Text

Revised Emergency Plan Implementing Procedures,Including Temporary Change 02-1.2-1 to EP 02-3 Re Training Programs, Rev 3 to EPP 01-7.1 Re Radiological Release Info Sys & Rev 5 to EPP 01-7.2 Re Manual Determination of Release Rate
	ML20140A500
Person / Time
Site:	Wolf Creek
Issue date:	03/14/1986
From:	; KANSAS GAS & ELECTRIC CO.
To:	;
Shared Package
ML20140A490	List: ML20140A485; ML20140A500;
References
	PROC-860314, NUDOCS 8603200266
	Download: ML20140A500 (137)
	v • d • e

{{#Wiki_filter:r EPP TofC Rev. 10 l DC29 2 B6 WCGS EMERGENCY PLAN IMPLEMENTING PROCEDURES TABLE OF CONTENTS FEBRUARY 17, 1986 l PROCEDURE NO. TITLE REV. STATUS EPP 01-1.1 WCGS Organization 4 MAJOR SC EPP 01-1.2 Emergency Operation Facility 3 MAJOR SC Emergency Organization EPP 01-1.3 Home Office Emergency Center 1 MAJOR SC Organization EPP 01-1.4 Public Information Organization 2 MAJOR SC EPP 01-2.1 Emergency Classification 2 MAJOR SC EPP 01-2.2 Activation of Emergency Plan / 2 MAJOR SC Organization EPP 01-2.3 Accident Assessment and 1 MAJOR SC Mitigation EPP 01-3.1 Immediate Notifications 3 MAJOR SC EPP 01-3.2 Followup Notifications 2 MAJOR SC EPP 01-3.3 Offsite Support Notification 2 MAJOR SC EPP 01-3.4 Onsite Emergency Response 1 MAJOR SC Organization Manual Call-Out EPP 01-3.5 EOF, HOEC and Public Information 2 MAJOR SC Emergency Response Organization Manual Call-Out EPP 01-3.6 KG&E Emergency Response 0 MAJOR SC Organization Automatic Call-Out EPP 01-4.1 Technical Support Center 3 MAJOR SC Activation EPP 01-4.2 Operations Support Center 3 MAJOR SC Activation / Operation EPP 01-4.3 Emergency Operations Facility 3 MAJOR SC Activation EPP 01-4.4 Home Office Emergency Center 0 MAJOR SC Activation 9603200266 B60314 PDR ADOCK O g2 Page 1 of 3

EPP TofC l Rev. 10 PROCEDURE NO. TITLE REV. STATUS EPP 01-4.5 General Office Activation 2 MAJOR SC EPP 01-4.6 Information Clearinghouse / Media 2 MAJOR SC Release Center Activation EPP 01-4.7 Emergency Response Facility 0 MAJOR SC Information System (ERFIS) EPP 01-5.1 Exclusion Area Evacuation 2 MAJOR 3C EPP 01-6.1 Personnel Accountability 3 MAJOR SC EPP 01-7.1 Radiological Release Information 2 MAJOR SC System (RRIS) EPP-01-7.2 Manual Oetermination of Release 4 MAJOR SC Rate EPP 01-7.3 Manual Dose Projection 4 MAJOR SC Determination EPP 01-8.1-Onsite Radiological Monitoring 3 MAJOR SC EPP 01-8.2 Offsite Radiological Monitoring 2 MAJOR SC EPP 01-8.3 Joint Radiological Monitoring 0 MAJOR SC Team Formation and Operation EPP 01-9.1 Exposure Control and Personnel 2 MAJOR SC Protection EPP 01-9.2 Personnel Decontamination 2 MAJOR SC EPP 01-9.3 Radioprotective Drugs 2 MAJOR SC EPP 01-9.4 Emergency Team Formation 3 MAJOR SC EPP 01-9.5 Aid to Contaminated / Injured 2 MAJOR SC Personnel EPP 01-10.1 Protective Action Recommendations 2 MAJOR SC EPP 01-10.2 Preparation of News Releases 2 MAJOR SC EPP 01-10.3 Release of Emergency-Related 2 MAJOR SC Information to the Public EPP 01-11.1 Communications 2 MAJOR SC Page 2 of 3

EPP TofC Rev. 10 l PROCEDURE NO. TITLE REV. STATUS EPP 01-11'.2 Status Boards 1 MAJOR SC EPP 01-11.3 Logs and Record Keeping 0 MAJOR SC EPP 01-12.1 Reentry and Recovery Operations 2 MAJOR SC EPP 02-1.1 Emergency Preparedness Program 2 MAJOR SC Maintenance EPP 02-1.2 TCN No. 02-1.2-1 3 MAJOR SC l EPP 02-1.2 Training Programs 3 MAJOR SC EPP 02-1.3 Drills and Exercises 2 MAJOR SC EPP 02-1.4 Public Education 1 MAJOR SC EPP 02-1.5 Maintenance of Emergency 4 MAJOR SC Facilities and Equipment EPP 02-1.6 Communications Tests 1 MAJOR SC EPP 02-1.7 Tone Alert Radio Maintenance and 0 MAJOR SC Compensating Measures EPP 02-1.8 Testing and Maintenance of 1 MAJOR SC Public Alert System Sirens Page 3 of 3

r ATTACHMEiT 4.0 l (Page 1 of 2) aarr FCPN EP 02-3 TD90RARY PRX'!IL".tE Cm!G PA7FICE REV. 0 j j of Pfl0CT CRE TI M : PMXZX;RE NO./REVISICN D NO. Training Programs FP PO? - 1. 2 /3 c.2 -i. 2 - i REMON FOR D: Correction of errors on the WCGS Radiological Emergency Response Plan Initial Training Module Matrix AITICID STEPS:.0 Om!Q RICU!RfD: Delete Module 4 as,a requirement for the following ERO posi-tions: Shift Supervisor - DED Supervising Operators Administrative Emergency Coordinator Radiological Assessment Coordinator Dose Assessment Coordinator Maintenance Emergency Coordinator Operations Support Center Supervisor Onsite Survey Team Director Administrative Resource Manager s 1/5dZz, ac,/y, /n. "-"" = 2 ;... M*W j// / cap APPRA7D BK / / ' ' ~ ' ~ - * - a} /

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.j FORM KMF-32 REV. 8/85 Date: 2 -a t-Trfo 1 Sheet: 1 of NUCLEAR DEPARTMENT POLICY / PROCEDURE MANUAL REMOVE AND INSERT. INSTRUCTION s REMOVE INSERT EGS RADIOLOGICAL DiERGE!CY Rt:S 92SE PLAN IMPLDiENTING PROCEDURES NOTE: Please refer to the transmittal for pertinent documents to be removed and/or inserted into the manual. 1) Rmove EPP TofC, Rev.10 (3 pages) 1) Insert EPP TofC, Rev.11 (3 pages) 2) Retove EPP 01-7.1, Rev. 2 (31 pages) 2) Insert EPP 01-7.1, Rev. 3 -(32 pages) 3) Raove EPP 01-7.2, Rev. 4 (16 pages) 3) Insert EPP 01-7.2, Rev. 5 (16 pages) 4) Retove EPP 01-7.3, Rev. 4 (24 pages) 4) Insert EPP 01-7.3, Rev. 5 (24 pages) 5) Raove EPP 01-8.1, Rev. 3 (12 pages) 5) Insert EPP 01-8.1, Rev. 4 (12 pages) 5) Raove EPP 01-8.2, Rev. 2 (21 pages) 6) Insert EPP 01-8.2, Rev. 3 (23 pages) 7) Raove EPP 01-8.3, Rev. 0 (22 pages) 7) Insert EPP 01-8.3, Rev.1 (25 pages) F 1L

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.-M-84, WCGS EMERGENCY PLAN IMPLEMENTING PROCEDURES TABLE OF CONTENTS FEBRUARY 28, 1986 PROCEDURE NO.

TITLE REV. STATUS EPP 01-1.1 WCGS Organization 4 MAJOR SC EPP 01-1.2 Emergency Operation Facility 3 MAJOR SC Emergency Organization EPP 01-1.3 Home Office Em,ergency. Center 1 MAJOR SC Organization EPP 01-1.4 Public Information Organization 2 MAJOR.SC ~ EPP 01-2.1 Emergency Classification 2 MAJOR SC EPP 01-2.2 Activation of Emergency Plan / 2 MAJOR SC Organization ( EPP 01-2.3 Accident Assessment and 1 MAJOR SC Mitigation EPP 01-3.1 Innediate Notifications 3 MAJOR SC EPP 01-3.2 Followup Notifications 2 MAJOR SC EPP 01-3.3 Offsite Support Notification 2 MAJOR SC EPP 01-3.4 Onsite Emergency Response 1 MAJOR SC Organization Manual Call-Out EPP 01-3.5 EOF, HOEC and Public Information 2 MAJOR SC Emergency Response Organization Manual Call-Out EPP 01-3.6 KG&E Emergency Response O MAJOR SC Organization Automatic Call-Out EPP 0.1-4.1 Technical Support Center 3 MAJOR SC j Activation EPP 01-4.2 Operations Support Center 3 MAJOR SC Activation / Operation EPP 01-4.3 Emergency Operations Facility 3 MAJOR SC ~ . Activa, tion NP.P dl-4.4 'HomeOf'Eice'Eme'rgency,beter 'O MAJOR SC-Activation- -*s. ,z. Page 1 of 3 ..n

EPP TofC l Rev. 11 Fl( PROCEDURE NO. TITLE REV. STATUS EPP 01-4.5 General Office Activation 2 MAJOR SC EPP 01-4.6 Information Clearinghouse / Media 2 MAJOR SC Release Center Activation EPP 01-4.7 Emergency Response Facility 0 MAJOR SC Information System (ERFIS) EPP 01-5.1 Exclusion Area Evacuation 2 MAJOR SC EPP 01-6.1 Personnel Accountability 3 MAJOR SC EPP 01-7.1 Radiological Release Inf o rmation 3 MAJOR SC System (RRIS) EPP 01-7.2 Manual Determination of Release 5 MAJ0P. SC Rate EPP 01-7.3 Manual Dose Projection 5 MAJOR SC Determination EPP 01-8.1 Onsite Radiological Monitoring 4 MAJOR SC EPP 01-8.2 Offsite Radiological Monitoring 3 MAJOR SC EPP 01-8.3 Joint Radiological Monitoring 1 MAJOR SC Team Formation and Operation EPP 01-9.1 Exposure Control and Personnel 2 MAJOR SC Protection EPP 01-9.2 Personnel Decontamination 2 MAJOR SC EPP 01-9.3 Radioprotective Drugs 2 MAJOR SC EPP 01-9.4 Emergency Team Formation 3 MAJOR SC EPP 01-9.5 Aid to Contaminated / Injured 2 MAJOR SC Personnel EPP 01-10.1 Protective Action Recommendations 2 MAJOR SC EPP 01-10.2 Preparation of News Releases 2 MAJOR SC EPP 01-10.3 Release of Emergency-Related 2 MAJOR SC Information to the Public EPP 01-11.1 Communications 2 MAJOR SC \\ ~ \\ 1 .s Page 2 of 3 -.__-,,m .m__

EPP TofC Rev. 11 l PROCEDURE NO. TITLE REV. STATUS EPP-01-11.2 Status Boards 1 MAJOR SC EPP 01-11.3 Logs and Record Keeping O MAJOR SC EPP 01-12.1 Reentry and Recovery Operations 2 MAJOR SC EPP 02-1.1 Emergency Preparedness PP;ogram-2 MAJOR SC Maintenance EPP 02-1.2 TCN No. 02-1.2-1 3 MAJOR SC EPP 02-1.2 Training Programs 3 MAJOR SC EPP 02-1.3 Drills and Exercises 2 MAJOR SC EPP 02-1.4 Public Education 1 MAJOR SC EPP 02-1.5 Maintenance of Emergency 4 MAJOR SC Facilities and Equipment EPP 02-1.6 Communications Tests 1 MAJOR SC ( EPP 02-1.7 Tone Alert Radio Maintenance and 0 MAJOR SC Compensating Measures EPP 02-1.8 Testing and Maintenance of 1 MAJOR SC Public Alert System Sirens l h' i r. Page 3 of 3 -r - - - ---- - ~ ' ' '--~-" - ~ ' ' - ' ' '

KANSAS GAS & ELECTRIC COMPANY WOLF CREEK GENERATING STATION RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURE RADIOLOGICAL RELEASE INFORMATION SYSTEM (RRIS) EPP 01-7.1 Revision 3 C ?A / k )$ EMERGENCY PLANN,G COOR{INATOR REVIEW DATK / AAA Mnt D-/ 9 - 8 $ EMERGENCY PLANNING ADMINISTRATOR REVIEW DATE 0 A $f PS APP VAL RECOMMENDATION DATE / b) hl} VTP. tfUCLEAR nPPROVAC c.. DATE. ~ . s* ;i. g.,;...s ;; < s .. ' '

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\\ 1.0 PURPOSE This procedure provides guidance to dose projection / assessment personnel in the operation of the Radioactive Release Information System (RRIS). 2.0 APPLICABILITY This procedure is applicable to designated Control Room, Technical Support Center (TSC) and Emergency Operations Facility (EOF) dose projection / assessment l personnel during and after a radiological emergency. It shall be utilized after the RRIS is operable to automatically project or calculate the radiological doses and dose rates to the public surrounding the WCGS. 3.0 DEFINITIONS 3.1 RRIS Radioactive Release Information System 3.2 QKLOOK A fast running model in the RRIS which calculates ( offsite radiological conditions based on straight line gaussian dispersion. equations. 3.3 TOTPUF A more detailed dispersion model which tracks actual plume location and integrated doses and air concentrations. 3.4 X/Q A factor based on meteorological dispersion characteristics which relates atmospheric radionuclide release rates to offsite air concentrations. 3.5 EVENT A condition on the RRIS System, based on an automatic signal from the ERFIS computer, or a manually entered signal, which initiates automatic running of real time QKLOOK and TOTPUF models and recording of pre-event, l event and post-event data. ) l.' -: .'.$.. = -l ,_ V i.' {'.,. s;y.' _ l*:'~*~ y,4.:y.;..; :..>.. : -1.a.;... :: +..: a; 4.:.c.c.;..+.,.. r.yyy @'. ~ v ~~ EPp 01-7 ~ .r

r n 4.0 INSTRUCTIONS 4.1 - PRECAUTIONS l 4.1.1 If the RRIS is inoperable, immediately proceed to EPP 01-7.2, " Manual Determination of Release Rate" and EPP 01-7.3, " Manual Dose Projection Determination." 4.1.2 Master status, which involves the control of TOTPUF l and the editing of input parameters, will be transferred from the Control Room terminal to the TSC terminal to the EOF terminal as these facilities are staffed and activated. 4.1.2.1 Master status transfer should only occur when the l receiving facility is activated. 4.1.2.2 Master status should not be requested by a non-master l terminal without first contacting the master terminal operator by telephone. 4.1.3 All models begin running using real-time data when the l RRIS receives the Initiation of Event signal from the ERFIS computer. If the " Event in Progress" alarm is not listed on the RRIS alarm summary and a ( radiological release is in progress, the operator should manually initiate the event from the RRIS function menu. If a radiological release is not in progress, the operator shall not initiate an event until directed to do so by the DAC or DAS. 4.1.4 To assure that input data to the OKLOOK and TOTPUF l models is good, the operator should check the validity of the Met Tower Data, the Rad Data, Release Rate Data and the Effluent Flow / Fan inputs for each dose calculation update by selecting the data displays from the function menu (in realtime, not historical mode). Validation should be repeated if parameters change significantly. 4.1.4.1 Use the primary (or secondary) values automatically selected by the RRIS if these values are available and valid. 4.1.4.2 If the primary or secondary value is unavailable or l known to be incorrect and a correct value or estimate is known manually enter the value. The Control Room j must be called for Rad or Effluent Flow / Fan Data. Met Data must be telephoned from Met Tower. 4 ,EP.P.0'l.7.1.' c s i..r y..... ,L. 4. .q. -y.- . }te v (.~3 ' -, l. U. '. Page':2; 'of, '31 ~- lrS U.].. ' -y.T.z: 4 \\ ; :.c. ' /.e.Q. 'n. y :,h !.. e1.% 3 ..y..' ,.f s;. i 4 e - r - waM

A A 4.1.4.3 If none of these inputs are available, use default R:d l values determined from last " good" quality primary / secondary value. If there is reason to suspect that actual conditions may be worse, then use Step 4.1.4.4. l 4.1.4.4 Use predetermined, conservative release cases stored I in the RRIS in the absence of all the above data (see 0.0, " Predetermined Release Parameters Stored in RRIS Release Model"). 4.1.5 Once the release. point (s) have been identified, the l isotopic spectrum being used by the RRIS for a release point should be validated and updated as more recent sample information becomes available. 4.2 INITIAL ACTIONS l 4.2.1 Verify the red light on the CRT (health light) and the red light on the reset key on the upper left side of the keyboard are lit. If lights are lit, proceed to Step 4.2.2. If lights are not lit, perform the following: 4.2.1.1 Verify the ON/OFF switches on the right front sides of the CRT and the video generator are in the ON position. ( 4.2.1.2 Verify the~AC cords are plugged in. I \\ 4.2.1.3 If Steps 4.2.1.1 and 4.2.1.2 fail to correct the problem, proceed to EPP 01-7.2 and 01-7.3. 4.2.2 To initialize the system, press home key, wait a few I seconds and a display should appear. -If not, check to see if the key switch on the right side of the keyboard is in the vertical position. If the key switch is in the vertical position, RRIS is inoperable. Proceed to EPP 01-7.2 and 01-7.3. 4.2.3 Review Attachment 11.0, " Flowchart for RRIS Operator l Actions." l 4.2.4 TOTPUF Model l 4.2.4.1 Although not' displayed initially, TOTPUF is automa'ti-I cally initiated in sn event and should be left run-ning, in real time mode only, throughout the event. Predictive or historical modes should not be used for TOTPUF during an event. To see results of TOTPUF, "TOTPUF" should be selected from the "Model Display Selection" menu. "TOTPUF CONTROL" should not be selected from the function menu except as noted in -this procedure or the RRIS User's Manual (see Re,ference 5.4).

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i U 4.2.4.2 Map or tabular displays of: Air concentration - Gamma dose rate (whole body)~ - Beta dose rate provides indication of the actual and present location of the plume. Plume location on the site area maps is shown by operator selected isopleths (Attachment 6.0, "Isopleth Value Selection"). Tabular values are at distances of 3/4, 2, 5, 10, and 50 miles and at azimuths from 0.0 to 337.5 degrees at 22.5 degree i increments. 4.2.4.3 Map or tabular displays of: l - Time integrated air concentration - Gamma dose (whole body) - Beta dose - Tbyroid dose integrate these values for all areas of plume passage since the beginning of the TOTPUF model initiation. 4.2.4.4 Hardcopies of tabular data should be made (see l Attachments 2.0 through 5.0) when requested by the DAC/DAS or REC / RAM and at half hour intervals during the event to provide real time dose and dose rate information. C 4.2.4.5 If the maximum puff limit for the TOTPUF model is I reached, an alarm is displayed stating that only old puffs will be followed. If this occurs, go to.0, " Actions following " Maximum Puff Limit Reached - Only Old Puffs will be Followed" Alarm". 4.2.5 QKLOOK Model l 4.2.5.1 QKLOOK is automatically initiated and displayed on all l terminals (master and non-master) using real time data in an event. ("QKLOOK" must be selected on "Model Display Selection" to see QKLOOK results). 4.2.5.2 The straight line mode of QKLOOK displays isopleth or l tabular results for a single time interval (i.e. no integration of successive results) out to 50 miles for: - X/Q - Gamma dose (whole body) - Beta dose - Thyroid dose - Plume arrival time (tabular display only) Hardcopy records of tabular results are available. l 1 I.hg( 'l '+.i:.,- ~

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5.0 REFERENCES

5.1 WCGS Radiological Emergency Response Plan 5.2 EPP 01-7.2, " Manual Determination of Release Rate" 5.3 EPP 01-7.3, " Manual Dose Projection Determination" 5.4 RRIS-VAXIAA01-M2-0 Users Manual for the SNUPPS RRIS 6.0 RECORDS 6.1 For actual emergencies, all hardcopies/ photographs of data produced by the RRIS shall be retained by the ' REC / RAM. After the emergency has.been terminated, these hardcopies/ photographs shall be forwarded to the Emergency Planning Coordinator (EPC). The EPC shall forward these to the WCGS vault for storage. These records will be retained for the life of the plant. These shall be considered QA records. I + ,n. e. ~..>c..' ~ ..,.., '.. E P P.'.' O.l'. 7. 1.. u .f R e v._ 3 - .l i. Page 5 of..31 T. :=. !<' ;. ;>'..<.. J : ,.... ' '. t.- , ?.a i. : h,l...,....f,'*. g..k ; .b,.'..

