion coefficient m; (see Exhibit 3.4.2-7).

( 3.4 Dose Ccnversion Factor (DCF)

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3.4.1 If the nuclide mix of the source term is unknown, go to Step 3.4.2. If the nuclide mix is known, go to Step 3.4.3.

3.4.2 Determine the Dose Conversion Factor corresponding to the ti=e after Rx shutdcun plus the travel time of cloud to the point of interest.

3.4.2.1 Esti= ate the arrival time of cloud to the point of interest and add it to the time after Rx shutdown.

distance to point of interest (in meters) time after shutdcwn (in hours) + 3600u

= hours 3.4.2.2 Select tha Dose Conversion Factor frcm Exhibit 3.4.2-8 corresponding to the cloud passage time of 3.4.2.1. Use the value in units of (rem /hr)/(Ci/m') if the source term being used is given in terms of Ci/sec. If the source ters is in curies, divide the CCF by 3600. Record it l dn Column 3 of Exhibit 3.4.2-1. Proceed to Step 3.5.

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EXHIBIT 3.4.2-2

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DETERMINATION OF DOSE CCSVERSION FACTOR WCRESHEET Date:

Sample Ti=e Release Time Difference (t) (hr) i Nuclide Dose Sa ple Release *. of Conversion Factor Adjusted l

Nuclide Conc. 1(HR'1) e'* Cont. Mix Exhibit 3.4.2-3 DCF i

Total DCF (rem /hr)/(Ci/m') Is The Sum of Adjusted DCFs.*

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EXHIBIT 3.4.2-3 r GAMMA WHOLE 30DY DOSE CONVERSICN FACTORS AND DECAY COSSTANTS OF SCBLE GASES Nuclide Gamma - WB DCF (rem /hrl/(Ci/m') 1(HR'I)

^1 0.158 KR-85M 8.46 x 10

~0 KR-85 1.12 x '.0 7.4 x 10 s,

KR-87 4.79 x 10 ' O.878 IR-88 1.23 x 10 0.248

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KR-39 1.08 x 10'3 13.075

-0 XE-131M 4.46 x 10 0.002 XE-133M 1.54 x 10 0.013 XE-133 1.78 x 10 0.005

+n XE-135M 2.28 x 10 ' 2.665 XE-135 1.52 x 10 ' O.076 r,

XE-137 1.02 x 10 ' 10.662 r,

XE-138 6.70 x 10 2.376

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EXTIBIT 3.4.2-8 WHOLE BODY CONVERSION FAC~0RS FOR UNKNCWN MIX

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Time After Rx Dose Conversion Factor Shutdown (Hr.) (rem /hr)/(Ci/m')

0.5 287 1 244 2 202 5 133 8 97 12 72 24 45 72 19 f

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CAROLINA POWER & LIGHT CO.'!PANY BRUNSWICK STEA>! ELECTRIC PL.uT UNIT 0 THYROID DOSE PROJECTIONS PLANT E!!ERGENCY PRCCEDURE: PEP-03.4.3 VOLCliE XIII

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EXHI3IT 3.4.3-2 DETERMINATICN OF DOSE CONVERSION FACTOR

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'n'ORKS REET Date:

Sample Time Release Time Difference (t) (hr) f f l Suclide Dose i Sa plei Release ! f. o f Conversion Factor Adjusted' t -1 .

Suclide Conc. -1) e  ; Cont. Mix Exhibit 3.4.3-3 DCF i

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i Total DCF rem-M' Is The Sum Of Adjusted DCFs.+

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EXHIBIT 3.4.3-3 THYROID (ICDINE INEALATION) DOSE CONVERSICN FACTORS

(~ AND DECAY CONSTANTS OF RADIGICDINES DOSE CONVERSION FACTOR rem-m' Nuclide Sec-Ci 1(HR"11 I-130 108 5.64E-2 I-131 951 3.59E-3 I-132 11 3.07E-1 I-133 226 3.41E-2 I-134 3 7.97E-1 I-135 46 1.00E-1 j a

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THYROID 00SE CONVERSION FACTCKS FOR UNKSC'4N MIX

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Time After Rx Dose Conversion Factor Shu:dewn (Hr.) rem-m' Sec-Ci 0.5 208 l 1

225 2 263 5 347 3 397 12 447 2' 571 72 817

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1 CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT L3IT 0 AUTOMATION OF DOSE PROJECTION PROCEDURES USING THE HP-9830A TABLETOP COMPUTER i

PLANT EMERGENCY PROCEDURE

PEP-03.4.5 VOLLM XIII Rev. 002 n..

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i 1.0 Resconsible Individual and Objectives (x The Radiological Control Director or the Dose Assessment Coordinator is responsible for calculating dose projections to be used by the Radiological.Centrol Director and the Site Emergency Coordinator in detarmining and evaluating possible off-site consequences frem a release 1

of radioactivity. The Radiological Control Manager shall assume responsibility for calculating off-site dose projections (to be used by the Emergency Respense Manager) after the Emergency Operations Facility is activated.

i 2.0 Sccee and Aeolicability This precedure is intended to describe the use of a cceputer program which automates many of the calculations performed in PEP-03.4.2, Whole Body Dose Projections, and PEP-03.4.3, Thyroid Dose Projections. The program is intended for use on a Hewlett-Packard Model 9830A tabletop ce=puter. This program will usually serve as a backup to a program used on the IBM personal computer.

Individuals using this program to automate dose projections shculd be very familiar with the above mentioned procedures. The program allows the capability of calculating downwind centerline doses at any distance including the direction dependent site boundary distance, 1, 2, 5, and 10 miles. The program can also provide X and Y coordinates (X heing in the dcunwind direction) for plotting any desired isopleth. The program does

< not correct for lateral deviation if the point of interest is not on the

( centerline of the cicud. These provisions can be included if the correction factors are determined manually and then applied directly to the computer program's results where appropriate.

3.0 Actions Refer to the appropriate plant emergency procedure for guidance in determining the necessary inputs called for by the computer program.