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r .s m l A l((" ATTACHMENT 1.0 RADIOACTIVITY RELEASE RATE

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Description This display shows the release activity, flow rate, and release rate for each release point. Instruction 1. To see the display of Radioactivity Release Rate Summary, select with the lightpen the identifier next l to " RAD REL RATE

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" on the Function Menu. 2. Note the Function Menu is erased from the screen and the Radioactivity Release Rate Summary display appears on the screen. 3. Note that if any parameters were altered in the Radiological Data display or FLOW displays, the new value is shown in the Radioactivity Release Rate Summary, after the next 15 minute update. 4. To obtain a hardcopy, depress with the lightpen the l identifier next to "HARDCOPY" in the lower right hand corner of the screen. 5. .To return to the Function Menu, depress with the lightpen the identifier next to " FUNCTION MENU" in the j lower right hand corner of the screen. 6. Validity of the data used in the Radioactivity Release Rate Summary may be assessed by selecting the " RAD DATA" and the "EFF FLOW / FAN" displays from the function menu. l l f Y a..i - ..".'.L.. .,.. :. y..,..Rev.01-'1 L. .c..:l,. c, ; EPP : ^ .x .v ,3. .; p :

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4 1 6.- + a. i 'f ATTACHMENT 2.0 I( DISPLAY OF TABULAR DATA FOR X/Q Description X/Q's (QKLOOK Model only) are displayed for distances t" of 3/4, 2, 5, 10, and 50 miles from the power plant site and at azimuths of 0.0 to 337.5 degrees, in 22.5 degree increments. Instruction 1. To see the X/Q display, select with lightpen "X/Q" on l the Function Menu. 2. Note the Function Menu is erased from tne screen and the X/O display appears on the screen. 3. To obtain a hardcopy, depress with the lightpen the l identifier next to "HARDCOPY" in the lower right hand corner of the screen. ( 4. To return to the Function Menu, depress with the lightpen the identifier next_to " FUNCTION MENU" in the l lower right hand corner of the screen. i 1 I 1 ~ ...,.,. g e... -... E P P '01.7.'l ~ - .u.....-.,-,.,, .. R. ey. ;. 3 '. ' '. C $. * ' ' ' E *' a .e. ?: %d.. ; V,'.: v, '. <1 *t ; * *. .,,;r.- .r.,..:;,),,i.',,,.'.~;{..,.:t. Page'8. of 31. =.. ~... .~. :: ., ; : '., y ',t .,.....,.y. ~. ;..,

go y, .t. q"J, .f ATTACHMENT 3.0 DISPLAY OF TABULAR DATA FOR BETA GAMMA DOSE / DOSE RATE Description

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y.. Gamma Dose Rates (TOTPUF Model only) and Gamma. Doses are displayed for distances of 3/4, 2, 5, 10, and 50 miles from the power plant site and at azimuths'of 0.0 to 337.5 degrees, in~22.5 degree increments. Instructions 1. To see the Whole Body. Gamma Dose Rates display, select with the lightpen the identifier next to " DOSE RATE - l GAMMA" on the Function Menu. 2. Note the Function Menu is erased from the screen and the Whole Body Gamma Dose Rates display appears on the screen. 3. To obtain a hardcopy, depress with the lightpen the l identifier next to "HARDCOPY" in the lower right hand C corner of the screen. 4. To return to the Function Menu, depress with the lightpen the identifier next to " FUNCTION MENU" in the l lower right hand corner of the screen. 5. To see the Whole Body Gamma Dose display, select with the lightpen the identifier next to " DOSE - GAMMA" on j the Function Menu. 6. Note the Function Menu is erased from the screen and the Whole Body Gamma Dose display appears on the screen. l 7. To obtain a hardcopy, depress with the lightpen, the identifier next to "HARDCOPY" in the lower right hand corner of the screen. 8. To return to the Function Menu, depress with the lightpen the identifier next to " FUNCTION MENU" in the l lower right hand corner of the screen. 9. Repeat Steps 1 through 7 for BETA DOSE / DOSE RATE by selecting " DOSE RATE - BETA" and " DOSE - BETA" with the lightpen.

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4 a C ATTACHMENT 4.0 DISPLAY OF TABULAR DATA FOR THYROID INHALATION DOSE Description Inhalation Thyroid Doses (TOTPUF Model only) are displayed for distances of'3/4, 2, 5, 10, and 50 miles ~ from the power plant site and at azimuths of 0.0 to 337.5 degrees, in 22.5 degree increments. Instruction 1. To see the Inhalation Thyroid Dose display, select with the lightpen the identifier next to " DOSE - THYROID" on l the Function Menu. 2. Note the Function Menu is erased from the screen and the Inhalation Thyroid Dose display appears on the screen. 3. To obtain a hardcopy, depress with the lightpen the l identifier next to "HARDCOPY" in the lower right hand corner of the screen. 4. To return to the Function Menu, depress with the lightpen the identifier next to "FUNC. TION MENU" in the l lower right hand corner of the screen. 1 .i ..."3 -_,_. v,. < .gey,,9, .,\\. -('.;,.. _.?;. ,..... E PP' 01--7..l. , ::n,*:, r

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j i l ATTACHMINT 5.0 C DISPLAY OF TABULAR DATA FOR PLUME ARRIVAL TIME Description Arrival times (QKLOOK Model only) are displayed for distances of 3/4, 2, 5, 10, and 50 miles from the power plant site and at azimuths of 0.0 to 337.5 degrees, in 22.5 degree increments. The plume arrival time indicates the travel time in hours and minutes (for predictive cases) or the actual clock time (for real time cases) at which the plume would contact a particular point. It displays times at the locations described above if the location is within a distance of twice the horizontal dispersion coeffecient of the plume at the point on the plume where the distance from the radial location to the plume is measured. Instructions 1. To see the Plume Arrival display, select with the lightpen " PLUME ARRIVAL" on the Function Menu. l C 2. ~ Note the Function Menu is erased from the screen and the Plume Arrival display appears en the screen. 3. To obtain a hardcopy, depress with the lightpen the I identifier next to "HARDCOPY" in the lower right hand corner of the screen. 4. To return to the Function Menu, depress with the lightpen the identifier next to " FUNCTION MENU" in the - l lower right hand corner of the screen. i 1 f ~.. .q. ; i.,.,?p ?.. ...., ; p*. .,..,,; q,. _.;',' ..,ha n.,, -- . v-

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ATTACHMENT 6.0 (Page 1 of 3) l k ISOPLETH VALUE SELECTION Description The Isopleth Value Selection display allows the user to select up to five isopleth levels for.each of the follow-ing: X/Q, Air Concentration, Time-Integrated Air Concentra-tion, Thyroid Dose, Beta Dose, Beta Dose Rate, Gamma Dose, and Gamma Dose Rate. Suggested Isopleth values are shown - below. Desired isopleth levels must be selected before a model is run to be displayed on the map (RRIS will not 3 ]. recalculate QKLOOK isopleths after a model has run - see - Attachments 7.0 and 8.0). Suggested Isopleth Values Category Suggested Initial Isopleth Values %/Q 1.00 E-4 sec/m 3 1.00 E-5 1.00 E-6 1.00 E-7 1.00 E-8 Air concentration, 1.00 E-4 Ci/m or Ci-HR/m3 Time integrated air 1.00 E-6 concentration 1.00 E-8 1.00 E-10 Beta Dose 1.00 E+00 mR Gamma Dose 1.00 E+1 Thyroid Dose 1.00 E+2 Beta Dose Rate 1.00 E+3 Gamma Dose Rate 1.00 E+4 NOTE: TOTPUF model run time is dependent on the number of Isopleths selected (i.e., the more Isopleths chosen, the longer the model will take to run). Instructions l. To see the Isopleth Value Selection, select with the lightpen the identifier next to " SELECT ISOPLETH LEVEL" on l the Function Menu. 2. The Function Menu will be erased from the screen and the Isopleth Value Selection menu display will appear on the screen. ..". ;.1 - Q., - l A 'j hn... '. ' ~.?. ; p. : C- .. ' :L. * :. h'., S I- ~..*:? ~ , : l.. { . g.,; ...,., 3.- .s EPP 01-Cle N!."- f$4,::.]h'.:. ,4~'.Y y.';.?:'.0:;, *,:.;. k1 i:.'.: ;.'. S.f.i:.~??! *k :.:. ' h f g'. . 'W.'? Y 5 3---.-%,

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~ C ATTACHMENT 6.0 (Page 2 of 3) l ISOPLETH VALUE SELECTION 3. The display will list the following categories of isopleths; X/Q, Time-Integrated Air Concentration, Beta-Dose, Gamma-Dose, Air-Concentration, Thyroid Dose, Beta Dose Rate, Gamma Dose Rate. Each category may contain up to five isopleth levels. 4. All selection identifiers will be shown as disabled until you have chosen either " ADD" or " DELETE". 5. Select with the lightpen the identifier next, to " ADD". l 6. Note that the identifier is now highlighted and will' stay highlighted until another function selection has been made. 7. The identifier beside the next available calculation which you may add in each category is now shown in a solid line versus the dotted lines of the disabled identifiers signifying that it is enabled for addition. 8. Select with the lightpen the enabled identifier below l one of the displayed model output types for addition of isopleth level. 9. Note that the identifier is now highlighted and a prompt is given in the lower portion of the display to " ENTER THE NEW VALUE". 10. Type in the desired isopleth new value on the keyboard as shown on the display. Note: The new value will now be displayed and the identifier beside it now shows as disabled and is no longer highlighted. 11. The next available area, if any, will now show as enabled. 12. To delete an isopleth value, select with the lightpen l the identifier next to " DELETE". 13. Note that the highlighting for " ADD" has been removed and the identifier beside " DELETE" is now highlighted.

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s. l 1 C ATTACHMENT 6.0 (Page 3 of 3) ISOPLETH VALUE SELECTION 14. Note the selection identifiers with isopleth values are enabled and identifiers without isopleth values are now disabled. n-l 15. To make a deletion, select with the lightpen the identifier next to the value you wish to delete. 16. The isopleth level selected for deletion will be erased from the display, will no' longer be used for model calculations, and the identifier will be disabled. 17. To obtain a hardcopy, depress with the lightpen the l identifier next to "HARDCOPY" in the lower right hand corner of the screen. 18. To return to the Function Menu, depress with the lightpen, the identifier next to " FUNCTION MENU" in the lower right hand corner of the screen. i 1 r s. 7

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1 C ATTACHMENT 7.0 (Page 1 of 2) l OKLOOK DIFFUSION AND DOSE CALCULATIONS USING REAL TIME MET AND RAD DATA NOTE: The real time, straight line QKLOOK model starts running automatically when an event is ~'e initiated - no operator action is necessary. This instruction should be used to restart the real time mode after QKLOOK has been used for Historial or Predictive calculations. Description The QKLOOK model computes X/Q and dose values in either straight line mode or segmented modes. The model will compute.both isopleths and tabular data for the input data. In segmented mode, the model will run for as many time intervals selected or until the combined distance traveled (as computed by wind speed X time), for all intervals, equals fifty miles. In straight line mode, the model will run until it has processed all the intervals requested. Instructions 1. To see the QKLOOK Control Display, select with the lightpen the identifier next to "QKLOOK CONTROL" on the Function Menu. 2. The Function Menu will be erased from the screen and the QKLOOK Control display will appear on the screen. Note: When each page of model input is complete, a "DONE" identifier will be displayed at the bottom of the screen. When the user has checked all data input for accuracy and h'as mado hardcopics of the page (if desired), the user should select with the lightpen the identifier next to "DONE". This will enable the next page of data input (if needed) or a message indicating input is complete will be displayed. Selecting the " FUNCTION MENU" identifier before the input complete message has been displayed will cancel all input. .Y(.Q ;.,. '..c.;.G. t '.3 _f.,9&j.r..',.9.L.,+-Q.*Y'b1 l. 7,.+~ _ :[ l.'. i, ':\\ [ . y ,paye 1s:otf.5.;...g.,g -l ?. st

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, ~ v. . i. t ?: ATTACHMENT 7.0 (Page 2 of 2) l OKLOOK DIFFUSION AND DOSE CALCULATIONS USING REAL TIME MET AND RAD DATA 3. A prompt will be displayed to " SELECT PLUME TYPE:". l ^ ' 4. Select with the lightpen the identifier next to one of. l the plume types; segmented or straight line. 5. In segmented mode, the model tracks the radionuclides released during the first interval only, updating the results of that release for subsequent chaning meterological conditions. 6. In straight line mode, the model calculates results based on MET and RAD data for one interval at a time. 7. A prompt will be displayed to " SELECT RELEASE POINT:". 8. Select with the lightpen the identifier for the release l point desired. 9. A prompt will be displayed to " SELECT TIME FRAME:".

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P 4 g ATTACHMENT 8.0 j (Page 1 of 4) l k QKLOOK DIFFUSION AND DOSE CALCULATIONS USING PREDICTIVE MET AND RAD DATA NOTE: Only the straight line version of QKLOOK should be used for predictive cases. .;9. :;., c,.. Description The QKIDOK model computes X/Q values and doses using MET and RAD data for a single interval, calculating both tabular data and isopleths resulting from the input values. Up to ten successive intervals may be run; the model will run until it has processed all the intervals requested. To run the QKIDOK model in predictive mode, the user must enter all data manually. The RRIS System, however, provides default values from the data that is currently selected. Therefore, when preparing to run l QKLOOK in predictive mode, it may be helpful to select a historical period that contains data similar to that l desired for the predictive run. The default values are C i repeated for as many intervals as are selected for the run. The applicable default values from the selected l time are: 1. Stability, 2. 10 meter wind speed and wind direction, 3. If Radwaste or Unit Vent is selected, the default RMS values will be those for Noble Gas. Isotopic spectrum values will be zeroed. i Instructions 1. To see the QKLOOK Control Display, select with the lightpen the identifier next to "QKLOOK CONTROL" on the-l Function Menu. 4 l l f t ?.~.Q<.. 6.:... :. c.. -: ';;.. v -:., p : 9.: ; ;{q:. i..: +.7.%,.. . +.y: ';.: :.,.~?,f.. y ..s......e, ,c1ar.2 ' Nf.b.~.:: a.

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t ..J. ./ ? ATTACHMENT 8.0 (Page 2 of 4) l QKLOOK DIFFUSION AND DOSE CALCULATIONS USING PREDICTIVE MET AND RAD DATA 2. The Function Menu will be erased from the screen and the QKLOOK Control display will appear on the screen. N C Note: When each page of model input is complete, a "DONE" identifier will be displayed at the bottom of the screen. When the user has checked all data input for accuracy and has made hardcopies of the page (if desired), the user should select with the lightpen the identifier next to "DONE". This will enable the next page of data input (if needed) or a message indicating input is complete will be displayed. Selecting the " FUNCTION MENU" identifier before the input complete message has been displayed, will cancel all input. 3. A prompt will be displayed to " SELECT PLUME TYPE:". 4. Select with the lightpen the ident'fier next to l " Straight line". 5. A prompt will be displayed to " SELECT RELEASE POINT:". 6. Select with the lightpen the identifier for the release l point desired. 7. A prompt will be displayed to " SELECT TIME FRAME:". 8. Select with the lightpen ", PREDICTIVE". l 9. A prompt will be displayed to " ENTER # OF TIME SLOTS (1-10)". Note: If the user plans to run RELEASE, the start time will always be valid, but the model will only, generate doses using the data for the num-ber of time intervals specified in the release case chosen. Specifically, each release case will generate valid isotopic spectra for a pre-defined number of time intervals. For example, a user wants to run release case 1 for 20 his-torical time periods. Release case 1 will only return valid data for 12 time intervals; so the last 8 will return 0 for all nuclides. No warning will be given as to this event. r

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C u . C ATTACHMENT 8.0 (Page 3 of 4) l QKLOOK DIFFUSION AND DOSE CALCULATIONS USING PREDICTIVE MET AND RAD DATA 10. Enter the number of predictive segments to calculate on the keyboard. For a single case, one segment should be l "f ' ' N chosen. 11. At the time of the selection, the current display will be erased from the screen and the QKLOOK Control Meterological Data Input menu will be displayed, showing the default values from the time period selected. 12. A prompt is displayed to " SELECT METEROLOGICAL VALUE TO ALTER:". 13. Select with the lightpen the identifier next to the l meterological value you wish to alter. 14. If you selected a value under wind speed, a prompt will be displayed to " ENTER WIND SPEED". 15. Type in the new wind speed value on the keyboard. l 16. If you selected a value under wind direction, a prompt will be displayed to " ENTER WIND DIRECTION:". Type in the new wind direction value on the keyboard. The range is O degrees to 360 degrees. 17. If you selected a value undar stability class, a prompt will be displayed to " ENTER STABILITY CLASS:". Type in the new stability class value on the keyboard. l The valid values are A through G. 18. To obtain a hardcopy, depress with the lightpen, the identifier next to "HARDCOPY" in the lower right hand corner of the screen. 19. Select with the lightpen the identifier next to "DONE" l in the lower portion of the screen when inputting of meterological data is complete. 20. At the time of the selection, the current display will disappear and the QKLOOK Control RELEASE display will l I appear. l P s 'E P P ' 41-7,. I ~.- .y;p.;R.',j? ~.i.- ll9:,l,'*?; Eb ':D % -

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U. t X C ATTACHMENT 8.0 (Page 4 of 4) l QKLOOK DIFFUSION AND DOSE CALCULATIONS USING PREDICTIVE NET AND RAD DATA 21. A prompt "DO YOU WANT TO RUN RELEASE?" will be displayed. l Select with the lightpen the. identifier next to "YES" or "NO". 22. If "YES" was selected, a prompt will be displayed to " SELECT ONE RELEASE CASE"; following this selection, the "QKLOOK INPUT Complete" message will be displayed. To view results return to the FUNCTION MENU by selecting the " Function Menu" with the lightpen. 23. The Radiological / Flow Data input screen will appear if "NO" is selected. These values may be altered or the default values appearing may be used depending on the desired inputs for the predictive case. When inputs are completed, depress the "DONE" identifier. ( 24. The Isotopic Spectrum Data Input screen will appear (no default isotopic values ar_e_given); isotopes should be entered based on known or predicted isotopic concentrations as desired. Select the "DONE" identifier when isotope entry is complete. 25. The "QKLOOK INPUT Complete" message will appear on the screen. Return to the Function Menu to choose results to be displayed. NOTE: The QKLOOK Model is based on assumed interval lengths of 15 minutes. To project doses for longer periods of time than this, tabular dose results may be multiplied by the number of 15 minute segments in the desired predicted time. (For example, if the predicted dose for the next 3 hours is desired, the tabular QKLOOK doses should be multiplied by 12, which is the number of 15-minute intervals in 3 hours. If total credicted doses are desired, tabular results o1 QKLOOK projected doses should be added to the tabular doses at corresponding locations as obtained by the real time TOTPUF l outputs. ..f . E PP 01-7'.'l- .. ',N ~ } R'{ vse- ., iff.,.. M : 4y,,g s f,'; v<N v .. ",..il..,i - ' i - t.. -; t,c;:l-. -9..

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r. - g-ATTACHMENT 9.0 {k (Page 1 of 2) l ACTIONS FOLLOWING " MAXIMUM PUFF LIMIT REACHED - ONLY OLD PUFFS WILL BE FOLLOWED" ALARM ^ If the Release release rate magnitude is stable or increasing at the time the alarm is received, perform Section "A" below. If the magnitude of the release rate is fr decreasing rapidly or.is significantly less than the peak value when the alarm is received, perform Section "B". A. Since maximum projected doses and dose rates will be nearest the release point while releases are occurring, it is important to continue calculating these near-site conditions. The effect of " losing" more distant puffs that have already dispersed is acceptable in this case (these puffs may be added back in at a later time by re-running TOTPUF in historical mode). The steps to be followed, therefore, are: 1. Obtain tabular hardcopies of all dose, dose rate, and air concentration values (these tabular results may'be added to subsequent tabular results for total resulting doses and integrated air concentrations). C-2. Restart.TOTPUF in Real Time Mode by: a. Selecting "TOTPUF Control" from the Function 'l Menu using the lightpen. b. Selecting the box next to "REAL TIME" when prompted. Following the display of the "TOTPUF input complete" message, return to the Function Menu by selecting the Function Menu box with the lightpen. 3. Steps (1) and (2) above should be performed as quickly as possible to prevent the loss of information (preferably early in the same interval in which the alarm is received). }c-!. ;. 4('. i,.?'.:._.f :.. l' ?. ia'.. D. ~ *:::, ' :. - Q;y* '..': ' ,',A. ' \\$.,.l:':. * *.' '!:, ;.'k e v i'._$ ' '. ' < b.':.,: . ). :. EPP Gl-7.1 1

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ATTACHMENT 9.0 C (Page 2 of 2) l B. Since no new significant doses or dose rates are being added in this case, it is more important to continue following puffs already released. The steps to be followed are: 1. As long as release rates.are small, continue to allow TOTPUF to run until puffs are outside the area of interest (old puff location can be tracked with " Air Concentration" or Gamma, Beta, or Thyroid " DOSE" isopleth displays). Important: Release Rates (on RAD data or Release Rate Summary Displays) should be observed frequently during this time: if release rates begin to increase significantly, immediately perform Section "A" of this attachment) 2. When old puffs are outside the area of interest, hardcopy all tabular results and re-initiate a new real time TOTPUF run as in Section "A" above. ( ~ .,.I \\ '. '. '.". '.'. ' ~ 'l'; * * *

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s. ATTACHMENT 10.0 (Page 1 of 8) PREDETERMINED RELEASE PARAMETERS STORED IN RRIS RELEASE MODEL r -- RELEASE CASE 1 4 Case 1 is a fuel handling accident in the Fuel Building. Table 10.1 lists the assumptions including ~the initial air concentration of activity in the Fuel Building. The accident assumes 1 fuel assembly out of 193 fuel assemblies'is involved in the accident. The accident starts when activity from one assembly enters the atmosphere of the fuel handling building. The activity is assumed to be released to-the environment via the building exhaust at the rate of 9000 CFM. Ninety percent of the Iodine is filtered out by the exhaust filters. The noble gases are not filtered. The set up of the release input assumes the activity-is initially in the Fuel Building. The flow rate out of the building is equal to 0.593 vol/hr. ( 'EPP.01 7.1. F'll *. g..

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ATTACHMENT 10.0 g C (Page 2 of 8) TABLE 10.1 FUEL-HANDLING ACCIDENT IN FUEL BUILDING Initial Concentration Initial Activity Isotope in Fuel Bldg (uCi/cc) in Fuel Bldg (Curies) I-131 2.073 E-2 5.34 E+2 I-132 5.465 E-15 1.41 E-10 y I-133 2.422 E-3 6.22 E+1 I-134 0 0 I-135' 2.031 E-6 5.23 E-2 Kr-83m 7.944 E-17 5.23 E-12 Kr-85 1.454 E-1 3.75 E+3 Kr-85m 1.891 E-7 4.87 E-3 Kr-87 0 0 Kr-88 5.151~E-ll 1.33 E-6 Kr-89 0 0 Xe-131m 2.413 E-2 6.22 E+2 Xe-133m. 4.661 E-2 1.20 E+3 Xe-133 3.846 9.91 E+4 Xe-135m 0 0 ( Xe-135 3.187 E-3 8.21 E+1 {k Xe-137 0 0 Xe-138 0 0 Accident Assumptions l Volume of building =910,000 ft Building exhaust flow rate 9,000 CFM = 0.593 Vol/HR Volume release rate = Exhaust filter efficiency (for iodines) 90 % = Release is from one assembly out of 193 fuel assemblies Release duration 2 hours = Initial activity in fuel building is given above.

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ATTACHMENT 10.0 ( j (Page 3 of 8) l k RELEASE CASE 2 Case 2 is-a fuel handling accident in the Containment Building. The assumptions for case 2 are given in Table 10.2. The release model assumes initial activity is in the Containment Building. Only the leak path from containment to the environment via the Auxiliary Building and filter is calculated. The flow rate from containment to the Aux Building is 7.50 E-05 Vol/Hr. The flow rate from the Auxiliary Building to the environment is 0.318 Vol/Hr. f f EPP 01-7.1 i ,./.,~:. .',':,Y.,'.,i, c.. ' s, ~, ,1,. <~ ' ir.. :,,' j. {, he y,, 3 i, e,;.1;;; .m. pagg _25 og..r,31 ;. ': - t i,y _,. .t !i :,2-),,! i, - .:.:z o, ,,,. ;'., c,. [,,.,,......,,,.. :.. ; . -),,..... .c r- ,o

ATTACHMENT 10.0 C (Page 4 of 8)- l TABLE 10.2 FUEL-HANDLING ACCIDENT IN CONTAINMENT Initial Concentration Initial Activity Isotope in Ctat (uCi/cc) in Ctmt (Curies) ~~' I-131 9.053 E-3 6.41 E+2 I-132 2.387 E-15 1.69 E-10 I-133 1.058 E-3 7.49 E+01 I-134 0 0 I-135 8.870 E-7 6.28 E-2 Kr-83m 3.470 E-17 2.46 E-12 Kr-85 6.352 E-2 4.50 E+3 Kr-85m 8.262 E-8 5.85 E-3 Kr-87 0 0 Kr-88 2.250 E-ll 1.59 E-6 Kr-89 0 0 Xe-131m 1.054 E-2 7.46 E+2 Xe-133m 2.036 E-2 1.44 E+3 Xe-13 3 - 1.680 1.19 E+5 Xe-135m 0 0 ( Xe-135 1.392 E-3 9.86 E+1 Xe-137 0 0 Xe-138 0 0 Accident Assumptions: Free volume in containment 2,500,000 ft = 1,700,000 ft Volume of Aux Bldg = 0.02% volume / day Leak rate from containment to environment = 0.18% volume / day Leak rate from containment to Aux Bldg = 9,000 CFM Aux Bldg flow rate = Exhaust filter efficiency ( for iodines) 90% = Release is frem 1.2 assemblies out of 193 fuel assemblies. Initial activity in containment is given above. EPP'01-7.1 . :c.,.? ', ?..i' R,'. M. : .,N..,. .3., '. ., N ',,'.$! I'Y ' l' ", 5.; ?Eev~." 3 ~ &.'o 'i *.*N ': : *'~. l l.', f I +l.,..,...'...'.*l ,.y ,,,,q .P 2 6 'o f ".n31, /. '..

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i m_ ] s f ATTACHMENT 10.0 (Page 5 of 8) l RELEASE CASE 3 Case 3 is a loss of coolant accident (LOCA). The assumptions for case 3 are given in Table 10.3. The leak rate from the containment to the environment is 8.33 E-06.Vol/ day. All initial activity is assumed to be in the Containment Building. l ] ~ EPP.01-7.l..., ?....;.y:,.' t. ..,,,'6 i..,-

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5-L' ATTACHMENT 10.0 (Page 6 of 8) l TABLE 10.3 LOSS OF COOLANT ACCIDENT (LOCA) Initial Concentration Initial Activity Isotope in Ctmt (uCi/cc) in Ctmt (Curies) 1 I-131 3.157 E+2 2.24 E+7 j - I-132 4.792 E+2 3.39 E+7 I-133 7.077 E+2 5.01 E+7 I-134 8.278 E+2 5.86 E+7 I-135 6.424 E+2 4.55 E+7 Kr-83m 2.091 E+2 1.48 E+7 Kr-85 2.065 E+1 1.46 E+6 Kr-85m 6.532 0+2 4.62 E+7 Kr-87 1.176 E+3 8.33 E+7 Kr-88 1.612 E+3 1.14 E+8 Kr-89 2.004 E+3 1.42 E+8 Xe-131m 1.307 E+1 9.25 E+5 Xe-133m 6.970 E+1 4.93 E+6 Xe-133 2.831 E+3 2.00 E+8 Xe-135m 7.841 E+2 5.55 E+7 Xe-135 2.701 E+3 1.91 E+8 ( - Xe-138 2.404 E+3 1.70 E+8 Xe-137 2.569 E+3 1.82 E+8 Accident Assumptions: l Free volume of containment =2,500,000 ft 0.02%/ day Containment leak rate to environment = Initial activity in containment given above. l 'll ?{*' l b.. J'i '.EPP. 01-7.1 ..l h j ' -{.i '. !.6. *.'. '. C'.. *' n,.. ',.,'.).. .. aRe v;..'3 l~, ;? **?, i;'..*, 'i.*

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K 7 . k-1. '( ATTACHMENT 10.0 l l( (Page 8 of 8) I TABLE 10.4 WASTE GAS TANK RUPTURE Activity Released to 'jMb Isotope Radwaste Bldg (Curies) I-131 8.30 E-1 I-132 3.80 E-3 I-133 1.60 E-1 I-134 7.50 E-4 I-135 2.60 E-2 Xe-131m 5.14 E+2 Xe-133m 1.68 E+2 Xe-133 1.25 E+4 Xe-135m 1.40 E-1 Xe-135 3.28 E+2 Xe-138 1.60 E-1 KR-85m 4.35 E+1 Kr-85 7.66 E+3 Kr-87 4.20 E+0 Kr-88 4.25 E+1 ( Accident Assumptions: Radwaste bldg volume =1,120,000 ft '12,000 CFM Exhaust flow = Exhaust filter efficiency (for iodines) = 90% Volume Release Rate = 0.640 Vol/HR Activity from tank is ar,sumed released to Radwaste Building. . EPP 01.7.1- .;*,C,. ' '..,*. e,,-(?.,1....,,,,j 1.cf.,c/,.' g..;:.,i.!s,ge f,): 7; - ' t..'!.Q:., l p,9,.3 g 7,g, j,4.'.i.,:., q f.,y,,',',] L 3;. if;. l .~ 3 5 Q,..,; ( ~, ~ - . *,,..,:.~ : .c t.'- q.Q :.Q.~;h..... '....y..,.,...n.;..:.... A;:. ;.,s. y,;. y;;9,g:;;.9. ::..j:,.; u..). ;},:;,:.,;.\\,..,;.i.. ;;.... ^- = > +. = .4 a.. me w4.m4% ,y.... %g

r c 4.~, .v: r n ATTACHMENT 11.0 I FLOWC'MhdT FOR RRIS OPERATOR ACTIONS l Assure Terminal Operable l 4..- %f Acquire Master Status (if appropriate) .\\/ Initiate event if not already initiated by ERFIS Signal (See Step 4.1.3) V Assure validity of Input l Data (hardcopy results as required) C /\\ \\/ Reverify for Dose Calculations, each dose update A Sr S/ Real time: Predictive: TOTPUF (See Step QKLOOK (See 4.3.1) (QKLOOK Step 4.3.2) l may also be used) \\/ 5/ Report / Record results as required I l i EPP 01-7.1 1 .......;: e i.J.c.. ; & :. ;.J;<! '.>; n.i. : :.'-[:'..... l:. l.:.i.L.3.,(.. i.'. '... l n p e;3.1 m at.,,'.,f.,,'.:;

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.~j KANSAS GAS AND ELECTRIC COMPANY WOLF CREEK GENERATING STATION RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURE MANUAL DETERMINATION OF RELEASE RATE EPP 01-7.2 Revision 5 ^ / PA ] A /T W{ EMERGENDY PLAN NG COORDI ATOR REVIEW DATE / / ~ )$ Oum 2 - / W -f f EMERGENCY PLANNING ADMINISTRATOR REVIEW DATE / h }} PSRC APP VAL COMMENDATION DAp /' i Ah $7h l V.P. LEAR APPROVAL DATE RELEASED M .2 FI, DATE 6

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.z 'c; ~ !; ' 2 A 1.0 PURPOSE 1.1 This procedure provides guidance and instruction for determining release rates of airborne radioactivity when the Radiological Release Information System (RRIS) is inoperable during emergency conditions at Wolf Creek Generating Station (WCGS). m 2.0 APPLICABILITY ..w i 2.1 This procedure shall be utilized when the RRIS com- ~ puter is inoperable during emergency conditions. 2.2 The estimated release rate and total release values calculated in accordance with this procedure shall be used in conjunction with EPP 01-7.3, " Manual Dose Projection Determination" and EPP 01-10.1, " Protective Action Recommendations", as a basis for determining what offsite protective actions should be recommended 4 to State and County officials. j 2.3 This procedure will be implemented by WCGS emergency l response personnel in the following manner: i 2.3.1 Prior to manning the Technical Support Center (TSC), 1 Control Room personnel who are trained in this pro-cedure, shall perform these calculations. I 2.3.2 After the TSC is activated, but prior to the activation of the Emergency Operations Facility (EOF), Dose Assessment Coordinator (DAC) shall assure that i the RRIS Operator implements this procedure. 4 2.3.3 Upon activation of the EOF, the Radiological Assess-ment Manager (RAM) shall assure that the RRIS operator l implements this procedure. ( j 3.0 DEFINITIONS s i 3.1 RELEASE RATE The quantity of radioactive material being released to t the environment expressed in curies per second (Ci/sec).- i 3.2 SOURCE TERM The calculated quantity of radioactive material avail-able for release or being released to the i environment. i .} 3

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4 -,1 Ls' 4.0 INSTRUCTIONS 4.1 PRECAUTIONS I i 4.1.1 Calculations contained in this procedure should be reviewed by the DED or REC at the TSC, or the DEM or RAM at the EOF, prior to changing the Status Board or dissemination of results to other emergency response personnel. 4.1.2 Upon activation of the EOF, the RRIS Operator and/or l Dose Assessment Supervisor (DAS) shall have the RAM or DEM review intermediate calculations, when appropriate. 4.1.3 Review of offsite determination of release rates will i be performed by the DAC/DAS. 4.2 INITIAL ACTIONS 4.2.1 The DAC or DAS, as appropriate, shall: l '4.2.1.1 If RRIS is inoperable, assure the completion of.0, "Onsite Determination of Vent Release Rate," Form EP 7.2-1 ( 4.2.1.2 If vent monitor (s) are inoperable, consider the dis-patch of Onsite Survey Team (s) to collect appropriate grab samples from the unmonitored locations in accordance with CHM 01-007, " Sampling of Unit and Radwaste Vents for Radioactive Gases and Tritium" or l CHM 01-005, " Exchange of Unit and Radwaste Vent Parti-culate and Iodine Filter Cartridges." 4.2.1.2.1 Recommend that Offsite Monitoring Teams be dispatched to determine offsite dose rates in accordance with EPP 01-8.2, "Offsite Radiological Monitoring." 4.2.1.2.2 Record results on Attachment 1.0. 4.2.1.3 If a steam generator tube rupture is suspected or verified, assure the completion of Attachment 4.0, " Steam Generator Tube Rupture Release Rate Determina-tion," Form EP 7.2-4. f .,_.: 9. <.

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G. ' [., ? y. \\ i. \\ g' 4 4.2.1.4 As required to calculate the release rate using off-I f~ site data (backcalculations), assure the completion of ~ Attachinant 5.0, " Release Rate Calculation Using Offsite Field Team Data (Backcalculations)", Form EP 7.2-5. 4.2.1.5 To determine the containment leak rate contribution to the containment release rate, assure the completion of.0, " Containment Release Rate Calculation," Form EP 7.2-6. 4.2.1.6 Review completed Attachments. 4.2.1.7 Inform REC / RAM of results. 4.3 SUBSEQUENT ACTIONS 4.3.1 The DAC/DAS shall: 4.3.1.1 Continue to evaluate the results supplied by the attachments. 4.3.1.2 As new results are received, assure d ey are posted on the appropriate Status Boards. 5.O REFERENCES 5.1 WCGS Radiological Emergency Response Plan 5.2 EPP 01-7.3, " Manual Dose Projection Determination" 5.3 EPP 01-10.1, " Protective Action Recommendations" l 5.4 WCGS Final Safety Analysis Report, Chapter 15.0 1 5.5 CHM 01-005, " Exchange of Unit and Radwaste Vent I Particulate and Iodine Filter Cartridges" l 5.6 CHM 01-007, " Sampling of Unit and Radwaste Vents for l l Radioactive Gas and Tritium" 6.0 RECORDS 6.1 Form EP 7.2-1 "Onsite Determination of Vent Release Rate" 6.2 Form EP 7.2-2 " Exhaust Fan Status" 6.3 Form EP 7.2-4 " Steam Generator Tube Rupture Release Rate Determination" '...!. '.:. a. ',.'. ' k ) :..f,;. ':.f'. :.-Q$ l.~~ *l ' ' %.,,l.,'.,* *.h:.',' '. '- l i f.".-l,l 'h, N '.b. U.'**b.{.5b ,'Q '.'y,,. ; ;y 'y,_ *' .., ' -^*'.-l A' 6' : ', EPP D1~ 7. 2 * : (,,.. '. : ~ /:.. l %. - 5 Rev. 5. ., e ;. l:..).,. ' i. H.., - [ \\ .' 'a:' P'ag e

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f ..o., .:s. 4 I 6.4 Form EP 7.2-5 " Release. Rate Calculation Using offsite Field Team Data (Backcalculations)" 6.5 Form EP 7.2-6 " Containment Release Rate Calculation" 6.6 The records generated by this procedure during an actual emergency shall be forwarded to the Emergency Planning Coordinator (EPC) at the termination of the emergency. The EPC forwards the records to the WCGS vault for storage. These records will be retained for the life of the plant. These records shall be j considered QA records. l 6.7 The records generated by this procedure during drills j and exercise shall be forwarded to the EPC upon termi-i nation of the drill or exercise. The EPC shall main-4 tain these records for at least one year. These records shall be considered non-QA records. i 7.O ATTACHMENTS 7.1.0, "Onsite Determination'of Vent Release Rate" i 7.2.O, " Exhaust Fan Status" 7.3.0, " Design Basis Accident Release Rates" 7.4.0, " Steam Generator Tube Rupture Release Rate Determination" 7.5.0, " Release Rate Calculation Using Offsite Field Team Data i (Backcalculations)" j 7.6.0, " Containment Release Rate Calculation" i i i i l.,' f '. f., :.'.. r ',

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FORM EP 7.2-1 REV. 1 ATTACHPE!NT 1.0 I (Page 1 cf 2) ONSITE DETERMINATION OF VENT RELEASE RATE l (See Back for Instructions) DATE: TIME:

1 UNIT VENT FIDW RATE =

QM O Caiculated (from Attachment 2.0) Measured

2 UNIT VENT CONCENTRATION =

uCi/cc Noble Gas C Monitor O Plant Sanple C Default Value l $3 UNIT VENT CONCENTRATION = uCi/cc Iodine O Monitor O Plant Sanple C Default Value l UNIT VENT RELEASE RATE =

4

( uCi/cc) ( CEM) (4.72E-4) = Ci/sec Noble Gas t5 ( uCi/cc)( CEN) (4.72E-4) = Ci/sec Iodine N $6 RADWASTE VENT FLOW RATE = CEM O Calculated (fran Attachment 2.0) O Measurea $7 RADWASTE VENT CONCENTRATION = uCi/cc Noble Gas O Monitor O Plant Sanple Default Value l 98 RADWASTE VENT CONCENTRATION = UCi/cc Iodine O Monitor C Plant Saaple O oefault value I RADWASTE VENT RELEASE RATE = Concentration X Flow Rate X Conversion Factor = Release Rate f9 ( uCi/cc)( CEM) (4.72E-4) = Ci/sec Noble Gas

10 (

uCi/cc) ( CFM) (4.72E-4) = Ci/sec Iodine 'IUTAL RELEASE RATE = l

11 Unit Vent Release Radwaste Vent Release Total Noble Gas Rate (Noble Gas)

Rate (Noble Gas) Release Rate j i

4

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= Noble Gas $12 Unit Vent Release Radwaste Vent Release Total Iodine Rate (Iodine) Rate (Iodine) Release Rate ] U. # ti/sec,Q.,t/.' { i,j,*.p... ,, *

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A'ITACHMENI' l.0 (Page 2 of 2) INSTRUCIONS {f l Obtain Radiation Monitting System (RMS) readings from the Control ( Rom for the Unit %nt and/or Ra&aste Vent flw rate (s) in cubic feet per minute (CEN) and insert at Its #1 and #6, respectively. If vent flw rate is unavailable, determine flw rate by using i EPP 01-7.2, Attachment 2.0, " Exhaust Fan Status," Form EP 7.2-2. 1

2 Obtain the noble gas activity concentration (uCi/cc) of the unit vent from the BMS display. If vent monitor is out of service, refer to Onsite Survey Team data or Attaclinent 3.0, " Design Basis Accident l

Release Rates."

3 Obtain iodine activity concentration (uci/cc) of the unit vent fra the RMS display.

If vent monitor is offscale or out of service, refer to Onsite Survey Team data or Attachment 3.0, " Design Basis Accident Release Rates."

4 Multiply concentration in Item #2 by flw rate in Its #1 and the conversion factor to obtain release rate of noble gas through the unit vent.

45 Multiply concentration in Its #3 by flw rate in Its #1 and the conversion factor to obtain release rate of iodine through the unit vent. 6 See Item #1, then proceed to Item #7. l

7 Obtain the noble gas activity concentration (uCi/cc) of the ra&aste vent from the PMS display. If vent monitor is out of service, refer to Onsite Survey Team data or Attachment 3.0, " Design Basis Accident Release Rates."
8 Obtain iodine activity concentration (uCi/cc) of the ra & aste vent from the RMS display. If vent monitor is offscale or out of service, refer to Onsite survey Team data or Attachment 3.0, " Design Basis Accident Release Rates."
9 Multiply concentration in Its #7 by flw rate in Item 46 and the conversion factor to obtain release rate of noble gas through the ra&aste vent.

I

10 Multiply concentration in Iten 48 by flw rate in Its #6 and the conversion factor to obtain release rate of iodine through the ra&aste vent.
11 Add the release rate in Itan #4 and the release rate in Its #9 to obtain the total release rate of noble gas.
12 Add the release rate in It m #5 and the release rate in It s #10 to obtain the total release rate of iodine.

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REM EP 7.2-2 REL 0 ATDGMENT 2.0 EXh7 CST FAN STE.3 NorE: Ccritact Q:ritrol Rcm for fan status Exhaust Fan Design Enter Design Systen ID nw n w on Unit Vent Flw CEID3A 12,000 (sl w) Aux Bldg HVAC 32,000 fast CEM CEID3B 12,000 (sl w) 32,000 fast CEM 4 i Contrra Bldg CE02A 6,000 CEM HVAC CLK02B 6,000 CEM l Ebel Bldg CDG02A 9,000 CEM HVAC CDG02B 9,000 CEM C Remcr/al HVAC ~ Cordersser Air CE013 1,000 CEM CGE01A 1,000 CEM Ccritainment cur 01 20,000 CEM Purge Exhaust cur 02 4,000 I CEM i Main Steam CT03A 17,000 CEM Enclosure Billriing Exhaust Fans CG03B 17,000 CEM Unit Vent Total nN CEM l Radwaea Vent Flow Radwaste CCH01A 12,000 CEM Biibiing Exhaust CmolB 12,000 CEM Radwaste Vent Total Flow CEM i y-EPP 01 0.2.

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ATDOttENP 3.0 (Page 1 of 1) IISIGN BASIS AOCIIENT REIBSE IUm3 FSAR Secticn Type of Accident Release Rate (Ci/sec) Iodine patio. Noble Gas 15.6-6 IOCA Noble Gas 27.92 0.087 Iodine 2.44 15.1-3 Main Steam Line Bcuak (Nost 14=4tLm!) Noble Gas 0.00066 15.15 Iodine 0.01 15.2-3 Ices of E.. pJf AC Noble Gas 0.00066 0.14 Icdine 0.000092 \\ 15.3-3 Iocked Roter Nctle Gas 0.83 0.005 Icdine 0.0042 15.4-4 RCIA Ejectica$ l Ncble Gas 0.06 0.006 Icdine 0.0034 15.6-2 CWS Imtdeun Line Break Outside Cor*m4==rit Neble Gas 0.08 0.006 Iodine 0.00046 15.6-4 Steam Generattr 'Iube Rupture Nchle Gas 0.29 0.38 ( Icdine 0.11 15.7-7 Ibel Handling Arw 4riant Noble Gas 14.52 0.0007 Iodine 0.01 15.7-3 Wasta Gas Decay Tank Rupture Noble Gas 2.95 0.00007 Iodine 0.0002 Steam 'Iurbine Dtivun Aw4114=7 Feed Pung PAL 02 Noble Gas 1.40 0.014 Iodine 0.02

Precaution: If given the Noble Gas ocncentraticn cnly, alltiply by ratio to obtain the Iodine canoentraticm. If given the Iodine concentration cnly, divide by ratio to obtain the Hable Gas ocncentration.

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A PGM EP 7.2-4 REV. 1 ATI7GMENT 4.0 (Page 1 of 2) srEAM GENERAER 'IUBE BUPIURE REIEASE PATE IEIERMDiATICH (See Back for Instructials) ImTE: TIME: Steam Flow Rate Determinaticn il Release Rato Determinaticm A. Affected Steam Flow (llafar) x Release Valve (ar/hr) lbn.mr = Mcmiter Reading hr hr_ S/G-A x = S/&B x = S/G-C x = S/G-D x = 'IUIAL =

2 Noble Gas Release Ra*a TUIAL x conversion factor = Noble Gas Relanc:a Rate x 1.44E-5 Ci/sec C1/sec

= tr/hr. Ibyhr

3 Iodir.e Release Ra*a N6ble Gas Release Rate x ocmersion factor = Ioiine Release Rate C1/sec x 38 Ci/sec

= Performed By: Reviewed By: EPP 01-7.2 / ?. ..s....., ;, j

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1 Obtain the steam flow rate (s) (llzVhr) fran the affected steem generator (s) steam line and insert into the first half of the egaation.

Obtain the release valve mztitar reading (mr/hr) frun the omtrol Roca cr EMS and insert into the second half of the equaticn. If the release valve monitors are out of service, insert the am e late roble gas / iodine ratio from EPP 01-7.2, Attachment 3.0, " Design Basis Accident Release Rates." Multiply the two halves to obtain a release rate de* amination for each affected steam generator. Add all the release rata determinations to octain a 'IUIAL.