PEP 03.4.2 is for whole body dose projecticns, and PEP-03.4.3 is for thyroid dose projections. The worksheet EXHIBITS in each of these procedures can be used for recording dose projections.

The computer program uses the same calculaticral methods as those described in the procedures mentioned above. The program calculates X/Q values from the basic equation using inputs of release height, stability class, wind directica and wind velocity. Other inputs include an

appropriate source term and time after reactor shutdewn. Inputting the time after shutdown allcws the computer to choose the dose conversion factor corresponding to the time that the cloud is projected to pass by the point of interest. The program calculates isepleth coordinates based en the B. Turner =ethod.

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l CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT L3IT 0 ALTCMATION OF DOSE PROJECTION PROCEDURE C51NG THE IBM PERSONAL COMPUTER PLANT EMERGENCY PROCEDURE: PEP-03.4.7 VOLUME XIII Rev. 000 Recc= ended 3y: _ p -

Date: 7!h!J3 Director-AdegistrativeSupport Approved By: d ,'_-i-- Date: ((I // M General Mandger /

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1.0 Responsible Individual and Objectives The Radiological Control Director or the Dose Assessment Coordinator is responsible for calculating dose projections to be used by the Radiological Control Director and the Site Emergency Coordinator in determining and evaluating possible of f-site consequences from a release of radioactivity. The Radiological Control Manager shall assume responsibility for calculating off-site dose projections (to be used by

- the Emergency Response Manager) af ter the Emergency Operations Facility is activated.

2.0 Scoce and Aeolicability i

i This procedure is intended to describe the use of a series of computer programs which automate many of the calculations performed in PEP-03.4.2, b' hole Body Dose Projections, and PEP-03.4.3, Thyroid Dese Projections.

The program is intended for use on an IBM Personal Computer.

Individuals using these programs to automate dose projections should be very familiar with the above mentiened procecures. The program allows the capability of calculating downwind centerline doses at any distance including the direction dependent site boundary distance, 1, 2, 5, and 10 miles. The program can also provide X and Y coordinates (X being in the downwind direction) which it uses to plot any desired isopleth. The program does not correct for lateral deviation if the point of interest is not on the centerline of the cloud. These provisions can be included if the correction factors are determined manually and then applied

( directly to the computer program results where appropriate.

i 3.0 Actions Refer to the appropriate plant emergency procedure for guidance in determining the necessary inputs called for by the computer program.

PEP-03.4.2 is for whole body dose projections, and PEP-03.4.3 is for

thyroid dose projections. The worksheet EXHIBITS in each of these procedures can be used for recording dose projections. The computer printouts can also be used for recording dose projections and documenting meteorological data.

The co=puter program uses the same calculation methods as those described

in the procedures mentioned above. The program calculates X/Q values from the basic equation using inputs of release height, stability class, wind direction, and wind velocity. Other inputs include an appropriate source term and time after reactor shutdown. Inputting the time after reactor shutdown allows the computer to select the dose conversion factor corresponding to the ti=e that the cloud is projected to pass by the point of interest. The program calculates isopleths based on the

3. Turner method.

Cne diskette labeled EMERGENCY DOSE PROJECTIONS is required.

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3.1 For Dose Projections 3.1.1 Load the diskette into disk drive A (disk drive located on the left). While simultaneously holding the ALT and CTRL keys, press the DEL key.

3.1.2 Af ter a short pause, the screen will clear and the introduction to the dose projection program will be displayed. As instructed, press any key to continue.

3.1.3 The screen will print "D0 YOU WANT TO GET MET DATA (YES OR NO)." If you want to call the Met tower or you have the

~

pulsas and want to convert them, then enter YES and continue at Step 3.2.1. Otherwise enter NO and continue below.

NOTE: When a YES or NO answer is required, generally Y and N can be used if desired. Initially, the program starts in the capital letter mode. The use of lower-case letters may cause a program error so ensure that the CAPS LOCK key is not accidentally pressed.

3.1.4 The screen will clear, then print "IS THERE A KNOWN DCF THAT YOU WISH TO USE (YES OR NO)." If you have a DCF from a previous run that you wish to use, enter YES; otherwise enter NO, then RETURN. If a YES was entered, the screen

( will print " DOSE CONVERSION FACTOR (REM / HOUR PER CURIES /

METERSA3)." Enter the DCF in these units and proceed to Step 3.1.6.

3.1.5 The screen will print "D0 YOU KNOW THE NUCLIDE MIX (YES OR NO)." If you know the nuclide mix, enter YES and proceed to Step 3.1.23; otherwise enter NO and centinue below.

3.1.6 The screen will print "WHOLE ECDY (W) OR THYROID (T) DOCE PROJECTION." The program is asking whether the user intends to make a whole body dose projection or a thyroid dose projection. Enter a W or T, whichever is appropriate.

3.1.7 The screen will print " SOURCE TERM UNITS (0-CURIES /SEC,1-CURIES)." Enter the source term units by entering a 0 or a 1, whichever is appropriate.

3.1.3 The screen will print "SCURCE TERM" and the units as selected above. Enter the source term in these units.

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. 3.1.8.1 If the units chosen were CURIES /SEC, the screen will print " ESTIMATED DURATION OF RELEASE 1

r-

\ (HOURS). IF UNCERTAIN OF DURATION ENTER 1 HOUR." By entering the duration of release, a i

total curie amount can be derived. If the duration is unknown, enter 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. This allows for easier correction later when the actual duration of release is known.

3.1.9 The screen will print "IS THIS A STACK RELEASE (TFS OR NO)." If the release was via the stack, enter YES; i otherwise enter NO.

I 3.1.10 If the nuclide mix in unknown, the screen will print " TIME SINCE REACTOR SHUTDOWN (H0URS)." Enter this time in units i of hours.

3.1.11 The screen will print " STABILITY CLASS (A-G)." Enter the appropriate stability class.

3.1.12 The screen will print " WIND VELCCITY (MPH)." Enter the appropriate wind velocity in units of miles per hour.

3.1.13 The screen will print " DIRECTION WIND BLOWING FROM (DEGREES)." This is used on the isepleth plot to indicate the direction of the plume travel. Make sure to enter the directica the wind is blewing from similar to what is k given in the meteorology program. ..