2 Multiply the 'IUIAL (frca #1) by the conversion factor to obtain the ncble gas release ra*a (Ci/sec).

l

3 Multiply the noble gas release rate by the conversion factor to obtain the iodine release ra*a (C1/sec).
4 Rem results to DAc (Tsc) or DAs (IDF).

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PURM EP 7.2-5 REV. 1 l ATDalMENT 5.0 (Page 1 of 2) I RELEASE PATE CAICJIATION USING Ortsur I( rn.1D TEAM DA2A (Backcalculations) DATE: TIME: IDCATICH

1 hhole Body Dose Rate to Noble Gas Cbncentration 3

mRetq/Hr Ci/m Noble Gas l 3.36E 4 *

2 Offsite Concentraticrt(s) to Plant Release Rate (s) 3 Carmikation (uCi/cc or Ci/m )

C1/sec = X/Q value (sec/m') 3 Ci/m Ci/sec Noble Gas = J sec/m Release Rate

3 uC1/cx::

Ci/sec Iodine (NOTE: Use this if 3 sec/m Release data is ( Rate available; Otre.rwise, P.W to Step 4).

4 Iodine Release Rate Estimate (Offsite Iodine Corwikation Unknown)

Note: Skip this step if step 3 is ocupleted. Noble Gas Release Rate x Attachment 3.0 Iodine / Noble Gas Rt.t.io = Iodine Release Rate Ci/sec x Ci/sec Iodire Release Rate = Pet *. formed by Reviewed by: i Assu:qrdens:

1) Offsite dose rate measured httile submarM in smi-infinite cloud.

2) All ncble gas relnawi is Xe-133.

3)

Dose rate conversion factor is 3.36 E 4 rxem x m' hased on 1 arxi 2 Hr. C1 above. ,~}UIE: 1 C1/m3, 'y, uCi/oc

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REM EP 7,2-5 REV. 1 ATDGMENT 5.0 (Page 2 of 2) neuu.ums

1 Obtain gama (closed wirdow) Wie body dose rata readings at a locati:n cm or naar a known X/Q value and record. 'Ihis locati:n is datamined by using the mapa and proper stability rla== isopleths available in the amargency lochers.

Insert this reading into the left side of the equaticn. Divide the reading by the acmversion factor to obtain the noble gas concentration at that locaticm.

2 Divida the noble gas cxmountration by the kncun X/Q value to obtain the noble gas release rata.
'3 Obtain the iodine wwibation at the location fr=2 the DAC or DM.

If reading is unavailable, refer to step #4. ( Divida this wa.m.stLation by the known X/Q value to obtain the iodine release rate.

4*

Refer to EPP 01-7.2, At**M 3.0 to obtain the aw, late iodine /ncble gas ratio. Multiply this ratio by the w a ikation in step #1 to obtain the iodine release rate.

5 Report results to DAC (ISC) or DAS (EOF).

Note: Skip this step if step 3 is empleted.

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.~ 3 i g;>.=. e FORM EP 7.2-6 REV. 1 l A'ITACHMEN'r 6.0 f (Page 1 of 3) 7,- P CONTAIMENT RELEASE RATE CAICJEATION . ATE: TIME: ~ 1. In-Contalment Hi-Range Monitor Reading R/hr 2. Time Post Accident in Hours hour (s) 3. From Table below select the Ci/R/hr from the block beneath the hour block that corresponds to hour (s) in 2 above. l Post Reactor Trip Hours 0 1 3 10 24 Ci/R/hr 86 160 270 500 1200 I and record (Ci/R/hr) l 4. Calculation for DBA Leak Rate. a. In-Containment Monitors: { ~Contairnent " Curies per ~ ~ Conversion ~ Hi-Range Monitor x R per hour x Factor DBA % Ci/sec ( = .. Reading _from step 3_ _of free voltane_. ~1 R/hr x Ci/R/hr x 2.32E-8 sec Ci/see = i b. Containment Air Sample DBA Leak Rate x Contairinent Concentration 3 3 1.64 E-3 m /sec x Ci/m Ci/sec = 5. Calculation for known or estimated leak rate if other than DBA leak rate. a. In-Containment Monitors: l 1 ~ ~ Containment " Curies per ~ ~KnownorEsgimated" l Hi Range Monitor x .R per hour x Flow Rate m /sec C1/sec = _ Reading _from step 3,,, V Voltane m' 3 _ of Contairrnent R/hr x Ci/R/hr x m /sec/ m = Ci/sec b. Containment Air Sample: i Leak Rate Containment Concentration 3 3 {' .m /sec ,x Ci/m Ci/sec.. = . f. .. T [ 7.' ' '.. : j.. :. '....' 9:.' : m.

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~ T }.i',:,, -1.- FOIM EP 7.2-6 REV. 1-t L i ATTACHMENT 6.0 (Page 2 of 3) lt Contairunent Pressure at ty Containment Pressure at t2 3 Flow Rate (m /sec) = (V ) (V.,) 1 in sac.) at at (sec) = (t2-t1 3 m j,,c, g )- g ) ( ) Periormed By: RfC Revier T % C T 10 \\ \\\\ 20 \\ \\ , 30 v> o oee 40 2- \\ 3 50 \\ 60 \\ 1 70 \\ \\ \\ l \\ 1' 1 \\ s 3 AVAILABLE CONTAINMENT VOLUME (m ) . u- .e 'EP. P. 0. &7. 2......a ..:,~,,..'... .~ .:.....-,;......., o.,, >: .,.pey, 5 - ~ ..t ...s..* ,.,'..r

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f 201E EP 7.2-6 REV. 1 ATTACHMENT 6.0 (Page 3 of 3) (( ( INSTRUCTIONS FOR COMPLETING FORM EP 7.2-6 . 41 S e containment release rate may be estimated based on High Range In-Contairunent Monitor readings and coropletion of this form. 92 23 design basis leag rate of 0.2% free voltane per 24 hours (3.47 ft Anin or 1.64 x 10 cc/sec) may be multiplied by known or estimated contairinent concentrations to quantify this release source if requested by'the RE or DED. (RAM or DEM at the EOF). Use Step 4. 43 If contairrnent integrity is lost perform the following: 44 Obtain from the Operations Status Bhard the high range monitor reading in containment and record.

5 Record the initial contairunent pressure and time (t ).y 96 Record the initial available contairunent volume (V ) fr m the graph.

1 7 Obtain an additional contairrnent pressure value at time (t )

l 2

Record the value. Record the available containment volume (V I f*C" 2 the graph. Flow Rate (m /sec) = (V ) (V I 1 2 At 47a Calculate time difference (At) in secondr,. 3

8 Calculate the ficw rate in m /see and record the flow rate in Step 5.
9 Calculate the number of Ci/R/hr using Steps 2 and 3.

Record in Step 5. 410 Calculate the release rate by performing Step 5. Report data to RT or DED (RAM or DEM at the DOF). As appropriate, use the results of this step as input for manual dose calculations as called out in EPP 01-7.3, Attachment 1.0. -7.2 r.: C': .,

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l {. i KANSAS GAS AND ELECTRIC COMPANY WOLF CREEK GENERATING STATION (( RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURE MANUAL DOSE PROJECTION DETERMINATION EPP 01-7.3 Revision 5 ( Jf 2/f)-f&f If A )$ $0 EMERGENC% PLANNING COORDINAT REVIEC 'DATE /'[ SY 2-/7-26 r EMERGENCY PLANNING ADMINISTRATOR REVIEW DATE 0 J / PSRC APP AL f OMMENDATION DA% / R4$2 Y97l/6 V.P. N EAR APFROVAL DATE RELEASED M 2 f/G DATE i l l

r s' - l. 1.0 PURPOSE C 1.1 This procedure provides guidance for estimating offsite dose rates and integrated doses to the whole body and thyroid in the event of a release.of airborne radioactive material from Wolf Creek Generating Station (WCGS) and the-Radioactive Release Information System (RRIS) becomes inoperable. 2.0 APPLICABILITY . 2.1 This procedure shall be implemented by WCGS emergency response personnel in the following manner: 2'.l.1 Prior to the activation of the Technical Support Center (TSC), the on-duty Shift Supervisor shall be responsible for implementation of this procedure,. 2.1.2 Following the activation of the TSC, but prior to the activation of the Emergency Operations Facility (EOF), the Radiological Emergency Coordinator (REC) or the Dose Assessment Coordinator (DAC) shall assure that the RRIS Operator implements this procedure. 2.1.3 Upon activation of the EOF, the Radiological Assessment Manager (RAM) or the Dose Assessment Supervisor (DAS) shall assure that the RRIS Operator ( implements this procedure. P 3.0 DEFINITIONS 3.1 EXCLUSION AREA BOUNDARY (EAB) That area surrounding the station, in which Kansas Gas and Electric Company (KG&E) has the authority to determine all activities including exclusion or removal of personnel and property from the area. 3.2 EMERGENCY PLANNING ZONE (EPZ) That area surrounding the station in which emergency preparedness planning is conducted for the protection of the public. With respect to protecting the public j from the plume exposure resulting from an incident, the EPZ encompasses an area with a radius of approximately 10 miles surrounding the facility. With respect-to the ingestion exposure pathway, the EPZ encompasses an area with a radius of about 50 miles. y*((,.,...,,. ^ 1 .EPP.01-7. 3 ~

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r" c 3.3 -INTEGRATED DOSE C -That dose of ionizing radiation that has been received during a given period of time by a population'or group. 3.4 PASQUILL-ATMOSPHERIC STABILITY CLASSIFICATIONS The Pasquill atmospheric stability. classifications are a measure of the stability or instability of an air mass based upon the vertical temperature differential between two points. 3.5 PROJECTED DOSE 1 That dose of ionizing radiation that is likely to be received by a population or group if no-protective action measures are implemented, y 3.6 PROJECTED INTEGRATED DOSE The summation of the Integrated Dose (previous) and the Projected Dose (future). 3.7 PROTECTIVE ACTIONS ( Those emergency measures taken to prevent or minimize l ( radiological exposures to affected population groups. 3.8 SOURCE TERM i The calculated quantity of radioactive material avail-l able for release or being released to the i environment. 3.9 X/Q A factor based on meteorological dispersion character-istics which relates atmospheric radionuclide release rates to offs'ite air concentrations. o4. 0 -INSTRUCTIONS 4.1 PRECAUTIONS 4.1.1 The dose projection capabilities of the manual calcu-lation method depend solely upon meteorological data, which become less exact at greater distances from the release point and/or at longer time intervals after the release. 1 l / . '. -aEpp',ol;7.3.. 4 l t ~ ,c , y,,,,, g_ y. n,...( py.. ', ..: y '..'Page;2 of".23

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__l r a i = 4 4.1.2 The projected offsite doses calculated in accordance gr with this procedure may be used in conjunction with {k EPP 01-10.1, " Protective Action Recommendations", as a basis for determining any offsite protective actions to be recommended to State and County officials. 4.1.3

This procedure shall be used in conjunction with EPP 01-7.2, " Manual Determination of Release Rate."

l 4.1.4 The HP-41CV calculator used for manual dose calcula-tion maintains a running total of real time integrated dose (past) and provides projected integrated dose (future). 4.1.5 The HP-41CV automatically adds'the results of each calculation to the value contained in the memory register to accomplish the integral function. If base data for the calculation changes, the memory of the calculator must be manually cleared to assure proper results. 4.1.6 Wind direction is given as the direction from which the wind is blowing. 4.2 INITIAL ACTIONS 4.2.1 l( Obtain the dose assessment material from Control Room, TSC or EOF storage lockers. This material consists of k the following equipment: 4.2.1.1 A base map covering a 10-mile radius out from WCGS-(Plume Exposure Pathway EPZ). 4.2.1.2. A set of six plume overlays, one for each of the six Pasquill atmospheric staoility classes. These over-lays are used to estimate the location of the affected downwind areas as a result of the plume expansion. 4.2.1.3 A programmable calculator, and two sets of the l appropriate dose projection program on magnetic program cards. 4.2.2 Perform offsite dose calculations by using one of the, two methods listed below: a) Programmable calculator, whose specific instructions are listed in Attachment 1.0, " Instructions for Using the Programmable Calculator for Manual Offsite Dose Calculations"; i . EP P.J.01.7.3 c, ., ~ r. s, a. gey..; 5 ,\\ .i I of 2I ^ .O I.ge 3' .Pa . z gt. '. ..=.:...'. . :. l. '. ~. w ;. --3 .1 .a.-._...

,t c b) Manual Calculation Worksheets, Attachments C 2.0 and 3.0. 4.2.3 Upon completion of an offsite dose calculation, I compara the whole body and thyroid dose estimates with' the values specified in EPP 01-10.1, " Protective Action Recommendations." 4.2.4-Assure that the Duty Emergency Director (DED) or Duty l_ Emergency Manager (DEM) is informed of the dose rate and projected integrated whole-body and thyroid doses. 4.3 SUBSEQUENT ACTIONS 4.3.1 offsite dose projection calculations should be performed at least once per hour during the first eight hours after the accident unless it is determined that releases of airborne radioactivity from the plant have been terminated. 4.3.2 offsite dose projection calculations should be updated if any of the.following conditions occur: 4.3.2.1 Release rates increase ~by more than 25 percent, o 4.3.2.2 Wind direction changes by more than 22.5

4. 3. 2. 3 -

Atmospheric stability classification changes, 4.3.2.4 Wind speed changes by more than 50 percent; or i 4.3.2.5 Prior to any planned releases. 4.3.2.6 If a major error is discovered in input parameters, i.e. release rates, the programmable calculator's real l time integrated exposure may be set to zero by using the SET /CLR routine. 4.3.3 All personnel' performing the offsite dose calculations at the TSC should keep the REC informed as to the j status of all offsite dose projection calculation results.. As appropriate, the REC shall advise the'DED regarding the status of offsite dose calculations and provide recommendations if dose' projections warrant implementation of protective actions. i ,. 1 :, ~'?.

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e-4.3.4 All personnel performing offsite dose calculations at C the EOF should keep the RAM informed as to the status of all offsite dose projection calculation results. The RAM shall advise the Duty Emergency Manager (DEM) regarding the status of offsite dose calculations and provide. recommendations if dose projections warrant implementation of protective actions. 4.3.5.0, " Thyroid Dose Equivalent Worksheet," Form EP 7.3-6, is used to project adult thyroid dose equivalent for individuals making reentries into known or suspected iodine airborne areas. l

5.0 REFERENCES

5.1 WCGS Radiological Emergency Response Plan 5.2 EPP 01-3.2, " Followup Notifications" 5.3 EPP 01-7.1, " Radiological Release Information System" 5.4 EPP 01-7.2, " Manual-Determination of Release Rate" l 5.5 EPP 01-10.1, " Protective Action Recommendations" 5.6 USNRC Regulatory Guide 1.109, " Calculation of Annual ( Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance _ with 10CFR50, Appendix I", (Rev. 1, October 1977) 5.7 USNRC Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine ~ Releases from Light Water Cooled Reactors", (Rev. 1, July 1977) 5.8 USNRC Regulatory Guide 1.145, " Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants", (August 1979) 5.9 USNRC Regulatory Guide 1.23, " Meteorological Programs in Support of Nuclear Power Plants", (September 1980) 5.10 USNRC Regulatory Guide 1.4, " Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors", (Rev. 2, June 1974) %r .[.:n...'. + 5'3 ; :. '= a ';;. T 'l b.: ;. '.'?. 'Page 5 4.of'23. . '. ' s s. L,0. :

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6.0 RECORDS 6.1 Form EP 7.3-2, " Manual Calculation Worksheet" 6.2 Form EP 7.3-6, " Thyroid Dose Equivalent Worksheet" l-6.3 Form EP 7.3 7, " Integrated Dose By Sectors" 6.4 The records generated by this procedure during an actual emergency shall be forwarded to the Emergency Planning Coordinator (EPC) at the termination of the emergency. The EPC forwards the records to the WCGS vault for storage. These records will be retained for the life of the plant. These records shall be con-sidered QA records. 6.5 The records generated by this procedure during drills and exercise shall be forwarded to the EPC upon termination of the drill or exercise. The EPC shall maintain these records for at least one year. These records shall be considered non-QA records. 7.0 ATTACHMENTS 7.1.0, " Instructions for using the pro-grammable calculator for Manual Dose Calculations" 7.2.0~, " Manual Calculation Worksheet" 7.3.0, " Instructions for Using Manual Calculation Worksheet" 7.4.0, " Atmospheric Stability Classifications" 7.5 Attachment S.0, "Z Table" s 7.6.0, " Thyroid Dose Equivalent Worksheet" l 7.7.0, " Integrated' Dose By Sectors" 7.8.0, " Test Case Data for HP-41CV E-Plan Program" 9.,..~- /. .l..... .s .;~ , EPP. 01.-7 J 3., f,3 ~.Rev. S

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o J. ATTACHMENT 1.0 (Page 1 of 7) INSTRUCTIONS FOR USING THE PROGRAMMABLE CALCULATOR FOR MANUAL DOSE CALCULATIONS A. To set up and program calculator: 1. Plug in the calculator and printer. Turn the calculator and printer ON. Turn the printer to NORM position. NOTE: Calculator must be in user mode 2. Press l l, E NOTE: l l is the yellow key. The calculator should display "CLR REGISTERS?" If the calculator does not display "CLR REGISTERS?" proceed to Step 3. If calculator displays "CLR REGISTERS?", proceed to Step 15. l 3. Turn the calculator OFF. 4. Pres s "ON" while depr essing l -+-- l. Calculator should display " MEMORY LOST". 5. Press XEQ, ALPHA, S, I, Z, E,

ALPHA, 0,

4, 8. 6. Load the program "X/Q" into the calculator by entering the magnetic cards provided through the card reader in the proper sequence. NOTE: There are nine magnetic cards to be loaded, both sides must be run through the calculator for a total of 17 evolutions (except the last card). NOTE: l l is the symbol for the yellow key. t 7. Press l l, ASN, ALPHA, X, l l, *- Q, ALPHA,l l, A. 8. Press l l, ASN, ALPHA, R, M, S, ALPHA,l l, B. 9. Press l l, ASN, ALPHA, F, I, E, L, D, ALPHA,I l, C. 10. Press l 1, ASN, ALPHA, I, N, T, D, O, d, E, ALPHA,l 1, D 11. Press l l, ASN, ALPHA, S, E, T, l _], - C, L, ~ R, ALPHA, l l, E 12. PressI l, ASN, ALPHA, S, T, E, A, M, ALPHA,1 1. F 13. Press USER l 14. PressI l, E 15. Press Y, l R/S l 16. Pr.ess bR/S l,.after entering each response. + .' 'E'PP OlN '.s. .,,..., ',.,',,. ggf.. g.

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s 0 ATTACHMENT 1.0 (Page 2 of 7) B. To perform calculations, the operator should read the prompts displayed in the printer and feed in the information (INPUT) as requested 1. Any subroutine on the program flow chart may be accessed by pushing l l and then the corresponding letter. IMPORTANT: If desiring to access a subroutine and " ALPHA" is in the calculator display, it is necessary to press ALPHA (to remove it from the display) before accessing a subroutine. 2. Under no circumstances is the l PRGM l Key to be pushed. Also never unplug power sources with the calculator or printer ON. 3. If desired, the program can be verified to be operating correctly by using the inputs and verifiying the outputs as shown on Attachment 8.0, " Test Case Data for HP-41CV E-Plan Program." Any or all three input options can be checked at any time. It would be easiest to perform these checks before dose calculations are made.' These checks can also be made any time the accuracy of the dose calculations is questioned. 4. After entering responses to prompts displayed by the ( calculator, hit lR/Sl. 5. Answers requiring a YES or NO response are answered by Y or N respectively. 6. If X/Q is not executed for calculation updates then the program assumes meterological conditions are unchanged since the last time X/Q was executed. 7. For executing RMS if the iodine monitor (uCi/cc) is inoperable or offscale determine the iodine concentration by multiplying the noble gas concentration (uCi/cc) by the appropriate default value in EPP 01-7.2, Attachment 3.0. l 8. If performing calculations based on FIELD data to compare with dose projections based on source term data, the prompt UPDTE INT HRS =? should be responded to with a zero. The reason is that the integrated dose for the time interval being considered should not be added into the integrated dose already calculated. l E,PP 01-7.3 %*I ,5*{: \\':* ^H' . :j *

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s ATTACHMENT 1.0 (Page 3 of 7) 9. To maintain integrated doses following a wind shift, use the following rules: a. If the vind shi f t is greater than 22.5 degreesi the integrated centerline dose at the new direction is set to Zero. b. If the wind shift is less than 22.5 degrees, the integrated dose at the new centerline direction is assumed equal to the values at the previous direction. C c i EPP 01-7.3. .'>.,7... 2, p, g.. S'.,f. g .. *Rev.. q,.. ~... , ~ - r. . ~.

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ATTACHMENT 1.0 (Page 4 of 7) KEY TO PROMPTS FROM PROGRAMMABLE CALCULATOR PROMPT INPUT WIND SPD = ? Wind speed in MPH STAB CLASS = ? Enter A thru F (Ref. EPP 01-7.3, Attachment 4.0) STEAM RELEASE Press l l, F to access this program. NO. RLFS OPEN = ? Enter the number of relief valves open. PRESSURE = ? Enter the pressure (PSIG) of the steam generator associated with the release. PORV OPEN? Enter "Y" if the PORV is open or "N" if it is closed. MREM /HR = ? Enter the mR/hr reading on the steamline plume monitor associated with the release. (Ref. EPP 01-7.2, Attachment 4.0) RMS DATA? Enter "Y" if flow rate and concentration data is available. Enter "N" if not available. FLOW CFM = -? Enter the flow rate in CFM through the release. point. (Ref EPP 01-7.2, Attachment 1.0) NOB GAS UCI/CC7 Enter the noble gas concentration in uCi/cc at the release point. (Ref. EPP 01-7.2, Attachment 1.0) IOD UCI/CC = ? Enter the iodine concentration in uCi/cc at the release point. (Ref. EPP 01-7.2, Attachment.l.0) FIELD DATA? Enter "Y" if dose rates and/or iodine concentrations are available at a specific distance. Enter "N" if not available. DIST MI. =? Enter the distance in miles from the plant to the point from which the field data is available. MREM /HR = ? Enter the dose rate in mrem /hr the field team is reporting. These values must be centerline dose rates. (Ref. EPP 01-7.2, Attachment 5.0) EPP.01-7.3. .t

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e ATTACHMENT 1.0 (Page' 5 of 7) O PROMPT INPUT IOD UCI/CC = ? Enter the iodine concentration (uci/cc) which the field team is reporting. This concentration must be a centerline valu'e. (Ref. EPP 01-7.2,.0) NOB GAS CI/S = ? Enter the noble gas release rate in Ci/sec as determined in EPP 01-7.2, Attachments 1.0, 3.0, 4.0, 5.0 or 6.0 IOD CI/SEC = ? -Enter the iodine release rate in Ci/sec as determined in EPP 01-7.2, Attachments 1.0, 3.0, 4.0, 5.0 or 6.0 UPDTE INT HRS?' Enter the duration (HRS) of the release since the last update calculation of the integrated dose. PROJ REL DUR? Enter the projected duration (HRS) of the release now in progress. If executing SET /CLR, the following prompts will appear: CLR REGISTERS ? Enter "Y" if you wish to clear all registers. "N" ( if not. ~ {. .,(,. ./.' EPP 01-7.3- -l,

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.c ATTACHMENT 1.0 (Page 6 of 7) PROGRAPHABLE CAIEULA'IOR PROGRAM FLOW CHART E A Set / Clear m Clear Recister ~ X/O Calculation B 9P C No Other, FSAR, No m m ~ Field Data Predictive ^ RMS Data Yes Yes y )( 1f F m Calculate Steam Release Dose Rates at EAB, 2, 5, 10 mi. If Duration of Update Interval ( D V Prints Integrated Dose Up '1hrough Interval of Interest 4 1r Projected Duration of Release Print Projected Intecrated Dose EPP 01-7.3 Rev. 5 .Page'.12.of. 23 ~ .r..... 1 v 7 ,e .s

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ATTACHMENT 1.0 (Page 7 of 7) FLOW CHART EOR PROMPTS I(f-WIND SPEED = ? STAB CLASS = ? 4 E m No NOB GAS CI/SE = ? No RMS DATA FIELD DATA ? ~ IOD CI/SEC = ? ^ Yes Yes y -y FIDW CEM = ? DIST MI = ? NOB GMi UCI/CC = ? MREN/HR = ? IOD UCI/CC = ? IOD UCI/CC = ? F I k U U y NO. RLFS OPEN = ? PRESSURE = ? UPDTE INT HRS = ? PORV OPEN ? MREM /HR = ? Y PROJ REL DDR = ? 1 EPP 01-7.3 Rev. 5 ' Page.13; of 23.; - j .g ~ f.. ..'..s.

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ATTACHMENT 3.0 (Page 1 Cf 3) INSTRUCTIONS MR USING MANUAL CALCULATION NORKSHErr INERMATION REQUIRED MR CAffGLATIONS A. Wind Stability Classification is obtained from the radiological status board or use Attachment 4.0 to calculate if unavailable. B. Wind Speed is obtained from the status board or Control Room. Enter the value in Column 3. Circle the proper units, i.e. nph (miles per hour) or kph (kilometers per hour). C. Radiological Release Rate for Noble Gas ( ) is obtained from the Radiological Status Board or may be determined by EPP 01 .2, " Manual Release Rate Determination". Radiological Release Rate for Iodine (RR is obtained from the radiological D. status board or may be determined by EPP b -)7.2, " Manual Release Rate Determination". E. Date/fime calculation ir,itiated. F. Name of person performing calculation. G. Name of person reviewing calculation. INSTRUCTIONS MR Mf0LE BODY DOSE RATE CALCULATIONS A. Obtain the Z nu:nber, refer to Attachment 5.0. Use the table on Attachment 5.0 for windspeed entered in Column 3. Circle which table the Z value is frcun. B. Take the wind speed nu:nber (Column 3) and divide it into the Z number in Column 2 and record in Column 4. This is the X/Q number. C. Record the Radiological Release Rate for Noble Gas (RRNG) btained in Step I. C. above and record in Column 5. EPP 01-7.3 1 Rev. 5 Page'.15 of;23. .,.s- .p:, . t. e' s t, % l:. ..ji.o .Q

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A'I"rAGMENT 3.0 (Page 2 cf 3) INSTRUCTIONS ER USING MANUAL CAIEULATION WORKSHEEP l D. Record the Radiological Release Rate for Iodine (RRIOD) obtained in Step I. D. above and record in Coltxan 7. E. Multiply.the RRm (5) by the Dose Conversion Factor for Noble Gas (CFg) in Column 6 and adtrthe product to the product of RRIOD (7) multiplied by the Dose Conversion Factor for Iodine in Coltran 8. NOTE: Numbers in ( ) refer to columns on worksheet. F. Multiply the sum frcxn the above step by the X/Q (4) and record in Column 9. This is the Dose Rate for the Whole Body (DRg). G.. Multiply DRgg (9) by four to determine the projected four hour Whole Body dose and record in Column 10. H. Multiply the four hour projected dose.(10) by six to obtain the projected 24 hour Whole Body dose and record in Column 11. I. Perform the above calculations for each distance listed in Column 1. J. Results should be given to the Dose Assessment Supervisor for review prior to being given to the Radiological Dnergency Coordinator or Radiological Emergency Manager and posting of status board. INSTRUCTIONS MR CHILD 'IEYROID DOSE RATE CAICULATIONS A. Record the Radiological Release Rate for Iodine (RRIOD) obtained in Step I. D. above and record in Column 12. B. Record the X/Q values obtained in Step II. B. in Column 14. Multiply RR (12) by the Dose Conversion Factor for Child Thyroid (CF under C. Column 13 aEby the X/0 (14) and record in the Child Thyroid Dose Rateb)lumn (DRg) under Coltran 15. To obtain the four hour Projected Child Thyroid Dose, multiply DR,rHY (15) by four D. and record in Column 16 (4 hr Int. Dose). EPP 01-7.3 .Rev. 5

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ATTACHMENT 3.0 (Page 3 of 3) INSTRUCTIONS EDR USIM MANUAL CALCULATION WORKSHEET E. To obtain the 24 hour Projected Child Tr yroid Dose, multiply the number in Column 16 (4 hr Int. Dose) by six and record in Column 17. F. Results should be given to the Dose Assessment Coordinator (DAC) or the Dose Assessment Supervisor (DAS) for review prior to being given to the Radiological Dnergency Coordinator (REC) or Radiological Assessnent Manager (RAM) and posting of status board. IV. INduUCTIONS EDR DOSE RATE CAICULATIONS BASED ON FIELD TEAM DATA NOTE: Whole Body, Thyroid Dose and Dose Rate calculations are based using a direct relationship between dose and X/Q values. Therefore, once reliable field data i has been obtained for one known X/Q location all others may be calculated by the calculation worksheet. l A. Obtain the Dose Rate (DR ) from the Radiological Field Team (s) for a known X/Q 3 l point and record in ColuBn 18 ~ (DR ). g B. Record the X/Q value for the survey point in Step IV. A. above in Column 20 (X/Q ). g C C. Record the X/Q value for the new location for which dose rate is to be determined in Column 19 (X/Q I

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Multiply the D g (18) by (19) and divide the product by X/Qg (20). Record the quotient in Column 21 ( ). E. DRB (21) is the dose rate at the new point. F. Repeat Steps A through E for each new point where dose rates are required. EPP 01-7.3 f . Rev. S... .? ,.i.Pa9.0 17 OE 23 s .c ~ a;.,;.r.y.~ ;.~:., ,';.-. j.g. t. . 9 ',. v. j f.c . a.o ; ^.,s..c j '..

, (_ ~ [ ATTACHMENT 4.0 4 (Page 1 of 2) l A'INOSPHERIC STABILITY CLASSIFICATIONS 1.0 For teuperature differential in C. The tenperature differential is obtained from the base of the met tower. NOTE: 'Ihe 60-10m Delta T is the preferred height for determining stability class if it is available. DELfA T DELfA T DELfA T STABILITY ( C) ( C) ( C) CLASS (85-10m) (60-10m) (35-10m) A <-1.42 <-0.95 <-0.47 B -1.42 to -1.27 -0.95 to -0.85 -0.47 to -0.42 C -1.27 to -1.12 -0.85 to -0.75 -0.42 to -0.37 D -1.12 to -0.37 -0.75 to -0.25 -0.37 to -0.12 E -0.37 to 1.12 -0.25 to 0.75 -0.12 to 0.37 F 1.12 to 3.00 .75 to 2.00 0.37 to 1.00 G > 3.00 > 2.00 > 1.00 Example: 1. If the T is available for the 85-10 differential and the T is -1.5, the stability class is A. ( 2. If the T is available for the 85-10 differential and the T is -1.32, the stability class is B. 2.0 For te@erature differential in F DELfA T DELfA T DELfA T STABILITY ( F) ( F) ( F) CLASS (85-10m) (60-10m) (35-10m) A <-2.56 -1.71 <-0.85 B -2.56 to -2.29 -1.71 to -1.53 -0.85 to -0.76 C -2.29 to -2.02 -1.53 to -1.35 -0.76 to -0.67 D -2.02 to -0.67 -1.35 to -0.45 -0.67 to -0.22 E -0.67 to 2.02 -0.45 to 1.35 -0.22 to 0.67 F 2.02 to 5.40 1.35 to 3.60 0.67 to 1.80 G > 5.40 > 3.60 > 1.80 3.0 If delta T sensors are inoperative for the time frame or the accident sequence l doesn't alloa for proceeding to the met toaer, use an ananometer frcm the emergency kits and the table on the following page to determine the stability class. l 4.0 Additional weather information may be obtained from the National Weather Service in Topeka at (913) 295-2631. 'EPP 01-7.3 . v.... .? y w. .- ~ ~. 3.,.~.

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ATTACHMENT 4.0 (Page 2 of 2) STABILITY CLASS BY OBSERVATION i SURFACE WIND l DAY l NIGHT Light Clear Overcast Broken Clear MPH m/sec Scat. Broken Overcast Clouds Scat. Clouds Clouds Overcast I Clouds <4.5 <2 A A-B B E F 4.5-7.8 2-3.5 A-B B C E F 7.8-10 2-3.5 B B-C C D E 10-13 4.5-6 C C-D D D D >l3 >6 C D D D D ( EPP 01-7.3 Rev. 5 ..~

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ATTACHMENT 5.0 (Page 1 cf 1) Z TABLE F For wind speed in mph use Table A. For wind speed in krg/hr use Table B to determine Z value. Table A (units are sec. nph } M Stab. Class A B C D E F G Dictance EAB (3/4 mile) 1.80E-6 1.16E-5 3.49E-5 1.llE-4 2.09E-4 5.02E-4 1.26E-3 2 mile 6.2E-7 8.73E-7 6.6E-6 2'4E-5 4.80E-5 1.13E-4 2.83E-4 . 5 mile 2.8E-7 3.6E-7 1.44E-6 5.49E-6 1.39E-5 3.58E-5 8.95E-5 10 mile 1.6E-7 2.02E-7 4.69E-7 2.4E-6 5.62E-6 1.59E-5 3.98E-5 Table B (units are sec. km/hr } ( M Stab. Class A B C D E F G Distance EAB (3/4 mile) 2.91E-6 1.87E-5 5.65E-5 1.8E-4 3.39E-4 8.14E-4 2.04E-3 2 mile 1.00E-6 1.41E-6 1.07E-5 3.89E-5 7.78E-5 1.83E-4 4.58E-4 5 mile 4.54E-7 5.83E-7 2.34E-6 8.89E-6 2.25E-5 5.80E-5 1.45E-4 10 mile 2.59E-7 3.27E-7 7.60E-7 3.89E-6 '9.llE-6 2.59E-5 6.98E-5 EPP 01-7.3 .. Rev., 5 ~.,.',..':

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o n EORM EP 7.3-6 REV. 1 ATTAQUENT 6.0 (Page 1 of 1) . IHYROID DOSE EQUIVALENT WORK 91EET IDCATION Actual DATE TIME Planned ~ On Site Off Site Adult Thyroid Dnergency Worker Projection RADIOIODINE DOSE l RADIOIODINE l REM /cc ISOTOPE FAC'IOR X CONCENTRATION = (RDi/uCi) (uCi/cc) inhaled inhaled 131 1.5E+0 132 1.4E-2 133 2.7E-1 134 3.7E-3 135 5.6E-2 SUM 9.13E+5 = BREAE ING EXPOSURE B YROID RATE X DURATION X TOTAL DOSE = (cc/hr) l (hours) l (RD4/cc) EQUIVALENT C (RD4) Child Thyroid Off Site Projection RADI0 IODINE DOSE RADIOIODINE l ISCyrOPE FACTOR CONCENTRATION RD4/cc = (REN/uCi) (uCi/cc) inhaled inhaled 131 4.4E+0 132 5.ZE-2 133 1.0E+0 134 1.4E-2 135 2.lE-1 SUM 4.22E+5 = BREAEING EXPOSURE E YROID RATE X DURATION X TCyrAL DOSE = (cc/hr) l (hours) l (RD4/cc) EQUIVALENT (REM) Remarks-r f.,,,,.,'i.... ' C -cr-: ' '.s.:. S i" ;, ;...',' ? ? 4 ".;.,,.,. '/,,d. EP 01-7.3'tf. *l. s.'" [ f " ' ~ ' DOSE' ASSESSMENT. COORDINATOR.- - ,, SI.GNA'IURE,.{.,. > :,,,.]., - l'..Page. 21'. df..23..,;.. ',3.,..,.' 'IteY. 5' 7- !.' y ',1 $, V. ',[* 1 - - ~ _ -_d a -- -.n,.:4

p q-3-7 REV. 0 i -.e t,..: ATTADHWT 7.0 INIHRAIED IJOSE BY SECIURS Page 1 of 1 Whole Body /lhyroid Integrated Dme (ohn) By Sectors North Est South West Tine Distance A B C D E F G H J K L M N P Q R Updated By 3/4 mile (EAB) . s; c. 2 5 10 3/4 mile (EAB) .c - 2 . ~. 5 l- : 10 3/4 mile (EAB) 2 d.'. 5 10 3/4 mile (EAB) 2 5 < j. 10 3/4 mile (EAB) i ./. y 2

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1 o ATTAO NENT 8.0 \\ (Page 1 'of 1) TEST CASE DATA EDR IIP-4]Cd E-PLAN PROGRAM Met Data j ~i 6.211 miles /hr Stability Class E Input Data RMS Option Release Rate Option Noble Gas uCi/cc = 5.915 Noble Gas 27.92 Ci/sec Iodine uCy/ min =10,000 ec = 5.169E-1 Iodine 2.44 Ci/see E Flowrate ft Field Team Option 10.01 miles 6 mRatVhr WB 2.205E-6 uCi/cc I-131 Output Data Noble Gas Ci/sec = 27.92 Iodine Ci/sec 2.44 = X/Q @ EAB = 3.37E-5 Whole Body Dose Rates EAB = 0.224 Ran/hr 2mi = 0.051 RetVhr Smi = 0.015 Ran/hr 10mi= 0.006 RatVhr Thyroid Dose Rate EAB = 152.119 RetVhr Inhaled I( 2mi = 34.881 RatVhr ~ Inhaled 5mi = 10.077 Resn/hr Inhaled 10mi= 4.086 Ran/hr Inhaled 1/2 Hour Interval Update Whole Body Dose EAB = 0.112 Ran 2mi = 0.026 Rem Smi = 0.007 Ran 10mi= 0.003 Ran Thyroid Dose EAB = 76.062 Ran 2mi = 17.441 Ran Smi = 5.038 Ran lQui= 2.043 Ran Plus, 7.5 Hour Projection Whole Body Dose EAB = 1.792 Ran (Effective 8 hour 2mi = 0.411 Ran Exposure) Smi = 0.119 Ran 10mi= 0.048 Ren Thyroid Dose EAB = 1216.990 Ran 2mi = 279.055 Ran Smi = 80.616 Ran .10ni.=. 32.686 Ran 3c f: ,,.. < I*" R'otindisg., errors.are[tb.,,,. ,.,.be'ignoredi' "?. '*' " ' ~ ' ' " ' ', ' l.' '. Og ; : ',,. -[.' ~ !;- .f. s, /; '~ 'EPP'01-713 ', ~ . Sey.* 'S,c:.., y; '3 a.l.,s, _ :.: ',:. :,:.;. , :,, 4 s : <..'..:' <., **, " (,. .....,.... *'r. , ay..y... ;,,.:, r.: Page'23 of'23 " ~ 4 - -~- .. _ _.. _. _ 4

i' {(( KANSAS GAS AND ELECTRIC COMPANY WOLF CREEK GENERATING STATION RADIOLI'.'ICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURE ONSITE RADIOLOGICAL MONITORING EPP 01-8.1 Revision 4 I v>As11/ EMERGENCY F ING'CO . OA 2 If % ~ INXTOR REVIEW DATE/ / Y 0 cm .7 - /[-@ G EMERGENCY PLANNING ADMINISTRATOR REVIEW DATE h PSRC APPRO RE .MENDATION DA[E /' ~ $d WF7/h V.P. MCC* star APPROVAL DATE RELEASED M _ m. -M-8 (o DATE ,. ; s.,,, .s.. 1

T 1" e 1.0 PURPOSE This procedure provides guidelines for onsite monitoring of radiological conditions in the event of a radiological emergency at Wolf Creek Generating Station (WCGS). 2.0 APPLICABILITY This procedure is applicable to the Duty Emergency Director (DED), Radiological Emergency Coordinator (REC), Radiological Assessment Coordinator (RAC), Dose Assessment Coordinator (DAC), Technical Support Center (TSC) Field Team Communicator, Onsite Survey Team Director (OSTD), Operations Support Center (OSC) Supervisor and other personnel assigned to support the activities of the Onsite Survey Teams. 3.0 DEFINITIONS 3.1 Emergency Response Facility - Those facilities including the Control Room, the TSC, and the OSC, from which instructions to Onsite Survey Teams may originate. 3.2 Onsite - Onsite is that area within the Owner Controlled Area fence for purposes of this procedure. 4.0 INSTRUCTIONS 4.1 PRECAUTIONS 4.1.1 Each Onsite Survey Team shall be composed of at least two (2) individuals, of which at least one (1) individual shall be a Health Physics Technician. NOTE: The REC may dispatch an individual to the control Room to monitor habitability and/or to a location outside the Power Block to perform surveys. 4.1.2 No onsite radiological survey activity shall be performed if that activity wo'11d result in personnel exposure in excess of 10CFR, Part 20 limits unless authorized by the Duty Emergency Manager (DEM) or the DED in his absence. l 4.1.3 Individurls performing onsite radiological survey activities shall exercise As Low As Reasonably Achievable (ALARA) concepts. -{ C.. ';,. :<- \\. '. >

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f e Each Onsite Survey Team should keep at least one dose C 4.1.4 rate monitoring instrument on at all times to minimize the chance of unexpected exposure. 4.1.5 Onsite Survey Teams should not enter or remain in areas where general area dose rates are in excess of 5 R/hr without approval from the RAC or DAC. 4.1.6 Onsite Survey Team personnel shall use protective clothing and respirators, as appropriate, to minimize internal exposure and skin contamination. 4.1.7 The RAC or DAC should consider the use of Potassium l Iodide (KI) tablets, in accordance with EPP 01-9.3, "Radioprotective Drugs", in the event that high levels of radioiodine are suspected. 4.1.8 Onsite Survey Team personnel shall assure that all radio and telephone data transmissions are carefully worded and clearly understood by the communicator receiving that information. 4.1.9 Onsite Survey Teams shall, in case of loss of communi-cations, contact the Onsite Field Team Communicator, l RAC or DAC via the intraplant page or telephone system: Onsite Field Team Communicator - Ext. 359 DAC - 353 RAC - 389 4.2 INITIAL ACTIONS 4.2.1 The RAC and/or DAC shall request the formation of Onsite Survey Teams through the Maintenance Emergency Coordinator (MEC). 4.2.2 The RAC and/or DAC shall inform the MEC of current plant conditions, recommended routes and monitoring objectives. 4.2.3 .The RAC shall assign a communicator for the Onsite Survey Teams which enter the power block buildings. 4.2.4 The DAC shall inform the TSC Field Team Communicator of the formation of Onsite Survey Teams which will perform their survey activities outside the power block buildings. 4.2.5 The MEC shall notifiy the OSC Supervisor of the need fdr Onsite Survey Teams as requested by the RAC/DAC. ..~ D .l,EPP.0.ly8.1

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t' . c 4 C e,<.2.6 The OSC Supervisor shall direct the OSTD to form the appropriate Onsite Survey Teams and prepare for their dispatch. 4.2.7 The OSTD shall perform the following: i 4.2.7.1 Assign individuals to form an Onsite Survey Team. Each team requires a minimum of two (2) individuals one of which must be a Health Physics Technician. 4.2.7.2 Assign an individual as the Onsite Survey Team Leader. 4.2.7.3 Brief the Onsite Survey Team on the current and projected emergency conditions and the monitoring objectives. This briefing should include the following: Magnitude and composition of any actual or a. potential radiological releases; e.g. the source of leakage, release rate, and expected duration. l b. Projected onsite dose rates, airborne activities I and contamination levels. Current and projected meteorological conditions. c. ( Survey results from any preliminary radiological d.

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e. Review requirements for protective clothing, respiratory protection, dosimetry types and placements, and survey equipment. f. Initial dastination 4.2.7.4 Issue the Onsite survey Team communication identificaticn. 4.2.7.5 Assign the Onsite Survey Team a vehicle appropriate to their monitoring objectives. 4.2.7.6 Obtain the Attachment 1.0, "Onsite Survey Team Checklist", Form EP 8.1-1, from the Onsite Survey Team after they have completed their part and complete and sign the checklist, thereby authorizing their departure. 4.2.7.7 Dispatch the Onsite Survey Team through either the TSC Field Team Communicator or the RAC - assigned Communicator. ? . _ : 4,,,.,' i. ' ' ..- ] 9 's:..,. - .. c *.