3.1.14 The screen will print " STANDARD DISTANCES ARE SITE BOUNDARY, 1, 2, S, 10 MILES. DO YOU WANT TO USE THESE (YES OR NO)." The program is asking whether the user wishes to look at centerline doses corresponding to the specific distances of sit, boundary 1, 2, S, and 10 miles, j

or to look at centerline doses corresponding to downwind j distances yet to be specified. Enter YES or NO whichever

is appropriate. Choosing nonstandard distances allows the user to obtain a more refined isopleth.

3.1.15 If a NO was entered to the previous question, the screen will print " MAXIMUM DISTANCE (MILES)." Enter the maximum downwind distance in miles for which centerline doses are desired.

3.1.15.1 The screen will then print " DOWNWIND INCREMENT J (MILES)." Enter the incremental distance in miles for which centerline doses out to the maximum downwind distance are desired.

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3.1.16 At this point the screen will clear and the information entered Will be displayed. In addition, the doses and X/Qs at the specified distances will be displayed. If the l

a=ount of information to be displayed exceeds the screen capability, the listing will stop and a message displayed at the bottom of the screen reading " HIT ANY KEY TO RESUME CUTPUT." Upon striking any key, the listing resumes and the previous information is overwritten. Continue this until all the information has been displayed.

3.1.17 The information displayed on the screen is now directed to the line printer. If the printer is not on, a message will be displayed to the user concerning the printer status. If for any reason the printer is inoperable, ignore this message by hitting the RETURN key.

3.1.18 The screen will read "ISOPLETH VALUE (HIT RETURN TO END)."

Enter the desired isepleth value in rem. If no isopleth is desired, hit the RETURN key and proceed to Step 3.1.20.

3.1.19 The screen will print "D0 YOU WANT TO PRINT THE X-Y CCORDINATES (YES CR NO)." Enter YES or NO, whichever is

! appropriate. The screen will print the X-Y coordinates to the screen and to the line printer, if a YES was entered.

Return to Step 3.1.18.

r 3.1.20 If the RETURN key was entered for the isopleth value, the

\_ screen will print " CALCULATIONS COMPLETE. DO YOU WANT TO r PLOT THE ISOPLETH (YES OR NO)." If you want to plot the isopleth, enter YES; otherwise enter NO.

3.1.20.1 If a NO was entered, the screen will print

" ENTER RUN TO RE-USE PROGRAM." To use the '

program again, type RUN and then RETURN.

3.1.20.2 If a YES was entered, there will be a short pause and the screen will print a message informing the user to ensure the plotter is ready and then hit any key to continue.

Continue with Step 3.1.21 to set up the plotter.

3.1.21 Check the X-Y plotter for the proper setup. Press the lever to the left of the tray to the up positien and align the paper in the tray. Press the lever to the down i

position. On the plotter keys, press the P2 butten, then the P1 button to ensure that the tray feed is operating correctly. Ensure that a pen is located in the left pen )

stall and press the LEFT(1) key.

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3.1.22 Press any key to continue. The plot now begins. Upon completion, raise the level and remove the plot. To use

\

again, type RUN then ENTER and return to Step 3.1.2.

3.1.23 The screen will clear, then print "WILL NUCLIDE AMOUNTS BE '

If the IN CONCENTRATION (C) OR PERCENT (P)."

j concentrations of the nuclides are know, enter a C; if the i

percents are known, enter a P.

3.1.24 The screen will read "HOW LONG AFTER SAMPLE WILL RELEASE OCCUR (HOURS). IF UNCERTAIN OF TIME ENTER 0 HOURS."

Enter the appropriate time between sample time and expected or actual release time. If uncertain, enter 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.

3.1.25 The screen will clear and a message printed at the top reading " ENTER NUCLIDE. . .THEN RETURN. ENTER % OR CONCENTRATION...THEN RETURN." This instructs the user how l

to enter the nuclides and their amounts. The screen will also print titles for the nuclides and the amounts.

3.1.26 When the cursor is under the nuclide title, enter the nuclide in its common form in capitals, e.g. , KR-85, XE-133, I-131, etc. Press RETURN and the cursor will shift over under the amount title. Enter the appropriate

% or concentration, then RETURN. If dealing with percents, the input will cease when 100% has been reached.

4 In any other situation, hitting the RETURN key when prompted for a nuclide will end input.

NOTE: The total % need not exactly equal 100%, a 2%

^ tolerance is built in; i.e. , a total % between 98 - 102% is acceptable.

3.1.27 The program will print the sample to release time, the whole body or thyroid DCF, and the units. A message will also be printed ins.tructing the user to press any key to continue. After this, return to Step 3.1.7.

3.2 For Meteorological Data 3.2,1 In order to get meteorological data, anothe4 program is loaded. After a short pause, the screen will clear and the introduction to the meteorological data a;quisition program will be displayed. As instructed, press any key to continus.

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3.2.2 The screen will clear, and then print "D0 YOU WANT TO CALL THE MET TOWER (YES OR Nd)." The user has the option of k' calling the Met tower to receive the pulses or converting pulses already on hand to usable units. Enter YES if you want to call the Met tower and continue below. Otherwise enter NO and continue to Step 3.2.6.

3.2.3 The screen will clear and flash the message "MAKE SURE

. MODEM IS RESET. PRESS ANY KEY TO CONTINUE." Ensure that the modem is reset by switching the toggle switch on the back right down and then up. Three lights should be a

j displayed on the front panel. When this is okay, press any key.

3.2.4 The screen will clear and inform the user that the modem is attempting to dial the Met tower via the plant extension. You will hear a dial tone, the touch tone dialing, and the ringing. If you receive a busy tone, someone else is using the Met tower at that moment. In this case, reset the modem and type Ctrl Scroll Lock.

(The Scroll Lock key is located on the upper right hand

- corner of the keyboard.) This halts execution of the program. Wait a few moments, type RUN and RETURN, and try again. Continue until the Met tower is contacted.

3.2.5 Once the Met tower has been successfully contacted, you will see the work CONNECT displayed on the screen. The

( meteorological information will then be printed. When all the necessary information has been received, a message will be flashed informing you to turn off the modem to continue. This allows other persons to use the Met tower without it being unnecessarily tied up. Once the modem has been turned off, proceed to Step 3.2.7.

3.2.6 The screen will clear and begin to ask for the pulses in the order that they are given by the Met program. You will be asked for the following pulses in this order:

3.2.6.1 Upper wind speed pulses.

3.2.6.2 Upper wind direction sine pulses.

3.2.6.3 Upper wind direction cosine pulses.

3.2.6.4 Lower wind speed pulses.

3.2.6.5 Lower wind direction sine pulses.

3.2.6.6 Lower wind direction cosine pulses.

3.2.6.7 Temperature pulses.

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3.2.6.8 Differential temperature 1 pulses.

r Differential temperature 2 pulses.

's 3.2.6.9 3.2.7 The pulses and the usable information they represent will then be displayed on the screen. At the bottom of the screen, two messages will be flashing. The first instructs the user to type SHIFT (the upward arrow on the keyboard) and Prtsc if they want a copy of what is on the screen. In this case, make sure the printer is on.

When l

you are done reviewing the meteorological data, hit any l key as instructed by the second message and you will return to the dose projection program at Step 3.1.2.

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j CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT 1

i UNIT 0 CONFIRMATION OF INITIAL OFF-SITE DOSE PROJECTIONS PLANT EMERGENCY PROCEDURE: PEP-03.5.1 VOLUME XIII Rev. 003

{

i

,,y.y Recoemended Sy: --

Date: f!#[13 Dire'ctor - Adminigf/rative Support Approved By: C D _& Date: dtt[y3 ~

General Mandger / /

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LIST OF EFFECTIVE PAGES PEP-03.5.1 PAGE(S) REVISION 1-2 2 3-4 3 BSEP/Vol. XIII/ PEP-03.5.1 i Rev. 3

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conditions to be encountered and on any special protective gear required.

[

3.1.6 Proceed to the survey vehicle, load the survey equipment and establish co=munications with the plant.

3.1.7 Proceed to the survey location.

3.1.8 Perform survey in accordance with guidelines outlined in ESRC-3213, Field Estimate of Airborne I-131 Concentration, or E&RC-3217, Field Estimate of Airborne Particulate Concentration.

3.1.9 Proceed as directed, to the site to return the samples for analysis or to other survey locations.

3.2 The Dose Projection Coordinator (Radiological Control Manager after the Emergency Operations Facility has been activated) shall:

3.2.1 Compare the maximum off-site dose rate readings to the projected whole body doses based on plant measurements of noble gas releases and estimated meteorological conditions.

NOTE: The actual meteorological dispersion values, for any given meteorological stability class, may

, vary by a factor of five or even more as compared with the values based on standard tables or

( figures. Where the observed dose rates are within a factor of five of the calculated dose rates it may be assumed that the initial dose

~

projections are reasonably representative of the consequences of the release.

3.2.2 If survey meters held against the samples indicate activity has been retained on the filters, this may be evidence that iodine has been released. If the activity on both filters at the second reported reading are within 25% of the first reading it should be presumed, pending isotopic analysis, that iodine is present.

NOTE: Noble gases will be retained to some extent on charcoal cartridges. It will slowly off gas.

Rb-88, with a 17 minute half-life, may be the predominant activity on paper filters. Thus activity on air samples may be the result of a noble gas release. The above step is an attempt to quickly determine whether iodine has also been released.

\

BSEP/Vol. XIII/ PEP-03.5.1 3 Rev. 3 I

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CAROLINA POWER & LIGHT COMPA.W

< BRUNSWICK STEAM ELECTRIC PLANT i

l UNIT 0 PLUME TRACKING BY ACTUAL MEASUREMENT PLAST EMERGENCY PROCEDURE: PEP-03.5.3 VOLUME XIII Rev 002 I

i

. . 3 L'

o Recommended By: Date: '

L!83 Director - A y istrative Support 4

Approved By: C D.' e Date: 813 [P7 General Managek /

/

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LIST OF EFFECTIVE PAGES PEP-03.5.3 Page(s) Revision 1-2 2

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PEP-3.5.3 PLUME TRACKING BY ACTUAL MEASUREMENT 1.0 Responsible Individual and Objectives The Radiological Control Director (the Radiological Control Manager af ter the Emergency Operations Facility is activated) is responsible for main-taining up-to-date assessment of the areas affected by radioactivity release into the environment. (For purposes of this procedure, this includes that area where exposure to members of the public are predicted to exceed 100 mrem.)

2.0 Scoce and Acplicability This procedure is to be implemented upon declaration of any Site or General Emergency where projected off-site exposures approach or exceed the levels associated with Environmental Protection Agency's Protective Action Guidelines. A determination must be made of doses in the affected areas. While these doses may be inferred from interpretations of release data, time varying meteorological conditions and results from environmental surveys, actual plume tracking should be attempted where practicable.

This procedure applies primarily to CP&L activities, necessary for emergency responses, but perfor=ed prior to full activation of the state response organi ations. Where releases continue for more than several hours, plume tracking efforts will be under the direction of the State, but CP&L may be requested to provide input. This procedure also addresses CP&L

( support of state-directed plume tracking efforts.

3.0 Actions and Limitations 3.1 The Environmental Monitoring Team shall provide necessary personnel and equipment to measure radioactivity levels in the plume.

3.1.1 Obtain maps, portable survey equipment, including an air sampler and a survey meter.

3.1.2 Consult with the Dose Projection Coordinator (Radiological Control Manager after the Emergency Operations Facility in activated) and review the release, estimated release heights and wind directions.

3.1.3 Proceed to the plume tracking vehicle and establish communications with the Environmental Monitoring Team Leader.

3.1.4 Proceed to a distance approximately 1 km (0.6 miles) from the plant, in the general dcwnwind direction.

3.1.5 Travel at a right angle to the reported wind direction and measure the highest dose rate.

L BSEP/ PEP-03.5.3 1 Rev. 2

3.1.6 If it has been determined that the release is from an

( elevated location or is associated with steam (as from open steam relief valve, steam line break, etc.) attempt (where it is safe to do so) to measure the height at which the maximum dose rate is observed.