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e 4.2.8 The Onsite Survey Teams shall perform the following: I(( 4.2.8.1 Obtain necessary monitoring and survey equipment from emergency lockers. 4.2.8.2 Perform all required operability checks on equipment. 4.2.8.3. Obtain the appropriate keys necessary to access areas of the plant to complete monitoring objectives. 4.2.8.4 Dress out in appropriate protective clothing and obtain necessary respiratory protective equipment, as directed. 4.2.8.5 Obtain the necessary dosimetry.- As a minimum, Onsite s Survey Team personnel shall wear a thermoluminescent dosimeter (TLD) and a low range and high range self-reading dosimeter. 4.2.8.6 Record the serial numbers and initial readings of the dosimetry devices for each Onsite Survey Team member on Form EP 9.1-4, " Emergency Dosimeter Log", located in the Emergency Locker. 4.2.8.7 Complete applicable parts of Attachment 1.0, "Onsite Survey Team Checklist", Form EP 8.1-1, and submit it l to the OSTD for approval for dispatch. 4.2.8.8 Attend a briefing regarding the emergency conditions and monitoring objectives by the OSTD. 4.2.8.9 Establish and maintain radio communications with the TSC Field Team Communicator and/or the RAC - assigned Communicator. 4.2.9 The TSC Field Team Communicator shall verify communication identification and team membership when the Onsite Survey Team establishes radio communications. 4.2.10 The RAC - assigned Communicator shall verify communi-cation identification and team membership when the in-plant Onsite Survey Team establishes radio communications. 4.3 Subsequent Actions 4.3.1 The RAC/DAC shall perform the following:

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r 4.3.1.1 Direct their respective Onsite Survey Teams to desired f" sampling or monitoring locations. If applicable, I refer to Attachment 2.0, "Onsite Radiological Monitoring Locations". 4.3.1.2 Direct their respective Onsite Survey Teams as to types of monitoring and/or sampling to be performed. 4.3.1.3 Review and approve incoming field data, Attachment 3.0, " Radiological Monitoring Data Sheet," Form EP 8.1-3, for survey results. l 4.3.1.4 Direct the updating of Radiological Status Board through the TSC Radiological Status Board Recorder. 4.3.2 The MEC shall coordinate with the RAC/DAC to monitor the activities of all Onsite Survey Teams. 4.3.3 The OSTD shall perform the following: 4.3.3.1 Assure the logging in and analysis of all incoming field samples at the OSC Bio-Assay Laboratory. 4.3.3.2 Review and assure dosimetry entries of incoming field teams. 4.3.4 The Onsite Survey Team shall perform the following: 4.3.4.1 Proceed to monitoring locations as directed. 4.3.4.2 Observe dose rate monitoring instrumentation while enroute to monitoring locations. 4.3.4.3 Communi.cate the arrival of the Onsite Survey Team at the designated sampling location to the TSC Field Team Communicator or RAC - assigned Communicator. 4.3.4.4 Perform, as directed, data collection, sampling and record keeping as follows: 4.3.4.4.1 Record all sampling locations, times, measurements and sample data on Attachment 3.0, " Radiological Monitoring Data Sheet", Form EP 8.1-3, or plant survey maps, as appropriate. 4.3.4.4.2 Place all air samples in separate bags and label with the following information, as applicable: . T.s : '.T y ..9 4;* ' ' ' '.. -'y,'.l . W..c 4* ~- ~ .a.. . - ~ - . s.

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- date and time C - location - individual / field team - type and description - air monitor sample times (start & stop) - air monitor sample flows (start & stop) - radiation reading at contact 4.3.4.4.3 Dose Rate Measurement Procedure (ion chamber): Measure the dose rate with the Beta shield open a. for a Beta / Gamma reading. b. Measure the dose rate with the Beta shield closed for a Gamma reading. _ Quantify the Beta dose by subtracting the Gamma c. reading from the Beta / Gamma reading and multiplying by the beta correction factor on the instrument. 4.3.4.4.4 Air Sample Collection: Assemble a particulate filter (coarse side out) a. and a silver zeolite cartridge (flow arrow pointed at sampler) in the sampling head and install the ( head on the sampler. b. Place the sampler so that a representative sample may be collected. Plug the sampler into.the vehicle inverter (vehicle must be running) or electrical outlet and start the sampler noting the actual flow rate and starting time. Allow the sampler to run for the requested time c. (normally at least 10 mins.). Note the final flow rate, stop the sampler and record stop time. d. Remove the particulate filter and silver zeolite cartridge from the sampler head and determine their gross activities if requested. 4.3.4.5 Communicate to the TSC Field Team Communicator /RAC - assigned Communicator that requested sampling is completed and request further instructions. NOTE: Onsite Survey Teams should move to a low ~ background area, as applicable, during periods when radiological monitoring activites are not being conducted or when data is recorded. . r....,. ~ : - , ' T *~. ','.., ~~i f _ *: _,.5l'_~',. ','_., ; -. _ c., - f : -..*:::.h* .Q :.J

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~% t i. + L 4.3.4.6 Upon completion of all onsite radiological monitoring activities the following shall be performed: 4.3.4.6.1 Submit all samples collected and corresponding data sheets to the OSC Bio-Assay Laboratory for further analysis and retention. NOTE: Samples that have significant activity should be placed in'a shielded area to reduce personnel exposures and radiation fields in the Bio-Assay Laboratory. 4.3.4.6.2 1ssure completion of a " Radiological Sample Inventory Log", Form EP ll.3-2 for onsite samples. Completed l inventory logs should be routed to the Onsite Survey Team Director. 4.3.5 The TSC Field Team Communicator /RAC - assigned Communicator shall perform the following: 4.3.5.1 Communicate all directions from the RAC/DAC to the proper Onsite Survey Team. 4.3.5.2 Track locations and status of all Onsite Survey Teams. 4.3.5.3 Record communicated data from the Onsite Survey Teams ( on Attachment 3.0, " Radiological Mo'nitoring Data l Sheet", Form EP 8.1-3, or plant survey maps, as appropriate, and submit it to the RAC/DAC for approval. 4.3.6 Recording, Transmitting and Receiving Data 4.3.6.1 To assure that a permanent record of all onsite survey activities is maintained, copies of Form EP 8.1-3, " Radiological Monitoring Data Sheets," are provided in the OSC Emergency Kits or cabinets. 4.3.6.2 Upon completing the instructed survey and sample collection activities, Onsite Survey Team personnel shall record the data and transmit to the TSC Field Team Communicator or RAC - assigned Communicator. 4.3.6.3 Field data received by the communicator shall be recorded on appropriate survey maps or on Form EP 8.1-3 " Radiological Monitoring Data Sheet", as appropriate. 4.3.6.4 Upon receiving and recording field data reported by the teams, the completed data sheets shall be used for subsequent evaluation and posting.

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REFERENCES 5.1 Wolf Creek Generating Station Radiological Emergency Response Plan 5.2 '~ ' EPP 01-9.1, " Exposure Control and Personnel Protection" 5.3 EPP 01-9.3, "Radioprotective Drugs" l 5.4 EPP 01-11.3, " Logs and Record Keeping" 6.0 RECORDS 6.1 Form EP 8.1-1, "Onsite Survey Team Checklist" l 6.2 Form EP 8.1-3, " Radiological Monitoring Data Sheet" ] 6.3 The records generated by this procedure during an actual emergency shall be forwarded to the Emergency i Planning Coordinator (EPC) at the termination of the emergency. The EPC forwards the records to the WCGS ( vault for storage. These records will be retained for i the life of the plant. These records shall be considered QA records. 6.4 The records generated by this procedure during drills and exercise shall be forwarded to the EPC upon termination of the drill or exercise. The EPC shall maintain these records for at least one year. These records shall be considered non-QA records. 7.0 ATTACHMENTS 7.1.0, "Onsite Survey Team Checklist" 7.2.0, "Onsite Radiological Monitoring l Locations" 7.3.0, " Radiological Monitoring Data Sheet" i 1 l .f ..k.'.:.., p.... .... ',.c .i. ..? . i,-( '*;E9P 01-C1f

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1 y FORM EP 8.1-1 R;v. O A ATTACHMENT 1.0 (Page 1 of 1) ONSITE SURVEY TEAM CHECKLIST Team Members Leader Member Member Member Radio Call ID for this team is The Team Leader shall sign his initials when an item is complete or write "N/A" for not applicable. TEAM LEADER INITIALS 1. Instruments checked for proper response 2. Obtained Survey Maps 3. Obtained appropriate keys. OSTD INITIALS 4. Properly dressed with required anti-contamination clothing, respirator equipment and dosimeters-6 5. Briefing completed on:

a. Additional protective clothing, respirator, dosimetry requirements

b. Emergency conditions and monitoring objectives, suggested route and alternate 6.

Team members were issued KI 7. Exposure extension authorized. 8. Established radio contact with TSC and informed applicable Communicator of Team Identification. Onsite Survey Team Director t' z,_ 6's. EPp.01-8:T '.*- ja . Rev. ' 4 6..-

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g i s.. (. e .*I.* '.. *. e - -n. .y e r FORM EP 8.1.) Afv. 0 RADIOLOGICAL MONITORING DATA SHEET N .\\,. Instrument Dose pate Count Rate Air Sampleg Tese Designettes Dete t e Serial Number Callbration Date Dose Rate Beta Correetton Footor .~g'* Effielency Dose Rate Air Sample Data Ccemmente _ pample (Window) Tsee flou Rate Vol. P U culate lodhe U ,s mr/Hr ar/Hr CPM Citt CPM uCL/co CPM CPM CPM uct/co Note any environmental semples } y Time Loef OPE N Cl0 SED ON OFF ON OFF Ft (Wgd Cross NET ACTIVITV f4gd Cross NET ACTIVITT.taken and also. Inforeetton O l#. O H g= O> ti.gy x at > g g ..(* 2; ID .i g d H O Z . '. j. ;. M OH 1 H M 2C 4J s. O He .I. U wO "*= a., ~1

W .e. ~' 0 ,O ABBREVIATIONS ,'8 s PARTICUL ATE ACTIVITY CALCULATION Crose CPM e Cross Counts per Minute -L Bksd CPM e Background Counts M per Minute (Cross CPM) - (Pkgd CPM) e NCPM e Activity in uC1/co Vol. e Volume in Cutie feet

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a(6.04 E a 09)(VOL FT ) Eff. e Efflotency d I uct e Mlerocurtes 3-IODINE ACTIVITY CARCULATION ce e Cubte Centimeter I* @NM (Cross CPM) _ (Pkg f CPM) s NCPM e Activity in uC1/ce Member Signaturest .07 -(D M 3 I .O' LQ 4 T '( 6. 04 E a 07)(ral FT )

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. - (D ' ','. O. 4. NOTE: Turn in Date meet to Emergency operettons Feetlity Environmental Laboratory ^.' H A.,H (Blo-assay I.aboratory at the Operettons Support Center). H* . I ',. ' f..,6 "Tht's constant includes filter erF. and counter err. '.! h H H

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m KANSAS GAS AND ELECTRIC COMPANY WOLF CREEK GENERATING STATION RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURE OFFSITE RADIOLOGICAL MONITORING EPP 01-8.2 Revision 3 I 1 \\ TAMA4 l/ $ [$ EMERGENM PLANN G COORD ATOR REVIEW DATE '/ 0 om a2. -/ 7-f S EMERGENCY PLANNING ADMINISTRATOR REVIEW DATE $ 20 '/ PSRC APPROVAL .ECOM NDATION DAyt [' 4 Yf7$$ V.P.' NOCLE g APPROVAL ~ DATE ' RELEASED Q - M-7(p DATE v_ e ..i, .g + 's .., y,., - ...;;*._,,,,.,:...~_.,, , i. .l. i'; - ~ ....a- ,.~:.- f'E74 g.c.~e :;...;. : 1. '.'. :..,,. 1,;..,,,y... .,f. e,;. 7. :,,::...,, ;...,....y q.,; ' ---.____e.

.~ l.0 PURPOSE This procedure establishes the criteria and instructions for assessing offsite radiological conditions in the event of a radiological emergency at Wolf Creek Generating Station (WCGS). 2.0 APPLICABILITY This procedure applies to the Dose Assessment Coordinator (DAC) in the Technical Support Center (TSC), the Radiological ~ Assessment Supervisor (RAS) in the Emergency Operations Facility (EOF), and other personnel assigned to, or associated with, Offsite Monitoring Teams. This procedure shall be initiated following the declaration of a Site Area Emergency or General Emergency or as directed by the Duty Emergency Director (DED). 3.0 DEFINITIONS 3.1 EMERGENCY RESPONSE FACILITY Those facilities, EOF, TSC, and the Operations Support Center (OSC), where instructions to Offsite Monitoring Teams may originate. ( 3.2 PRE-DETERMINED EMERGENCY SAMPLING LOCATIONS ,i Those offsite monitoring locations, as identified in.0, used for consistency in offsite monitoring as agreed to by KG&E, Coffey County, and the State of Kansas. 3.3 OFFSITE Offsite is that area outside the owner controlled area for purposes of this procedure. 4.0 INSTRUCTIONS 4.1 PRECAUTIONS 4.1.1 Each Offsite Monitoring Team shall be composed of at least two (2) individuals, of which, at least one (1) individual is a Health Physics Technician, trained in offsite monitoring. I 4.1.2 All offsite monitoring activities shall be conducted i so that exposures are maintained as low as reasonably i achievable (ALARA). .,,5 :.. .{i,:* 'l. f,_...;.V'",..' ?.z... _ f, 2 :..', ' <: ;;

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4.1.3 Each Offsite Monitoring Team shall keep a dose rate or count rate monitoring instrument on.at all times to detect unexpected or excessive exposure from the plume while performing radiological monitoring activities. 4.1.4 offsite Monitoring Team personnel shall use protective clothing and respirators as directed by the DAC or RAS, or upon their own determination of need to l minimize skin contamination and internal exposure. 4.1.5 _The Radiological Emergency Coordinator.'(REC) at the TSC (RAM at EOF) should consider the use of Potassium Iodide (KI) tablets, in accordance with EPP 01-9.3, "Radioprotective Drugs," in the event that high levels of radioiodine are suspected. 4.1.6 Offsite Monitoring Team personnel shall not exceed 10CFR, Part 20 exposure limits without approval from the Duty Emergency Director (DED) or later the Duty Emergency Manager (DEM). 4.1.7 offsite Monitoring Team personnel shall assure that all transmissions of data are clear and concise. 4.1.8 offsite Monitoring Teams shall use Operations radios on Channel 4 as the primary method of communication ( while dispatched and public telephone as a back-up. Utilize the following numbers in case'of a loss of communication: Radiological Assessment Supervisor (EOF); PH.# 364-8831 Ext. 391 TSC Field Team Communicator; PH.# 364-8831 Ext. 359 l 4.2 INITIAL ACTIONS 4.2.1 Assignment to Offsite Monitoring Teams will be accomplished by the Onsite Survey Team Director (OSTD) at the OSC before EOF activation. This function will l be accomplished by the RAS at the EOF after its activation. NOTE: A minimum of four monitoring teams composed of any combination of offsite Monitoring Teams and/or Joint Radiological Monitoring Teams shall be organized as soon as practicable whenever a radiological release is imminent or in progress. .:, s. ',,.iE P P <.01-8 2 - {. ' f.* :.

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1 4 Dispatch and direction of Offsite Monitoring Teams C .2.2 will be-initially accomplished at the.OSC and TSC respectively until the EOF is activated. Once the EOF is activated, dispatch and direction of Offsite Monitoring Teams is accomplished at the EOF. 4.2.3 The RAS shall perform the following: NOTE: The OSTD shall perform the following when offsite Monitoring Teams are being dispatched from the OSC. NOTE: The RAS may assign the following functions to the EOF Coordinator. 4.2.3.1 Assign individuals,to form an Offsite Monitoring Team. Each team requires a minimum of two (2) individuals, one of which must be a Health Physics Technician trained in offsite monitoring. 4.2.3.2 Assign an individual as Offsite Monitoring Team Leader. 4.2.3.3 A briefing of the Offsite Monitoring Teams on the current and projected emergency conditions and the monitoring objectives. This briefing should include ( the following: a. Magnitude and composition of any actual or potential radiological releases to the environment, e.g. the source of leakage and the release rate, the composition of the release (noble gas, radioiodine, or part'iculate) and the expected duration of the release. b. Projected offsite dose rates, and/or airborne activity. c. Current and projected meteorological conditions, including the wind speed, wind direction, and any other information concerning those areas or sectors that are or may be affected by the

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Survey results from any preliminary radiological monitoring activities conducted offsite. NOTE: If the State and County monitoring team members join the Offsite Monitoring Team in the field, assure that they also receive the above briefing.

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e. Requirements for protective clothing. l(g-f. Initial destination 4.2.3.4 Issue the Offsite Monitoring Team. communication identification. 4.2.3.5 Assign the Offsite Monitoring Team a vehicle appropriate'to their monitoring objectives. 4.2.3.6 Obtain the Attachment 1. 0, "Offsite Monitoring Team Checklist", Form EP 8.2-1, from the Offsite Monitoring Team after they have completed their part and complete and sign the~ checklist, thereby authorizing their departure. 4.2.3.7 Dispatch the Offsite Monitoring Team through the applicable Field Team Communicator. 4.2.4 The EOF Field Team Communicator shall perform the following: NOTE: The TSC Field Team Communicator shall perform the following when the EOF has not been activated. ( 4.2.4.1 Verify communication identification when the Offsite Monitoring Team establishes initial radio communica-tions or whenever the Teams are turned over to the EOF. 4.2.4.2 Notify the RAS (Dose Assessment' Coordinator at the TSC) when the Offsite Monitoring Teams are ready to depart. 4.2.5 The Offsite Monitoring Team shall perform the following: 4.2.5.1 Select an Emergency Kit located at the Emergency Lockers and perform an inventory check against the inventory list provided in the kit. NOTE: Inventory of the kit's contents is not required if the kit seal is intact. 4.2.5.2 Perform the required operability checks on the equipment contained within the Emergency Kit. NOTE: If inoperable instruments are discovered, backup instrumentation and/or batteries are available i n the Emergency Locker. r. '* i,.s l Q, E P P 01.,8. 2 '.)* M..,' '. ~ 1.- ., p i.,...,- ,... is . s. :- - y,.

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~ ...no.,_,e.. Obtain the keys to-the radiological emergency response C 4.2.5.3 vehicle from security officers at the Personnel Access Control Station (PACS) or the EOF and assur'e it is fueled and properly equipped to suppo'rt the monitoring ~< objectives. 4.2.5.4 Obtain appropriate dosimetry devices from Emergency Kit (s) and respirators from the emergency cabinet. As a minimum, Offsite Monitoring Team personnel shall wear a thermoluminescent dosimeter (TLD), a low range, .and a-high range direct reading pencil dosimeters. NOTE: Two (2) extra respirators should be taken for potential use by JRMT members. 4.2.5.4.1 Record the serial numbers and initial readings of the dosimetry devices for each Offsite Monitoring Team member on Form EP 9.1-4, " Emergency Dosimeter Log", located in the Emergency Locker. 4.2.5.5 Complete applicable parts of Attachment 1.0, "Offsite Monitoring Team Checklist", Form EP 8.2-1, and submit it to the EOFC (Onsite Survey Team Director at the OSC) for approval for departure. 4.2.5.6 Attend a briefing regarding the emergency conditions l ( and monitoring objectives by the RAS (Onsite Survey Team Director at the OSC). 4.2.5.7 Establish and maintain radio communications with the l EOF Field Team Communicator (or the TSC Field Team Communicator if the EOF is not activated). 4.3 SUBSEQUENT ACTIONS 4.3.1 The RAS (Dose Assessment Coordinator at the TSC) shall perform the following: l 4.3.1.1 Assess the need for Offsite Monitoring Team personnel I thyroid dose determination and Potassium Iodide (KI) administration in accordance with EPP 01-9.3, "Radioprotective Drugs." 4.3.1.2 Review incoming field data, Attachment 4. 0, " Radiological Monitoring Data Sheet", Form EP 8.1-3. .. EP P. 01-8. 2.- ..%...... p t... i.s .' gg g.gz .u: .t .;,... p g g. 0.23 a; ;J jj,a. '5,, *,'..:.. . a c.;'..r ,J i. ; %

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a 4.3.1.3-Accura that tha Doca A22coc=2nt Supervisor (DAC at l TSC) receives the field data following status board updates. C4.3.1.4 Direct the updating of status boards through the EOF l Radiological. Status Recorder (TSC Radiological Status Recorder at the TSC). 4.3.1.5.0, " Field Team Message Form," Form EP 8.2-8, may be utilized for instructions gi.ven to the field teams. 4.3.1.6 Assure the proper documentation, and analysis of, all. l incoming field samples at the EOF Environmental Laboratory. 4 NOTE: The Onsite Survey Team Director shall assume this responsibility at the OSC Bio-Assay Laboratory in the event the EOF is~not activated. 4.3.1.7 Coordinate the integration of County and State l personnel into Offsite Monitoring Teams as outlined in EPP 01-8.3, " Joint Radiological Monitoring Team i Formation and Operation." 4.3.2 The EOF Field Team Communicator (TSC Field Team Communicator at the TSC) shall perform the following: 4.3.2.1 Communicate all directions from the RAS (Dose Assessment Coordinator at the TSC) to the proper Offsite Monitoring Team. I 4.3.2.2 The EOF Field Team Communicator (TSC Field Team Communicator at the TSC) should use Attachment 7.0, " Field Monitoring Team Data," Form EP 8.2-7, to track Offsite Monitoring Team data by location. l 4.3.2.3 Record communicated data from the Offsite Monitoring Teams on Attachment 4.0, verify calculations and submit the information to the RAS (Dose Assessment Coordinator at the TSC) for approval. j 4.3.3. The Offsite Monitoring Team shall perform the following: 4.3.3.1 Advise the TSC or EOF Field Team Communicators of plume location and movements. EPP 01-8.2 .. R ev. 3,,.. ,a - q p a g e ' 6

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s. ~ .t Proceed, as directed, to an offsite monitoring l C 4.3.3.2 location by referencing Attachment 2. 0, " Pre-Determined Emergency Sampling Locations", or.0, " Environmental TLD and Air Sampling Locations". 4.3.3.3 Observe count ~ rate and/or dose rate monitoring l instrumentation while enroute to monitoring locations or when directed to conduct plume traverse / plume tracking activities as follows: a. Hold the detector of the monitoring instrumentation inside the vehicle and above the lap. The vehicle windows should be open. b. Upon observing a count rate or dose rate above normal background, notify the EOF Field Team Communicator (TSC Field Team Communicator at the TSC) of your location. NOTE: Because of its greater sensitivity as a detector of beta / gamma radiation relative to a dose rate instrument, the count rate instrument will provide the first indication of radiation from a plume. ( c. Conduct further plume traverse / tracking only as directed by the applicable Field Team Communicator. If traverse / tracking instructions are requested, the Offsite Monitoring Team shall, to the best of their ability, identify and transmit the location of the maximum readings noted, as well as, plume boundaries. NOTE: Maintain an estimate of the time spent in the plume. 4.3.3.4 Communicate the arrival of the Offsite Monitoring Team at the designated sampling location to the applicable Field Team Communicator. l 4.3.3.5 Perform, as directed, field data. collection, sampling l and record keeping as follows: NOTE: It may be necessary to collect field samples and then move, after informing the applicable l Field Team Communicator, to a low background area in order to estimate sample activities in the field.

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^ i e k- ? Record all sampl'ing locations, times, measurements and ( 4.3.3.5.1 sample data on Attachment 4. 0, " Radiological Monitoring Data Sheet," Form EP 8.1-3. Communicate data to the applicable Field Team Communicator as soon as possible. 4.3.3.5.2 Place all field samples in separate sample containers l and label with the following information, if applicable: - date'and time - location - individual / field team - type and description - air monitor samples times (start & stop) - air monitor samples flows (initial & final) - radiation reading at contact 4.3.3.5.3 Dose Rate Measurement Procedure: l a. Perform dose rate measurements with the dose rate detector approximately five (5) feet.above ground level. b. Measure the dose rate with the beta shield open C for a beta / gamma reading. c. Measure the dose rate with the beta shield closed for a gamma reading. d. Quantify the beta dose by subtracting the gamma reading from the beta / gamma reading and multiplying this result by the beta correction factor on the instrument. NOTE: Direct contact with the plume is indicated by significant beta measurements. Conversely, the absence of beta radiation indicates exposure to " sky shine radiation," gamma radiation from plume overhead. 4.3.3.5.4 Air Sample Collection: l l g a. Assemble a particulate filter (coarse side out) and a silver zeolite cartridge (flow arrow pointed at sampler) in the sampling head and install the head on the sampler. \\ .? , E P P. 01 -,8. 2 ' l,

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Q, e, n ',, y, e s -k. I '> C b. Place the sampler so that a representative sample may be collected. Plug the sampler'into the-vehicle inverter (vehicle must be running) and start the sampler. noting the actual flow-rate and starting time. ^ NOTE:. Offsite air sample flow rates should be set at 2.0 cfm for 10 min., providing whole body dose rates permit. Higher sample rates and/or i W' shorter sample times may be utilized to l minimize exposures. c. Allow the sampler to run for the requested time 1 (normally at least 10 mins.). Note the final flow rate, stop the sampler and record stop i time. d. Remove the particulate filter and silver zeolite cartridge from the sampler head, bag and label, and determine their gross activities if j requested. -If dose rates are prohibitive, bag j the entire air sampler and move to a low j background area. NOTE: Before measurement, aspirate the cartridge with a 3-second draw of fresh (non-plume) air or wave vigorously in air with both ends open for 20 seconds. 1 4.3.3.5.5 Determination of Gross Particulate Activity j i a. Measure a background count rate using a count rate instrument with an HP-210 probe. b. Place the filter in a planchette in the sample i holder, inlet side facing up, 4 i 2 c. Measure the particulate filter count rate by placing an HP-210 probe in the sample holder. d. Bag and label the particulate filter and discard j the used planchette in a plastic bag. t e. Calculate gross particulate activity as follows: 4 PARTICULATE ACTIVITY CALCULATION i (Gross CPM)- (Bkgd CPM) = NCPM = Activity in

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1 (- (0.96) and counter eff. (0.10) l. k NCPM 3 = (Gross CPM - Bkgd CPM) (time, min) (flow, avg) vol, ft = NOTE:.0, " Particulate Sampler Conversion Graph," may be utilized to. verify' calculations or in the event of calculator failure. If the calculator fails, notify the EOF, 4.3.3.5.6 Determination of Gross Iodine Activity: a. Determine a background c'ount rate using a count rate instrument with a HP-210 probe. b. Aspirate cartridge according to Note in l 4.3.3.5.4.d c. Bag and label the silver zeolite cartridge. d. Measure the silver zeolite cartridge count rate by placing an HP-210 probe directly at contact to .the inlet side of the cartridge. ( e. Calculate gross iodine activity as follows: IODINE ACTIVITY CALCULATION (Gross CPM)- (Bkgd CPM) NCPM = Activity in =

(6. 04 E 07)(VOL FT )
(6.04 E

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(0.96) and counter eff. (0.01) l NCPM (Gr ss CPM - Bkgd CPM) = 3 (time, min) (flow, avg) vol, ft = NOTE:.0, " Iodine Sampler Conversion Graph," may be utilized to verify calculations or in the event of calculator failure. If the calculator fails, notify the EOF. 4.3.3.5.7 Ground Deposition Survey (direct scan): NOTE: Ground measurements should be made in an undisturbed, open area away from vehicles, buildings, roads, evacuated areas, or piled gravel or soil. Care should be exercised to ' prevent puncture of,the mylar window and/or . - a co n tam i n a t io n. o'E : t h 6.p r o be; *. y;, + '....;. < *.,,..,. .t;- - ?...,. ;,... - :.

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4 x 7; P r. W m i I Determine the background count rate using a count a. rate instrument with an HP-210 probe approximately three (3) feet above ground level. i ~ b. Determine a gross count rate approximately two (2) inches above ground level. Determine the not count rate (NCPM) by c. subtracting the background count rate (Bkgd CPM) from the gross count rate (Gross CPM). 1 d. Record results in the comments section of Attachtcant 4.0, " Radiological Monitoring Data Sheet," Form EP 8.1-3. l 4.3.3.5.8 Ground Deposition Survey (smear): l t NOTE: The area to be swiped should be a flat, smooth ) surface (e.g., a car hood other than that of i the team vehicle), using care not to shake off the collected material. 2 a. Swipe a 100cm area using a smear pad. I b. Measure the background. count rate using a count rate instrument with an HP-210 probe. ( Place the smear in a planchette in the sample c. holder. d. Measure the gross count rate by placing an HP-210 probe in the sample holder. t i Bag and label the smear pad. e. f. Determine the net smearable contamination (sample cpm) by subtracting the background count rate i from the gross count rate. J g. Calculate the smearable contamination in uCi/m as follows: uCi/m2 (NCPM)3 = 4.4x1U where: 3 2.2x10 includes detector efficiency, area correction and dpm conversion L i L c I.,.',* :,....* . p '.. A. 4,4..'y*,. '...~ t. :. l.. f.: l' *3-.~.2 .<.er. ',. o.. M.. ;...,.f .s ~.. .3..".. e w ... 'l* 'b '. ). '.

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s,- I h. Record the results in terms of uCi/m in the C comments section of Attachment 4.0, " Radiological Monitoring Data Sheet," Form EP 8.1-3 and on the sample label. 4.3.3.5.9 Soil Sample Collection: l NOTE: Soil samples should be obtained in areas free of any vegetation. ~s Wearing gloves, remove gpproximately the top 1/2 a. inch of soil from a 1 m area using a trowel. b. Bag and label the soil sample. 4.3.3.5.10 Vegetation Sample Collection: l Wearing gloves, cut vegetation growth down t a. approximately 1 inch from ground level in a 1 m2 area. b. Bag and label the-vegetation sample. 4.3.3.5.11 Snow Sample Collection: l NOTE: Snow samples should be collected in areas free C from vegetation, buildings, etc. Wearing gloves, collect aPproximately the top 3 a. inches of snow in a 1 m2 area. b. Bag and label the snow sample in double plastic bag. Transfer the snow sample once it has melted to a c. labeled sample bottle. 4.3.3.5.12 Liquid Sample Collection: j NOTE: Sources of water to be sampled should normally be undisturbed, stagnant bodies, such as ponds or cattle troughs. 1 Wearing gloves, immerse a one liter bottle in a. water source until full. Avoid getting potentially contaminated water on the skin. b. Place the liquid sample bottle in a plastic bag and label. .. f ..,. v..,. G, O., ;.,... ... : --:...: n..e; s.i; np;...h +.:. :. 7. ;: ;.. 1 . :: 5. *4, Q.. g. ; c;. . :;...... y "._.

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i l Communicate to the applicable Field Team Communicator j C 4.3.3.6 that sampling is completed and request further instructions. NOTE: Offsite Monitoring Teams shall move to an area l away from direct plume exposure during periods when radiological monitoring activities are not being conducted. 4.3.3.7 Upon completion of all offsite radiological monitoring - l activities the following shall be performed: 4.3.3.7.1 Submit all field samples collected and corresponding l data sheets to the EOF Environmental Laboratory (Bio-Assay Laboratory at the OSC) for further analysis and retention. NOTE: Samples that have significant activity should .be placed in a shielded area to reduce personnel exposures and radiation fields in the laboratory. 4.3.3.7.2 Complete a " Radiological Sample Inventory Log," Form l EP 11.3-2 for offsite samples. Completed inventory logs should be routed to the RAS (OSTD at the OSC). l 4.3.3.7.3 Enter final dosimetry readings on Form EP 9.1-4, l " Emergency Dosimeter Log," for each Offsite Monitoring Team member.

5.0 REFERENCES

5.1 Wolf Creek Generating Station Radiological Emergency Response Plan 5.2 EPP 01-8.3, " Joint Radiological Monitoring Team Formation and Operation" 5.3 EPP 01-9.1, " Exposure Control and Personnel Protection" 5.4 EPP 01-9.3, "Radioprotective Drugs" 5.5 EPP 01-11.3, " Logs and Record Keeping" l 5.6 HPH 03-002, " Radiation Survey Methods" 5.7 HPH 03-003, " Airborne Radioactivity Surveys" 5.8 HPH 03-011, " Contamination Survey Methods" ..? .:;... i,....,: 7. :,. ; r - 2,.+...]

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RECORDS C 6.0 6.1 Form EP 8.2-1, "Offsite Monitoring Team Checklist" 6.2 Form EP 8.1-3, " Radiological Monitoring Data Sheet" 6.3 Form EP 8.2-7, " Field Monitoring Team Data" 6.4 Form EP 8.2-8, " Field Team Message Form" 6.5 The records generated by this procedure during an actual emergency shall be forwarded to the Emergency Planning Coordinator (EPC) at the termination of the emergency. The EPC forwards the records to the WCGS vault for storage. These records will be retained for the life of the plant. These records shall be considered QA records. 6.6 The records generated by this procedure during drills and exercises shall be forwarded to the EPC upon termination of the drill or exercise. The EPC shall maintain these records for at least one year. These records shall be considered non-QA records. 7.0 ATTACHMENTS ( 7.1.0, "Offsite Monitoring Team Checklist" 7.2.0, " Pre-Determined Emergency Sampling Locations" 7.3.0, " Environmental TLD and Air Sampling Locations" 7.4.0, " Radiological Monitoring Data Sheet" 7.5.0, " Particulate Sampler Conversion Graph" 7.6.0, " Iodine Sampler Conversion Graph" 7.7.0, " Field Monitoring Team Data" 7.8.0, " Field Team Message Form" 1 l ' J . il,;-..I...JEPP. 01 8 4,',*4 p,l,Y.' '-d , * '..'.;. e. . I" f,. ,J.

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9 FORM EP 8.2-1 REV. 1 l ATTACHMENT 1.0 1 OFFSITE MONITORING TEAM CHECKLIST Date/ Time Communication I.D. Vehicle No. Team Members KG&E KG&E ~ KG&E KGEE Team Member Initials offsite monitoring kit inventory complete / Equipment operability checks complete / Offsite vehicle fueled and properly equipped / Proper dosimetry (TLD, hi - lo pencils) and respirators obtained / Initial dosimetry readings entered (Form EP 9.1-4) / Communication established and identification issued / Individual responsibilities assigned. / Team briefing conducted on emergency conditions and monitoring objectives. / DAC requested to inform Security that team is preparing to leave site. Comments: Radiological Assessment Supervisor (EOF), Date Onsite Survey. Team Director.(OSC) .,.;...,rfr. .., i.,. ;. w. J. f ',, ' '. - .. ' :.,7.' ' i.~* EPP.01 -8. 2". \\ ;.,, ^ !. ,..,",4 :.:. l.. '. Rev. % -l ' F ', n, .*.?. : Page 15 ot.22

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9 ATTACHMENT 3.0 ENVIRONMENTAL TLD AND AIR SAMPLING LOCATIONS C 39, f F ( L 7 l i I / i i i4 a*. K.i k / [\\ l

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ATTACHMENT 5.0 PARTICULATE SAMPLER CONVERSION GRAPH gs I I l i lllli I i I l l 1111 I I l lllll l l l ' Ill!" I F' 4 / / / / f i _s i if I i i / is i i / - j i ) / b8 uCi/cc / l e C / i f \\ s J l d' .1 i ~/ i / / / / 10 '0 ~ L i l I lilli i I l l 1 111, 3 l l l l llll4 l l l lllllf i 2 4 10 10 10 lo i COUNTS / MIN. 1 I 3 I'E : ' 'Tliis* graph' assumes a '-20 ' Pt..Ait.'5 ample". * '

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= ATTACHMENT 6.0 IODINE SAMPLER CONVERSION GRAPH I -~ g I l l lIlll l l llll l l l l l l I! / .1 / ~' . fr / /_ - / ~_ ~ g e f i / i / 4 4.t.. f uCI/cc f [ 7 l ( 10 1 s s is ' 4 ii/ i /. j'/tl-( 7 10 10' th3 O COUNTS / MIN. i l l HOTE: This graph assumes a 20 Ft Air Sample Multiply uCi/cc accordingly. .. i -; : s. 'c. '" 'E Pp. 01.- 8 ; 2 3'~.- . - * ~ .. :a s '...'.'. ', t, ;:. ; '- . ' _.. (, '., _ t... '., _., *,,. ~ n pi;y,. :3, s'.'.-- K,. .:.r - _ c. ~ ', ~- pggg 29.eg. 23; .[. ; :...., c.. .:.^*,'..'. .. 1-

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FORM EP 8.2-7 REV. 0 ATTACHMENT 7.0 C FIELD MONITORING TEAM DATA TEAM, DESIGNATION: TIME: LOCATION: 5 FOOT HEIGHT DOSE RATE: WINDOW OPEN mr/hr. WINDOW CLOSED mr/hr. SILVER ZEOLITE CARTRIDGE COUNT RATE cpm PARTICULATE FILTER COUNT RATE cpm GROSS IODINE ACTIVITY uCi/cc GROSS PARTICULATE ACTIVITY uCi/cc GROUND DEPOSITION uCi/m or cpm PERFORM SOIL SAMPLE (Y/N) PERFORM SNOW SAMPLE (Y/N) PERFORM LIQUID SAMPLE (Y/N) SAMPLE SHIELDED (Y/N) TRANSPORT SAMPLES TO EOF (Y/N) SELF READING POCKET DOSIMETER READING mr RECEIVED BY: d. ', ' 'l.g :., -,;{'

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~.m_ FORM EP 8.2-8 REV. O E ATTACHMENT 8.0 f FIELD TEAM MESSAGE FORM TIME TEAM (S) INSTRUCTIONS: o************************************************************************* TIME COMMUNICATED MESSAGE REPEATED'BACK YES NO (EOF /TSCFIELDTEAMCOMMUNICATOR REPLY: TIME RECEIVED MESSAGE REPEATED BACK YES NO RETURN TO DAC/ RAS

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KANSAS GAS AND ELECTRIC COMPANY WOLF CREEK GENERATING STATION RADIOLOGICAL EMERGENCY RESPONSE PLAN IMPLEMENTING PROCEDURE JOINT RADIOLOGICAL MONITORING TEAM FORMATION AND OPERATION EPP 01-8.3 Revision 1 ( f ~ FAfYA4 h lY EMERGEN PLANNI COORDINA OR REVIEW DATE ~ 01 W A - 1 P S fm m EMERGENCY PLANNING ADMINISTRATOR REVIEW DATE $h PSRC APP L REC MENDATION DKTE / W f 97/N V.P. NltCY, EAR APPRQVAL DA'fE RELEASED A -df-f(0 . DATE ~~ . :. ; Vi.. li..... :. :~ + ::. r.-:.:.. :.:-

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s-y j s e,- t E A-1.0 PURPOSE The purpose of this procedure is to provide guidance for the formation, deployment and operation of Joint Radiological Monitoring Teams (JRMTs) in the event of a radiological emergency at the Wolf Creek Generating Station (WCGS). 2.0 APPLICABILITY a This procedure applies to all personnel assigned to the JRMTs and those personnel responsible for providing the direction of these teams. This procedure shall be utilized for team formation after the activation of the Emergency Operations Facility. (EOF). 3.0 DEFINITIONS 3.1 JOINT RADIOLOGICAL MONITORING TEAMS (JRMTs) The JRMTs are offsite radiological monitoring teams comprised of one member from Kansas Gas and Electric Company (KG&E), and one member from the State of Kansas and/or Coffey County. 3.2 EMERGENCY RESPONSE FACILITY (ERF) Emergency Response Facilities are those emergency f acilities at which members of the JRMTs will receive'- direction during the formation and deployment of teams. These facilities will be the EOF, State Forward Staging Area, Coffey County Emergency Operations Center (County EOC), or other locations as directed. 3.3 PRE-DETERMINED EMERGENCY SAMPLING LOCATIONS Those offsite monitoring locations, as identified in.0, used for consistency in offsite monitoring as agreed to by KG&E, Coffey County, and the State of Kansas. 3.4 OFFSITE Offsite is that area cutside the WCGS owner-controlled area for purposes of this procedure. - .:o ..;,..:.,....:..;....;,.. ;eypfof g;.y.y...9,., F.. v...+.. ..i; ;,.. .. j ,.3 ..r 9;:';.~l'_; 9 :.....;.~?,pge.1.::;g.s:_ 1 c

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g-ll 4.0 INSTRUCTIONS 4.1 PRECAUTIONS 4.1.1 Each JRMT shall be composed of at least two (2) individuals, of which, at least one (1) individual is a KG&E Health Physics Technician,. trained in offsite monitoring. 4.1.2 All offsite monitoring activities shall be conducted such that exposures are maintained as low as reasonably achievable (ALARA). 4.1.3 Each JRMT shall keep a dose rate or count rate monitoring instrument on at all times to detect unexpected or excessive exposure from the plume while performing radiological monitoring activities. 4.1.4 JRMT personnel shall don protective clothing and respirators as directed by the Radiological Assessment Supervisor (RAS) or as appropriate to minimize skin contamination and internal exposure. 4.1.5 The KG&E and State of Kansas radiological assessment managers at the EOF should consider the use of Potassium Iodide (KI) tablets, in accordance with ( applicable procedures and EPP 01-9.3, "Radioprotective Drugs", in the event that high levels of radioiodine are actual or imminent. 4.1.6 KG&E JRMT personnel shall not exceed 10CFR, part 20 exposure limits without approval from the Duty Emergency Manager (DEM). State of Kansas and Coffey County monitoring team personnel exposure shall be authorized by State of Kansas radiological assessment management. 4.1.7 JRMT personnel shall assure that all transmissions of data are clear and concise. 4.1.8 JRMT personnel shall use Operations radios on Channel 4 or equivalent State frequency as the primary method of communication while dispatched and public telephone as a back-up. Utilize the following number in case of a loss of communication. Radiological Assessment Supervisor (EOF) PH.# 364-8831 EXT-391 ,.i..g, ,,2 E.P.P 0.L,8k3' M.,,,./.pf i ; e (,,../:t.;q, 4 ;:,...e.,:.,..; ' v,' g, Q. p., q, r, ~, . Q. 'gey, j t..y;$7,4 Yl. s ...<,g... j:. . e:,7.:. -( g.. ..,0-r ,y , :;. 4.y. '. t,. ..pgge;2 $f,.. -)' e -,..;.I.M..i qs., . ;. J., . 3.;...

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.t.*- M-t. p 4& 4.2 INITIAL ACTIONS 4.2.1 The formation and deployment of JRMT shall be accomplished from the EOF upon activation or as directed by the Radiological Assessment Supervisor (RAS). 4.2.2 The 7RMT shall consist of at least two members, one of which shall be a KG&E Health Physics Technician who p.;..- will act as Team Leader. 4.2.3 JRMT personnel will be assigned'an emergency response vehicle if available. In cases where no vehicle is available, personal vehicles may be used to transport team members. 4.2.4 The RAS shall perform the following: 4.2.4.1 Direct State and County personnel to assume JRMT l responsibilities upon arrival to the EOF or designated location. NOTE: Obtain JRMT State member assignments from State RAM, then inform EOFC of the assignments. 4.2.4.2 Assure a briefing is conducted by the EOF Coordinator ( (EOFC) prior to team dis _ patch. 4.2.4.3 Issue the JRMT communication identification as l required. 4.2.4.4 Assure the completion of the Attachment 1.0, " Joint l Radiological Monitoring Team Checklist," Form EP 8.3-1. 4.2.4.5 Direct the EOF.C to coordinate the forma' tion and l dispatch of the JRMT. l NOTE: A minimum of four monitoring teams composed of any combination of Offsite Monitoring Teams i and/or JRMT shall be organized as soon as practicable whenever a radiological release is imminent or is in progress. 4.2.4.6 Brief the EOFC, as appropriate. l 4.2.4.7 Direct the JRMTs through the Field Team Communicator I once prepared. 4.2.4.8 Provide the State of Kansas Radiological Assessment l Manager (SRAM) and Coffey County Radiological Officer with JRMT assignments and operational status.

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m e ? a ? 4.2.5 The EOFC shall perform the following: I I 4.2.5.1 Conduct a briefing prior to JRMT dispatch on the following items as applicable: I 4.2.5.1.1 Magnitude and composition of any actual or potential radiological releases to the environment. s 4.2.5.1.2 The source of leakage and the release rate. l l 4.2.5.1.3 Composition of the release (noble gas, radioiodine, or. particulate). 4.2.5.1.4 Expected duration of release. l 4.2.5.1.5 Projected or measured offsite dose rates and/or I airborne activity. 4.2.5.1.6 Current and projected meteorological conditions (w ind l speed, wind direction). 4.2.5.1.7 Location to join WCGS Offsite Monitoring Teams if l applicable. - 4.2.5.2 Complete Attachment 1.0, prior to dispatching teams. l 1 4.2.5.3 Issue JRMT personnel proper personnel monitoring devices and record such information on Forms EP 9.1-2, " Emergency Exposure Authorization" and EP 9.1-3, "New TLD Dosimetry Issue Log." 4.2.5.4 Assure radiological monitoring equipment operability. l 4.2.5.5 Assure adequate JRMT personnel exposure limits are l implemented by the State RAM. l 4.2.5.6 Submit completed Attachment 1.0 to the RAS. 4.2.5.7 Notify RAS that JRMTs are ready to be dispatched. l 4.2.5.8 Perform EOF habitability checks every 30 minutes l ~ unless instructed otherwise by the RAS. 4.2.6 The EOF Field Team Communicator shall perform the' l following: ) 4.2.6.1 Verify communication identification when the JRMT l I establishes radio communications with the EOF. 4.2.6.2 Notify the RAS when the JRMT are ready to depart. l .i .);.y..t,' .Q;h..:u; ql q.f."..