NOTE: This will provide useful benchmark information to help interpret subsequent measurements.

3.1.7 Proceed downwind, periodically taking crosswind measurements and reporting locations of maximum readings at any given distance.

NOTE: This may need to be repeated for continuing releases.

3.1.8 Collect air samples in accordance with E&RC-3215, Field Estimate of Airborne I-131 Concentration or E&RC-3217, Field Estimate of Airborne Particulate Concentration.

3.2 The Dose Projection Coordinator (Radiological Control Manager after the Emergency Operations Facility is a'ctivated) shall:

3.2.1 Provide projected plume trajectory estimates to the Environ-mental Monitoring Team Leader. ,

Record and display a summary of the reported results

( 3.2.2 (time, location, rate) on the map.

3.2.3 If releases or meteorological cenditions. change substantially during the plume tracking effort, advise and make reccmmendations as to revised tracking locations.

3.2.4 Revise projected doses where plume tracking results'so indicate.

NCTE: Make sure that all reported dose rates are adjusted to reflect a common time (e.g., correct for differences in decay) before revising projected doses.

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BSEP/ PEP-03.5.3 2 Rev. 2

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CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM EIICTRIC PLAST UNIT 0 RELEASE ESTIMATES BASED UPON STACK / VENT READINGS PLANT EMERGENCY PROCEDURE: PEP-03.6.1 VOLUME XIII Rev. 002 Recc=nended By: .

Date: '

2 !R3 Director - Agfrinistrative Support Approved By: C D[& Date: '

13[73

/

General Managhr dj

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s BSEP/Vol. XIII/ PEP-03.6.1 i Rev. 2

1.0 Resoonsible Individual and Object _ves The Radiological Control Director is responsible to the Site Emergency Coordinator for determining the magnitude and rate of radioactive release

' to the environment. The Radiological Control Director may delegato the calculational aspects of this procedure to the Dose Projection Coordinator.

2.0 Scope and Aoplicability This procedure shall be implemented by the Site Emergency Coordinator, or by the Radiological Control Director, whenever a radiological release through an identifiable release point is suspected including any Site or General Emergency. The only apparatus required is a scientific calculator.

3.0 Actions and Limitations NOTE: The detector response (pCi/cc of radioactivity per counts per minute or mr/hr) will depend on the specific isotopic mixture being released at various times. Grab samples must be taken, analyzed and evaluated by use of PEP-3.6.3, " Interpretation of

' Liquid and Gas, ecus Samples," to provide an exact relationship; however, the predetermined relationship used in this procedure should be sufficiently accurate to guide initial emergency response actions and assessments.

List of EXHIBITS:

3.6.1-1 Source Term Calculation from Plant Stack Monitors (Low Range) i (D12-RM-K600A & B) l 3.6.1-2 Source Term Calculation from Plant Stack Monitors (High Range) 3.6.1-3 Source Term Calculation from #1 RX Gas (1-CAC-AQH-1264-3) 3.6.1-4 Source Term Calculation from #1 Turbine Gas (1-VA-AQH-3215-3) 3.6.1-5 Source Term Calculation from #2 Rx Gas (2-CAC-AQH-1264-3) 3.6.1-6 Source Term Calculation from #2 Turbine Gas (2-VA-AQH-3215-3) 3.6.1-7 Source Term Calculation from #1 and/or #2 Turbine Building Vent (High Range) 3.6.1-8 ET -Time O to 72 Hours After Reactor Shutdown 3.1 Depeading upon alarming channel (s), use appropriate EXHIBIT (EXHIBIT 3.6.1-1 through EXHIBIT 3.6.1-7) to calculate the release l

source terug. ,,

Note: If the time duration of the release is unknown, assume 60 minutes and perform this procedure as directed by the Radiological Control Director.

\

i If only one channel is alarming or reading abnormally high, the source term determined on the appropriate j EXHIBIT is the total. If two monitors are measuring the same source term, use the averags reading of the two.

(- ,

1 Rev. 2 BSEP/Vol. XIII/ PEP-03.6.1 l

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- EXHIBIT 3.6.1-1 1

SOURCE TERM CALCULATION FROM STACK MONITORS (LOW RANGE) (D12-RM-K600A & B) l EFFICIESCYPJ FACTOR RELEASEb')

METER @

FLOd) pCi/sec RATE READING TIME (CPS) (CFM) CFM-sec EIN (uCi/sec) 1 If both the A and B monitors are reading high, use average cps.

• If not available, use sum of design flows for systems exhausting to stack:

Steam Jet Air Ejectors (A & B) 300 SCFM ea.

Rad Waste Bldg. Vent (2 fans) 23,100 SCFM ea.

Purge Fans (2 fans) 7,200 SCFM ea.

Standby Gas (per train - 2 trains) 3,500 SCFM ea.

• The efficiency f actors posted on the front panel of the stack, reactor

• buildings monitors. If not posted, these values can be obtained from E&RC File 13324 or use 4.0E-4 Refer to EXHIBIT 3.6.1-8 to determine the value of ET as a function of time.

5 Release Rate = cps X cfm X Efficiency Factor X ET l

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1 1 1 EXIIIBIT 3.6.1-2 Source Term Calculation from Plant Stack (High Range)

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.001 Indicated Dose, R/hr TEMPO!WlY GASEOUS EFFI.UE'iT RADIATION MONITORS To determine total release activity (curies /sec) from the plant stack:

1. Read the " actual specific activity (curies /ce)" from the graph as a function of the dose rate (R/hr) indicated on the meter.

2. Read flowmeter for the specific release point (SCFM).

3. Calculate Total Release (Ci/sec) = Specific Activity (Ci/cc) x Flow Rate (SCa!) x 28300 (cc/SCF) x .0167 (min /sec).

Graph parameters based on the projected isotopic distribution 30 minutes after a DII-based accident.