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a A m-a__ ^ -^ s 4.2.7 The JRMT shall perform the following: l 4.2.7.1 Request an emergency kit from the EOFC and perform an l ~ inventory check against the inventory list provided in -the kit. l NOTE:- An inventory of the kit's contents is only required if the kit seal has been broken. l ~ 4.2.7.2 Perform the required operability checks on the equipment contained within the emergency kit. s NOTE: If inoperable instruments are discovered, i backup instrumentation and/or batteries are available in the emergency locker. 4.2.7.3 If available, obtain the keys to the assigned l radiological emergency response vehicle from the EOFC 4 and assure that the vehicle is fueled and properly j equipped prior to dispatch. NOTE: If no KG&E emergency response vehicle is available, the use of personal vehicles may be authorized. l Obtain appropriate dosimetry and respiratory C 4.2.7.4 protection devices from the EOFC. As a minimum, JRMT personnel shall wear a thermoluminescent dosimeter (TLD), low range and high range direct reading pencil dosimeters. i NOTE: Two extra respirators should be taken for JRMT l members. 4.2.7.4.1 Assure the EOFC records the serial numbers and initial readings of the dosimetry devices for each JRMT member on Form EP 9.1-4, " Emergency Dosimeter Log," located in the Emergency Dosimeter Log Book in the emergency locker. 4.2.7.5 Establish and maintain radio communications with the l I EOF Field Team Communicator. i l 4.2.7.6 Complete applicable parts of the Attachment 1.0, and l submit it to the EOFC for approval to depart. f 4.2.7.7 Attend a briefing by the EOFC regarding the emergency l conditions and monitoring objectives. 1 NOTE: If circumstances warrant, JRMTs may be formed and/or dispatched at locations.other than the EOF. 3

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4.3 SUBSEQUENT ACTIONS I( k 4.3.1 The RAS shall perform the following: l 4.3.1.1 In coordination with offsite agency' radiological managers assess the need for JRMT personnel to utilize Potassium Iodide (KI) based on a thyroid. dose determination in accordance with EPP 01-9.3, "Radioprotective Drugs" or applicable procedures. 4.3.1.2 Review incoming field data, Attachment 4.0. l 4.3.1.3 Assure that the Dose Assessment Supervisor (DAS) receives the information on Attachment 4.0. 4.3.1.4 Direct the updating of status boards through the EOF l Radiological Status Recorder. 4.3.1.5.0, " Field Team Message Form," Form EP 8.2-8, may be utilized for instructions given to the field teams. 4.3.1.6 Coordinate establishment of new or relief JRMTs. l 4.3.1.7 Forward completed copies of Attachment 4.0 to the DAS l for retention and further processing. C 4.3.1.8 Forward completed copies of Attachment 1.0.to the RAM l for retention and further processing.- 4.3.2 The EOFC shall: 4.3.2.1 Distribute appropriate dosimetry and respiratory protection devices to the JRMT personnel. 4.3.2.2 Record the seria3 numbers of the dosimetry devices and initial readings of the pencil dosimeters before issuing to JRMT personnel. 4.3.2.3 Assure the proper documentation of all incoming field samples at the EOF Environmental Laboratory. 4.3.2.4 Document and prepare for shipment all radiological monitoring samples. s. . lr N.9.m: ( '.' ~.. _,:~ k: U.'I" U W',:l, ;!* ':::. T 4 ? '+ ...>*.,::... i, 1..'.V.' '. 9 : ;' ..,.5.$.;'. r.. y

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4.3.2.5 Establish radiological ingress / egress points for l (# returning JRMTs and incoming personnel. s 4.3.2.6 Obtain dosimeters from returning JRMTs and record results as applicable-4.3.3 The EOF Field Team Communicator shall perform the following: 4.3.3.1 Communicate all directions from the RAS to the proper JRMT. 4.3.3.2 The EOF Field Team Communicator should use Attachment 7.0, " Field Monitoring Team Data," Form EP 8.2-7, to l track JRMT status locations. 4.3.3.3 Record communicated data from the JRMT on Attachment 4.0, verify calculations and submit the information to l the RAS for approval. 4.3.4 The JRMT shall perform the following: 4.3.4.1 Advise the EOF Field Team Communicator of the Plume location and movements. ( 4.3.4.2 Proceed, as directed, to offsite monitoring locations -l by referencing Attachment 2.0, or Attachment 3.0. 4.3.4.3 Observe count rate and/or dose rate monitoring l instrumentation while e6 route to monitoring locations or when directed to conduct plume traverse / plume tracking activities as follows: a. Hold the detector of the monitoring instrumen-tation inside the vehicle and above the lap. The vehicle windows should be open. b. Upon observing a count rate or dose rate above normal background, notify the EOF Field Team Communicator of the location. NOTE: Because of its greater sensitivity as a detector of beta / gamma radiation relative to a dose rate instrument, the count rate instrument will provide the first indication of encountering radiation from a plume. p ( [-s.'... : ?.h :':. 1 m. = w n :.i. ' ? ':r. i* j'i'.ll-' :.n zpP,'%2 8j3:J. *Lls.,;;n :q d . y.,,,(,i...?g.j,,., ,,v. 7 : (;' *l,a,'f C. :',, q..,,'. .R k v.'t..li.',,.'.',2:,.3..:'./.1..' * [ ; [ :l V f p w... .p,gp.7 y o g;. 24 - O:'.C ': -. '" ? i ? :.7. ,. ',:.. ;; :.,.... u....,. n :. ..{::. x..~.: :.., J :,,,7.:

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l(I' c. Conduct further plume traverse / tracking only as directed by the EOF Field Team Communicator. If traverse / tracking instructions are requested, the JRMT shall, to the best of their ability, identify and transmit the location of the maximum readings noted, as well as, plume boundaries. NOTE: Maintain an estimate of the time spent in the plume. 4.3.4.4 Communicate the arrival of the JRMT at the designated sampling location to the EOF Field Team Communicator 4.3.4.5 Perform, as directed, field data collection, sampling l and record keeping as follows: NOTE: It may be necessary to collect fiel'd samples and then move, after informing the EOF Field Team Communicator, to a low background area in order to estimate sample activities in the field. 4.3.4.5.1 Record all sampling locations, times, measurements and l sample data on Attachment 4.0. Communicate data to the EOF Field Team Communicator as soon as possible. 4.3.4.5.2 Place all field samples in separate sample containers l and label with the following information, if applicable: - date and time - location - individual / field team - type and description - air monitor samples times (start & stop) - air monitor samples flows (initial & final) - radiation reading at contact 4.3.4.5.3 Dose Rate Measurement Procedure: l a. Perform dose rate measurements with the dose rate detector approximately five (5) feet above ground level. b. Measure the dose rate with the beta shield open for a beta / gamma reading. i c. Measure th'e dose rate with the beta shield closed for a gamma reading. . >. }....:.i;. g.,,,...... p... gpp 3.g,1; g,; y,,, s., _ '. f.; ;,% j y,,g,7 ' .t - 1.. : a.,,.....r ,,i,,.e.f a ' ~ ...,' i.c* '4:ll A.. y;p. i... :... ;,'. 1,R,v... 2. ; J !.

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l(" d. Quantify the beta dose by subtracting the gamma reading from the beta / gamma reading and multiplying this result by the beta correction factor on the instrument. NOTE: Direct contact with the plume is indicated by significant beta measurements. Conversely, the absence of beta radiation indicates exposure to " sky shine radiation," gamma radiation from plume overhead. 4.3.4.5.4 Air Sample Collection: l a. Assemble a particulate filter (coarse side out) and a silver zeolite cartridge (flow arrow pointed at sampler) in the sampling head and install the head on the sampler. b. Place the sampler so that a representative sample may be collected. Plug the sampler into the vehicle inverter (vehicle must be running) and start the sampler noting the actual flow rate and starting time. NOTE: Offsite air sample flow rates.should be set at 2.0 cfm for 10 min., providing ALARA consider-C ations are not exceeded. Situations where these considerations may be approached could dictate an increase in flow rate and/or reduction in sample time. c. Allow the sampler to run for the requested time (preferably at least 10 mins.). Upon stopping the sampler, note the final flow rate and stopping time, d. Remove the particulate filter and silver zeolite l cartridge from the sampler head and determine their gross activities if requested. If dose rates are prohibitive, bag the entire air sampler and move to a low background location. NOTE: Before measurement, aspirate the cartridge with a 3-second draw of fresh (non-plume) air or wave vigorously in air with both ends open for 20 seconds. 4.3.4.5.5 Determination of Gross Particulate Activity a. Measure a background count rate (CPM) using a count rate instrument with an HP-210 probe. .. ~ ;. 4: 'y .y;; y. w., *. : '..,.. :.,.;].:. ',ig :. :.EPP 4 01y 8.L3 : -. - ?..y *n.. ;';L A*: n: i s._ s :. g- . p.gy y, ;1,., .,7 . c, y ,s.. n.h:l.c.\\.. g '..:,:e, :.,.. ~ ~a .v...py e_.gf % f..2k : _ ~. :'. ..i l ^ g t- ..:;i.4.p. 'U. ;.:.y:. v t. M ;;. i. .z:. :.,: y.'. :. e

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E b. Place the filter in a planchette in the sample l l(~ ( holder, inlet side facing up. c. Measure the particulate filter' count rate by placing an HP-210 probe in the sample holder. d. Bag and label the particulate filter and discard the used planchette in a plastic bag.- . Calculate gross particulate activity as follows: e. PARTICULATE ACTIVITY CALCULATION NCPM = Activity in uCi/cc (6.04E 09) (VOL FT ) Where: NCPM = (Gross CPM) - (Bkgd CPM) 6.04E 09 = (28320 ) (2. 22E 06) (Filter ef f) (Counter eff) (Sample time, min) (Sampler flow, avg.). VOL ft = ( NOTE: Filter efficiency is conservatively assumed to be 96% and counter efficiency is 10%..0, " Particulate Sampler Conversion Graph," may be utilized to verify calculations, or in the event of calculator failure. If calculator fails, notify the EOF. 4.3.4.5.6 Determination of Gross Iodine Activity: l a. Determine a background count (Bkgd CPM) rate using a count rate instrument with a HP-210 probe. b. Aspirate cartridge according to Note in 4.3.4.5.4.d l c. Bag and label the silver zeolite cartridge, d. Measure the silver zeclite cartridge count rate by placing an HP-210 probe directly at contact to the inlet side of the cartridge. ,, l ( .,- : ~a:. , o h <.'(. .s .,,-i,.,. .. gyp 301ag 3 3.,.. ~

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Where: NCPM = (Gross CPM) - (Bkgd CPM) 6.04E 07 = (28320)(2.22E 06)(Filter eff)(Counter-eff) 3 (Sample time, min) (Sampler flow, avg.) VOL ft = NOTE: Filter efficiency is conservatively assumed to be 96% and counter efficiency is 0.1%..0, " Iodine Sampler Conversion Graph," may be utilized to verify calculations, or in the event of calculator failure. If calculator fails, notify the EOF. 4.3.4.5.7 Ground Deposition Survey (direct scan): g NOTE: Ground measurements should be made in an undisturbed, open area away from vehicles, buildings, roads, evacuated areas, or piled gravel or soil. Care should be exercised to prevent puncture of the mylar window and/or contamination of the probe. a. Determine the background count rate (Bkgd CPM) using a count rate instrument with an HP-210 probe at approximately three (3) feet above ground level. b. Determine a gross count rate at approximately two (2) inches above ground level. c. Determine the net ground count rate by subtracting the background count rate from the gross ground count rate. d. Record results in the Comments Section of.0. .j( x ..,.E P P. O l-87 3...,'. - 2 ,.,,...o ,.' ',, c c %, ','. * .~Re v...'1.^. v.

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= d. Report the results back to the EOF as soon as j possible. NOTE: The administrative action level is 40 MPC hours in one week. If you suspect exceeding this limit notify the EOF. 4.3.4.6 Communicate to the EOF Field Team Communicator that l sampling is completed and request further instructions. NOTE: JRMT shall move to an area away from direct l plume exposure during periods when radiological monitoring activities are not being conducted. 4.3.4.7 Upon completion of all offsite radiological monitoring l activities or as directed by the RAS the following shall be performed: 4.3.4.7.1 Submit all field samples collected and corresponding l data sheets to the EOFC for documentation and retention or further analysis. 2

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5.0 REFERENCES

5.1 Wolf Creek Generating Station Radiological Emergency Response Plan 5.2 HPH 03-0'02, " Radiation Survey Methods" 5.3 HPH 03-003, " Airborne Radioactivity Surveys" 5.4 HPH 03-011, " Contamination Survey Methods" 5.5 EPP 01-9.1, " Exposure Control and Personnel Protection" EPP 01-9.3, "Radioprotective Drugs" ( 5.6 5.7 EPP 01-11.3, " Logs and Record Keeping" 5.8 State of Kansas, Annex A, Nuclear Facilities Incidents Response Plan to Assistance R, Nuclear Emergencies of the State Disaster Emergency Plan. 5.9 Coffey County Contingency Plan for Incidents Involving Commercial Nuclear Power. 6.0 RECORDS 6.1 Form EP 8.3-1, " Joint Radiological Monitoring Team Checklist" 6.2 Form EP 8.1-3, " Radiological Monitoring Data Sheet" 6.3 Form EP 8.2-7, " Field Monitoring Team Data" 6.4 Form EP 8.2-8, " Field Team Message Form" _.:.. '...EPP;0148(3;.. 4 .f

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I 1 kr.7 The records generated by this procedure during an C6.5 actual emergency shall be forwarded to the Emergency Planning Coordinator (EPC) at the termination of the emergency. The EPC forwards the records to the WCGS vault for storage. These records will be retained for the life of the plant. These records shall be considered QA records. 6.6 The records generated by this procedure during drills and exercises shall be forwarded to the EPC upon termination of the drill or exercise. The EPC shall maintain these records for at least one year. These records shall be considered non-QA records. ATTACHMENTS 7.1.0, " Joint Radiological Monitoring Team Checklist" 7.2.0, " Pre-Determined Emergency Sampling Locations" 7.3.0, " Environmental TLD and Air Sampling Locations" -.0, " Radiological Monitoring Data Sheet" C 7.4 7.5.0, " Particulate Sampler Conversion Graph" 7.6.0, " Iodine Sampler Conversion Graph" 7.7.0, " Field Monitoring Team Data" 7.8.0, " Field Team Message Form" g i "r r. 2..... 7, s,> <c.1.. . {...,. / '.,,.,l,_'.; ;, 3...',, -(.j..'.,;,,..,EPF.01,..'8.3.,.3,,,. - ~ f ,7 ...y... ... c..... :. .1 a t., ~. Re v.,1 ~. >. ;~ v.:,.., 5 ~. :. }; b,}s.'.:;..'.

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m T FORM EP 8.3-1 REV 1 I 1 ATTACHMENT 1.0 ~" JOINT RADIOLOGICAL MONITORING TEAM CHECKLIST Date/ Time Communication I.D. Vehicle No. Team Members KG&E/ County / State KG&E/ County / State KG&E/ County / State KG&E/ County / State Team Member Initials Offsite monitoring kit inventory complete / Equipment operability' checks complete / ' Offsite vehicle fueled and properly equipped / Proper dosimetry (TLD, hi - lo pencils) and respirators obtained / Initial dosimetry readings entered (Form EP 9.1-4) / l Communication established and identification issued / oo*********************************************************************** l Individual responsibilities assigned. / Team briefing conducted on emergency conditions and monitoring objectives. / RAS requested to inform Security that team is preparing to leave the EOF. Comments: '3diological Assessment Supervisor. Date. .... v.. :....

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r. s- 'V ATTACHMENT 2.0 l PRE-DETERMINED EMERGENCY SAMPLING LOCATIONS vT 1 _i

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ATTACHMENT 3.0 ENV!RONMENTAL TLD AND AIR SAMPLING LOCATIONS f lt 34 1 1. l l f / _. ) r- ^- l ) i 4 r l [.L35 Nc g q 3 6'., N -1 W / _,l _ 4 N ,40 7.T \\. l 34,! -- - [ e' . T '. ,m l \\ ( a 5 / q ~ W ' ' 7 '\\ \\ ') /. .h h;yl 4 ~W mlI 8.l\\ / J 8,, \\ !-i i L ) E O IMfl;3h /l %f \\! /.. e ! 11 )s .is. l l / 1-- - x r l !12 ik I C. 7 ,'i 7-- ' _ p yw g ( l 24 . Q. _ N-

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RADIOLOGICAL MONITORING DATA SMEET s'. FORM EP 8.1-3 REV. 0 Detet ..,.4' Instrument Dose pate Count flate Air _ Sampler Team Designetton s. Serial Number Calibration Date Dose pate Beta Correction Footor ~ Efficiency Dose Rate Air Sample Date Cosament e '1".. Sample (Windou) Time _ Flou pate Vol. FEtteulate Iodine i pr/Hr er/Hr CFM CFM CFM uCt/co CM CPM CPM uC1/ce Note any environmental aseples 3 f-}, Time Loce OFEN CIOSED ON OFF ON OFF Ft mgd Cross NET ACTIVITY mgd Cross NET ACTIVITY taken and mise. Inforsetton ,, -,. e g ,...,? s O p O O .? H n pp t'*3- .. ", '..(* .K p ,.i-7f f OO Z: t 93 { >3 trj

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ABBREVIATIONS =, ' Crose CPM e Crom? Counta per Min.te g, ,.3, [/.3, I.s;. t PARTICULATE ACTIVITY CALCULATION Bksd CPM e Background Counta o , 9,. per Finnte c fi. ! Cross CPM) - (Bkgd CPM) e NCPM e Aettwity in uCt/en Vol. e Volume in Cutie Feet p l 8 3 3 T e

e(6.04 E a 09)(VOL FT )
(6.04 t a 09)(VOL FT )

Eff. e Efrietency y => 7.'. l .g uC1 e Microcuries ,. ] .t.. f'}. IODINE ACTIVITY CALCULATION co e Cutte Centimeter C/) '? 3 e (Gross CPM) - (Pkgd CFM) e RCM e Aettwity in uC1/eo flember Signaturess I I M ,.. ', d.* O 5

(6.04 E a OT)(VOL fT )
(6.04 E a OT)(VOL FT )

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.s .. =. .+ !l .,.j-BUT[a Turn in Date sheet to Faergener Operations Feellity Environmentel Laboratory = 6 , 7, (Die-assey taboratory at the Operettene $spport Center). l

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0-ATTACHMENT 5.0 PARTICULATE SAMPLER CONVERSION GRAPH I( L -5 I I I I lilli i l I lilll' I I I l l l11' I I ! !Illi io i a J i r t / t J r -7 to i,1 1 1 i ,/ l / \\ / e t b uCi/cc 1 t i if, ( t / I f i / i l I / / i -9 10 / r i i,. t/ i /.c / r -10 10 l i I l illi,2 I I i 11111 l l l 111111, l l l llill l 3 5 i 10 10 10 to 50 COUNTS / MIN. 3 . NOTE: This. graph assumes.a 20 Ft Air Sample EPP 01-8.3 .',a,,,.Re,v.,,1;, Pa g e .i..Mult'.iply uC1/ce,accordingly. s >. '... ;v . -), ;.,. : .. y.. s ..:,,.~ ,, < j... _.. ' : 3.,.,..i.'.'..,..2, ~.. . ;s'. .~... ...#.~ s.~... ..s s.,,,, .... ~., ? ..- ___..~ ~.-,,.. -.-. _ _u \\

o Or .t ATTACHMENT 6.0 C IODINE SAMPLER CONVERSION GRAPH ~ I I I I IIIi' I I I I IIII1 I I I I I l1l' t i i i / [: j l ,/ I j ll / t / . t r I. . / ,/ iI f 6 / t 6 ! / j is_ f [! uCi/cc ,/ ~ ~ / io-* 1 e .,r s ,t !.v i 4 i /4 i 1/sl / l l'l / + l 7 -7 10 i I I I i 11114 I I I I l i lli.- 1 l l l l ill 2 10 m m m COUNTS / MIN. NOTE: This graph assumes a 20 Ft Air Sample, multiply uCi/cc accordingly. EPP 01-8.3 i - (- ... - ;...n,Rev..Q:.. 1 \\~... .;;; ::. s::...;,y_- .;.v. .... v:.. :' ?. '. .* ;:.~

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c> Le FORM EP 8.2-7 REV 0 .(. .( ATTACHMENT 7.0 FIELD MONITORING TEAM DATA TEAM DESIGNATION: TIME: LOCATION: i w 5 FOOT HEIGHT DOSE RATE: WINDOW OPEN mr/hr. WINDOW CLOSED mr/hr. SILVER ZEOLITE CARTRIDGE COUNT RATE cpm PARTICULATE FILTER COUNT RATE cpm GROSS IODINE ACTIVITY uCi/cc GROSS PARTICULATE ACTIVITY uCi/cc GROUND DEPOSITION uCi/m ~ PERFORM SOIL SAMPLE (Y/N) PERFORM SNOW SAMPLE (Y/N) PERFORM LIQUID SAMPLE (Y/N) ] SAMPLE SHIELDED (Y/N) i TRANSPORT SAMPLES TO EOF (Y/N) SELF READING POCKET DOSIMETER READING mr i RECEIVED BY: i 1 l 4 l i 1 ) l . EPP.01-8.3 r .., a.,,,,. ..,.... c '.. _ Rev f.,1. 3..,,.,...l, .,w

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w FORM EP 8.2-8 REV. 0 l t ATTACHMENT 8.0 FIELD TEAM MESSAGE FORM l i 1 l TIME TEAM (S) I INSTRUCTIONS: o************************************************************************* TIME COMMUNICATED MESSAGE REPEATED BACK YES NO (EOF /TSCFIELDTEAMCOMMUNICATOR REPLY: { I s-_ TIME RECEIVED MESSAGE REPEATED BACK YES NO RETURN TO DAC/ RAS EPP 01.-8. u ; R e v,...'.1.,.. .3 ,3

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