Reference:

PM-79-296.

1

(_

BSEP/Vol. XIII/ PEP-03.6.1 4 Rev. 2 l

l l

l

EXHIBIT 3.6.1-7 Sour'ce Term Calculation from Unit No. 1 and/or Unit No. 2 l Turbine Building Vent (High Range) r

( .001 , . 01 g .1 ,1. 0 ,10 100

_9

~,

i i i - i

^

., 10 ~

.i- ' +

10 ~ I,

. . . .. i i.. . , ,, i I i i 1 11 u I l 1 l l 4

! 1  !!  !  ! l l l ll ,

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y 10 l 10~

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j i

.1 1.0 10 100

- .001 .01 Indicated Dose, R/hr TDIPORARY GASEOUS EFFLUENT RADIATION MONITORS To determine total release activity (curies /sec) from a Turbine Building vent:

1. Read the "actus1 specific activity (curies /cc)" from the graph as a function of the dose rate (R/hr) indicated on the meter.

2. Read flowmeter for the specific release point (SCEi).

3. Calculate Total Release (Ci/sec) = Specific Activity (C1/cc) x Flow Rate (SCni) x 28300 (cc/SCF) x .0167 (min /sec)

Graph parameters based on the projected isotopic distribution 30 minutes after a TMI-based accident.

Reference:

PM-79-296.

( Rev. 2 9

3SEP/Vol. XIII/ PEP-03.6.1

I

.. ', s CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT m.

UNIT 0 RADIATION WORK PERMITS AND EXPOSURE CONTROL

' PLANT EMERGENCY PROCEDURE: PEP-03.7.1

( VOLUME XIII

-Rev 003  ?

" :, $^ ,

Recommended by: Date: F A EJ

~

0 i

l Approved by: CD&

General Managed Date: 5'[F '/ M

/

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LIST OF EFFECTIVE PAGES l PEP-03.7.1 l Page(s) Revision 1-2 3 3-8 2

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L BSEP/Vol. XIII/ PEP-03.7.1 i Rev. 3

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1.0 Responsible Individuals and Objectives The Site Emergency Coordinator, Radiological Control Director and/or team leader (s) are responsible for informing personnel entering a known or potential radiation area of possible health effects.

Individual workers and team leaders are responsible to the Site Emergency i Coordinator for ensuring that emergency worker exposures are maintained within the guidelines of this procedure and ALARA to the extent possible.

2.0 Scoce and Acolicability This procedure shall be implemented following declaration of an Alert Site Emergency or General Emergency. Exhibit 3.7.1-1 provides " Guidelines for j

Control of Personnel Radiation Exposure."

! 3.0 Actions and Limitations i

3.1 Members of the Personnel Protection and Decontamination Team, as designated by the team leader, shall perform the following actions:

3.1.1 Setup a dosimetry area in the Operational Support Center (or where designated by Radiological Control Director or Personnel Protection and Decontamination Team Leader) containing the following items:

( 3.1.1.1 A supply of TLDs.

3.1.1.2 A supply of self-reading pocket dosimeters.

. 3.1.1.3 A supply of Exposure Record Sheets (E&RC-0425). l 3.1.1.4 A supply of pencils and/or pens.

3.1.2 Complete personal dosimetry forms, and issue proper i dosimetry at the Operational Support Center (OSC) for j incoming personnel. Dosimetry shall be issued in i accordance with E&RC-0430, E&RC-0435, and E&RC-0440 4

whenever possible and if time permits. If an RIMS computer terminal is not available at the OSC, dosimetry issue

! information should be recorded for later entry into the

! RIMS ccmputer by qualified dosimetry personnel.

l 3.1.3 Place TLDs in various areas outside the protected area as specified by the Personnel Protection and Decontamination j Team Leader.

l 3.1.3.1 Record location of TLD on Exhibit 3.7.1-3.

3.1.3.2 Periodically replace TLDs and record readings l obtained from removed TLDs on Exhibit 3.7.1-3.

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i .

3.1.4 Collect all Exposure Record Sheets and all TLDs for exiting personnel from Security for reading, as directed by the ,

( team leader. The information from these forms and TLD l readings must ha retained for later entry into the RIMS ' '

computer by qualified dosi=etry personnel.

l 3.2 Actions of all personnel entering a radiation area.

NOTE: Contact Personnel Protection and Decontamination Team Leader concerning where to obtain Radiation Work Permits and special dosimetry.

3.2.1 Obtain and complete a Radiation Work Permit, in accordance with E&RC-0230, Issue and Use of Computerized Radiation l Work Permit, prior to entering a radiation area.

3.2.2 As directed by the Personnel Protection and Decontamination Team member, obtain a high range dosimeter when:

3.2.2.1 Entering a radiation field 2 10 R/hr.

3.2.2.2 Entering a radiation field of unknown intensity.

3.2.3 As directed by personnel protection and decontamination team member, obtain finger badges when:

a 3.2.3.1 Handling radioactive material where expected

{ extremity dose rate is 2 100 R/hr.

3.2.3.2 Working on pipes or equipment where expected extremity dose rate is 2 25 R/hr.

3.2.4 Record any and all additional dosimetry on'the Radiation 3

Work Permit for each person entering the radiation area.

Whenever possible, the finger badges should be labeled with the individual's security badge number and dosimeter serial numbers should be recorded on the RWP. Having this l

information available will facilitate data input into this RIMS computer.

a 3.2.5 Obtain authorization for the Radiation Work Permit from the Site Emergency Coordinator, General Manager, or the Environmental and Radiation Control Manager when exposures are expected to exceed the limits set forth in 10CFR20 (> 3

' Rem / quarter).

3.2.6 The Site Emergency Coordinator may, at his discretion and as conditions warrant, defer requirements for a Radiation Work Permit, or portions thereof, prior to entry into a radiation area and give his authorization verbally.

i ( .

2 Rev. 3 BSEP/Vol. XIII/ PEP-03.7.1

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(

CAROLINA POWER & LIGHT COMPANY

' BRUNSWICK STEAM ELECTRIC PLANT L3IT 0 EMERGENCY PERSONNEL MONITORING AND DOSIMETRY PLANT EMERGENCY PROCEDURE: PEP-03.7.2 VOLUME XIII

( Rev 003 e

.q Recoc: mended By: -

Date: C, s.f7

Approved By

C h, "X Date: f/p i /M

/ /

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LIST OF EFFECTIVE PAGES

( PEP-03.7.2 Page(s) Revision 1 3 2-3 2 I

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BSEP/Vol. XIII/ PEP-3.7.2 i Rev. 3

,o 1.0 Responsible Individual and Objectives

( The Personnel Protection and Decontamination Team is responsible to the Radiological Control Director for:

1.1 Determining personnel exposures, utilining the Radiological Information Management Systems (RIMS) or a manual backup system during an emergency.

1.2 Maintaining exposure records through the use of the RIMS computer in a real time mode or by using an alternate record keeping system which can later be loaded into the RIMS data base.

1.3 Determining need for and issuing special personnel monitoring devices.

2.0 Scope and Acolicability This procedure shall be implemented upon activation of the Personnel Protection and Decontamination Team.

3.0 Actions and Limitations 3.1 Designated members of the Personnel Protection and Decontamination Team shall be trained in the use of the RIMS computer terminals to allow them to determine and document personnel exposures in g

accordance with the appropriate E&RC procedures with the following l additions and exceptions.

(

3.1.1 Set up a dosimetry issue area in the Operational Support Center as detailed in PEP-3.7.1, " Radiation Work Permits and Exposure Control".

3.1.1.1 Assist at the dosimetry issue area and complete additional documentation as required by E&RC-0485 if the RIMS terminal is not available {

and in use. Such assistance will be given as time and conditions permit.

NOTE: Appropriate documentation shall be completed on paper or entered through a RIMS terminal when exiting the plant for personnel who bypassed the additional documentation due to plant / emergency conditions.

(_

BSEP/Vol. XIII/ PEP-3.7.2 1 Rev. 3

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C CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT UNIT 0 EMERGENCY RESPONSE RESOURCES PLANT EMERGENCY PROCEDURES: PEP-APPENDIX A

=

VOLUME XIII

( Rev. 007 Rece= mended 3y: -

rd' _ Date

f!3!3 3 Assistant to tijre General Manager Approved By: C D: _ e Date: ([f,/77 General Managet / /

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LIST OF EFFECTIVE PAGES

( PEP-APPENDIX A Pages Revision 1 6 2 7 3-4 6 5 - 10 7

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J I I 3SEP/ PEP-APPENDIX A i Rev. 7 l

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TABLE OF CONTENTS PEP-APPENDIX A l

EMERGENCY RESPONSE RESOURCES Sections Page(s)

A.1 BSEP Personnel 1-5 i

A.2 Federal, State, and County Agencies 7 I

A.3 Fire and Medical Assistance 8 i A.4 Other Emergency Response Contacts 9 - 10 i

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4 ( aey, 7 3SEP/ PEP-APPENDIX A 11 I

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_,_,_.-..rs._.. .,pp ......_w.y, . .--

-. - . ,,. _...-._,..p, -.. - , . _ _ %. , .. _, ., ,,4, ., ,m% ..,,_.,y ,,,

Home Phone Office RADIATION CONTROL SUPERVISOR I (PERSONNEL PROTECTION AND DECONTAMINATION LEADER)

L. F. Tripp Alternate Radiation Control Foreman (See. Attached)

RADIATICN CONTROL SUPERVISOR II (PLANT MONITORING LEADER)

J. D. Hendersen #~

Alternate Radiation Centrol Foreman (See Attached) l l ENVIRONMENTAL AND CHEMISTRY SUPERVISOR (ENVIRONMENTAL MONITORING LEADER)

C. E. Robertsen Alterna:e A. H. Caylor l PRINCIPAL SPECIALIST - RADIATION CCNTROL (DOSE PROTECTION CCORDINATCR R. F. Queener .-

! Alternate R. C. Specialist (See Attached)

ECHANICAL MAINENANCE SUPERV!SCR (DAMAGE CONTROL LEADER)

G. G. Ca=pbell l

C. R. Treubel ISC/ELEC":"4ICAL MAINTENANCE SUPERVISCR (DAMAGE CCNTROL LEADER)

T. L. 3rcun l R. D. Creech l SENICR SPECIALIST ELEC-~4! CAL /E CHANICAL (OPERATICNAL SUPPCRT CENTER LEADER) l C. D. Aldridge C. D. Parker

. D. Stidham i

(

3SEP/ PEP-APPENDIX A.1 2 Rev. 7 l

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_ _ - _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ - ____m.--m-w.--_% _-----..w.-.-

, Heme Phene Office l

l RADIATION CONTROL SUPERVISOR I (PERSONNEL PROTECTION AND DECONTAMINATION LEADER)

L. F. Tripp Alternate Radiation Control Foreman (See Attached) l RADIATION CCNTROL SUPERVISOR II (PLANT MONITORING LEAI)ER)

J. D. Hendersen Alternate I

i Radiatica Control Foreman (See attached) l I

ENVIRON" ENTAL AND CHEMISTRY SUPERVISOR (ENVIRONMENTAL MONITCRING EADER C. E. Robertsen Alternate A. H. Caylor 1

l PRINCIPAL SPEC!ALIST - RADIATICN CONTROL (DOSE PROTECTION CCORDINATOR R. F. Queener Alternare j

R. C. Specialist (See Attached)

MECHANICAL MAINTENANCE SUPERVISCR .(DA". AGE CCNTROL E ADER)

G. G. Campbell l C. R. Treubel I&C/ ELECTRICAL MAINTENAhCE SUPERVISCR (DAMAGE CONTROL EADER)

T. L. 3rewn l l ,

R. D. Creeca i l SENIOR SPECIALIST ELEC'"RICAL/ MECHANICAL (OPERATICNAL SUPPCRT CENTER E ADER  !

l C. D. Aldridge l

C. D. Parker

,- D. Seidham 3SEP/ PEP-APPENDIX A.1 2

.s j .

1

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Qualified Ocerators for Emergency Switchboard Hcme Office i

' Annette Clemmons

! Charlotte Frye -

Kay Hewett i Sandy Knight l Rosetta Meachem .

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1 i EOF Personnel l l

! EOF Communicator i Mike Jones '

Wayne Martin l Phone Talkers TSC/ EOF l

j l Cindy Long l j

i Brenda Unger Evelyn Johnson 1

i  !

Status Board Plotter  !,

i Doug Allen

{

George Milligan j 4

Log Keecer l

! Ray White l nob 3everage 1

1

! SRO Norvell Stewar: l Ed Thorndyke Data Legge l 1 3arbara Ha -

Lynn Pierce l l

\

i C'ern  !

I Connie Cathev

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3 Rev. 7 3SEP/?EP-APPENDIX A.1 l

l EOF Personnel (Cont'd) f l

Hcme Office I

Aide 1

Gwen Vaught f

Telececier 4

' Katrina Hill l

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-. . . . - - - - - - - - - - - - - _ _ _ _ _ _____ __ . - - - - - _ ___~~

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. APPENDIX A.2 - FEDERAL, STATE. AND COUNTY AGENCIES _

(404_) 221-4503 U.S. NUCLEAR REGULATORY COMMISSION, REGION II_ (Daytime, Nights and Holidays)

Atlanta, Georgia (202) 951-0550 3ethesda, Maryland Upon failure of ENS-Red Phone System /

/

DEPARTMENT OF ENERGY.

Savannah River Opera:icas Of fice Radiological Assistance Tea =s W. T. Thorn:en S. R. Wrigh:

Alternate Primary (During Nor=al Working Hours)

STA3 0F SCR3 CARCLINA State Warning ? cia:

Highway Pa :cl Radiological Health 3 ranch Mr. Dayne 3rcwn

[s BRUNS'4!CK CCUST(

Warning Poin:

(County Sheriff - Sheriff Herman Streng)

Civil Preparedness (Mr. Cecil Logan)

NEW HANOVER CCCNN

^

'4arning ?cint (County Sheriff - Sheriff J. McQueen Civil Preparedness (Mr. 3en Washburn)

U.S. CCAST GUARD Mar.ne 5aie:y 0ffi:e (Du y Officer, Wrightsville Beach)

FEDERAL AV!ATICS ADMINIS RATICN

• Au:cmatic Ring-Ocun dedicated telephene line Rev. 7

, i t

7 3SE?,'?E?-A??END:X A.2 N

_ Y

s .

]

I APPENDIX A.3 - FIRE AND MEDICAL ASSISTANCE '

FIRE ANI) MEDICAL PHCNE ND!BERS i

Primary Alternate

/

MEDICAL CONSULTAN S TO CP&L Dr. Forstner '

Dr. Al=iral b

i HOSPITAES Desher Hospital

)

L RESCUE SQUAD Scu:hpor Volunteer Rescue Squad FIRE DEPARD.ENTS Yaupen Beach Fire Cepart=ent i i Southper: Fire Depart =ent

3ciling Spring Lakes Sunny ?cin l

l Cs 1

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3SEP/ PEP-APPENDIX A.3 3 Rev. 7 ,

4 0

--..,-____y _ . - - _ _ _ _ _

APPENDIX A.4 - OTHER EMERGENCY RESPONSE CONTACTS

[

s CP&L CORPORATE HEADCCARTERS Office Home ,

Vice President - Nuclear Operations: l B.J. Furr Alternate: H. R. Banks,  ;

Manager, '

Corporate Quality Assurance Senior Vice Presiden: - Pcwer Supply Lynn V. Eury Alternate: E. E. Utley 1

Meteorological Center Corporate Meteor 0'ogists Brian D. McFeaters Meteorological Supervisor Tim D. Drum Meteorologist _-

l TRANSMISSICN SUBSTAT:CN MAIN'TENANCE IN VILMINTON FOR EMERGENCY COMMUNICATICNS [

REPAIRS Office u-- Pager i .

C. C. Pearce J. 3. Cembs M. V. Russ l

NATICNAL WEATHER SERV!CE Wilmington, NC Raleigh, NC AMERICAN NUCLEAR INSCRERS (ANI)

Farming en, Ccnnecticut INST:TUTE OF NUCLEAR ?C'a~ER OPERATIONS (IN Atlanta, Georgia Teleccpier:

SSEP/ PEP-APPENDIX A.a 9 Rev. 7 f,

.s .. -

GENERAL ELECTRIC San Jose, California 408/925-3207 UNITED ENGINEERS AND CCNSTRUCTCRS Philadelphia, Penarylvania 213/422-4844 BASCCCK AND WILCOX EMERGENCY PROTCCOL For Postaccident Sample Analysis E=ergency Contac s The following individuals are the points of contact within 3&W for emergency notifica:icn that 3SEP is preparing to ship a postaccident sample to the Lynchburg Research Center (LRC):

Emergency Centrol Officer: Mr. J. P. (Pat) Doran

eP E=egency Control Officer - Alternate: Mr. A. F. (Arne) Olsen

4 . ce

( Recuired Information j When actifying the B&W E=ergency Centrol Officer (ECO), the caller should  ;

be prepared to supply the folicwing information:  !

1. The plant involved, the name of the individual =aking contact, and l the na=e and telephone numbers of the responsible persen at the utility to whom follcw-up cc==unication should be addressed.

2. ine nu=::er and type of samples to be shipped; i.e., liquid, gaseous and/or charcoal cartridge.

i

3. Measured radiatica levels frem the shipping container at the surface and at three feet.

l 4

Ute estimated shipping time and time of arrival at the Lynchburg (Virginia) Municipal Airport. (If shipment by other than air transport is intended, the carrier and time of arrival at the Lynchburg Research Center should be specified.)

RAD:AT:CN EMERGENCY ASSISTANCE CE U R/TRA:NING SI~'E (REAC/TS)

Dr. Karl Huener i

s.

3SE?/?EP-A??ENDIX A.4 10 Rev. 7

_ _ _ _ - .-