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Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures F3-15 Re Responsibilities of Radiation Survey Teams During Radioactive Airborne Releases & F3,table of Contents
	ML20032B029
Person / Time
Site:	Prairie Island
Issue date:	10/06/1981
From:	Schuelke D; NORTHERN STATES POWER CO.
To:	;
Shared Package
ML20032B023	List: ML20032B022; ML20032B025; ML20032B029;
References
	PROC-811006-05, NUDOCS 8111040305
	Download: ML20032B029 (53)
	v • d • e

{{#Wiki_filter:i e PAGE 1 OF 2 I EMERGENCY PLAN IMPLEMENTING l PRAIRIE ISLAND NUCLEAR PROCEDURES GENERATING PLANT NORTHERN STATES POWER COMPANY Number: TABLE OF CONTENTS Rev: 2 History Copy Reviewed bysff g /] / Retention Time: 5 Years /) d j f / ff. g. _ TITLE: Supt F a'd 'P ro t EMERGENCY PLAN IMPLEMENTING PROCEDURES TABLE OF CONTENTS NUMBER TITLE REV # 1 Onsite Emergency Organization 1 2 Classifications of Emergencies 0 3 Responsibilities During a Notification of Unusual Event 1 4 Responsibilities During an Alert, Site, or General Emergency 1 5 Emergency Notifications 1 6 Activation and Operation of Technical Support Center 0 7 Activation and Operation of Operational Support Center 0 8 Recommer;dations for Of fsite Protective Actionc 0 9 Emergency Evacuation 0 10 Personnel Accountability 1 11 Search and Bescue 1 12 Emergency Exposure Control 0 13 Offsite Dose Calculations 0 14 Orisite Radiological Monitoring 0 15 Responsibilities of the Radiation Survey Teams During a Padioactive Airborne Release 1 I EP-#02-B,28 8111040305 811328 PDR ADOCK 05000282 F PDR

e Table of Contents Page 2 Rev. 2 NUMBER 77 m r.E REV # 16 Responsibilities of the Radiation Survey Teams During a Radioactive Liquid Release 1 17 DELETED 18 Thyroid Indine Blocking Agent (Potassium Iodide) 0 19 Personnel ard Equipment Monitoring and Decontamination 0 20 Manual Determination of Radioactive Release Joncentrations 0 21 Establishment of a Secondary Access Control Point 1 22 Prairie Island Radiation Protection Group Response to a Monticello Emergency 1 23 Emergency Sampling 0 ( 24 Record Keeping During an Emergency 0 25 Re-Entry 1 26 Drills 0 27 Training 0 28 Review and Revision of Emergency Plans 0 29 Emergency Security Procedures 0 O EP-902-B,29

PAGE 1 OF 22 EMERGENCY PLAN IMPLEMENTING S PRAIRIE ISLAND NUCLEAR PROCEDURES GENERATING PLANT NORTHERN STATES POWER COMPANY Number: F3-15 Rev: 1 History Copy Retention Time: 5 Years -n f) g /g Reviewed by:A/.K ArJfulf. TITLE: ' Supt Rhd' Prot' RESPONSIBILITIES OF THE Approved by: / [ b M RADIATION SURVEY TEAMS DURING Plant ~Manajet A RADIOACTIVE AIRBORNE RELEASE OCt: }0-6-9/ 1.9 PURPOSE The purpose-of this instruction is to describe the respon-sibilities of the Radiation Survey Teams during an airborne radioactive release to the offsite environs. 2.0

SUMMARY

Three radiation survey teams exist, each consisting of a minimum of fodr Radiation Protection Specialists. One (1). Had Protection Specialist is required per team (minimum) to perform the required offsite surveys; all other team 'j Os members should report to the Radiological Emergency Coor dinator (REC) onsite, for further assignments (e.g.,onsite sampling, monitoring, analysis, exposure control,etc.). In the event of an offsite airborne release, the Radiolog-cal Emergency Coordinator (REC) may request support for offsite surveys from the Monticello Radiation Protection Group. When the Monticello Radiation _ Protection Group arrives at the Prairie Island Near-site EOF they will accept the responsibility for offsite surveys from the Prairie Island Survey Teams. This allows the Frairie Island personnel, who have completed the initial offsite surveys to augment Radiation survey Team #3 performing onsite surveys. All offsite surveys will continue under the direction of the Emergency Manager at the Prairie Island Near-site EOF. 3.0 APPLICABILITY This Instruction SHALL apply to all members of the Prairie Island Radiation Protection Group. 4.0 PRECAUTIONS AND'SPECIAL CONSIDERATIONS-(1) Each team shall obtain information pertaining to the (es) magnitude and the direction of the release, either from N> the Control Room or the Radiological Emergency Coor-dinator. EP-405-A,1

~ -s -F3-15 -Page 2 Rev. 1 (2) ' Report airborne activity sample results.in round . numbers, i.e., microcuries per ec with no decimal places. (3) Report all radiation levels in whole number mill- ] irems per hour -(i.e.,. Three Rera -per hour. shall be reported as thrae thousand millirem per hour). (4) Report all numbers individually (e.g., one hundred thirty-five shall be reported as one-three-five-and 5 x 10 shall be reported as five times ten to the minus three). (5) Preface each communication with the title or name of-the receiving party and your title or name. For example: " Prairie Island.TSC; Radiation Survey Team 41..." After the communication is completed, request the receiving party to repeat the message, if numerical-data was relayed. End message transmission with an appropriate termina-tion phrase. For. example: " Radiation Survey Team fl, out". i (6) The normal means of transportation.for survey teams during any emergency are NSP vehicles. Extreme environmental conditions (blocked roads, snow, bridges out, etc.) may preclude the use of these vehicles. The following alternate transportation is available: l (a) Power Boats - Sheriff's Department, NSP environ-i mental monitoring team, Red Wing Police. i (b) Four Whoel Drive Vehicle - at Prairie Island l (c) Amphibious Duck - at Prairie Island (d) He? icopter - available during suitable weather conditions from charter service 6 in Minneapolis and St. Paul. Arrange-ments to be made via the corporate l Emergency Organization at the EOF.- (7) The normal communication channel for the survey teams-1 is the portable (scrambled channel) radios' stored in. l (, -) the lockers. Normal telephone system will~ serve as a backup communication system. Telephone numbers in the '/ TSC for the Radiological Emergency Coordinator are: EP-405-A,2 . r

F3-15' .l. { Page 3 .Rev. I t i I (8). Periodically check dosimeter readings and report results to the' REC. 5.0 EQUIPMENT AND PERSONNEL REQUIRED '5;l Team Members Team I ' Team II Team III o I I i o f 1 NOTE: The Radiation Protection Coordina-tors shall assume onsite res,ponsi-bilities as directed by the REC. (- 5.2. Team Equipment Required ~ 5.2.1 Team #1 (1) Vehicle ~ (NSP or personal) (2) Offsite. sample kit (Attachment A) I 5.2.2 Team #2 (1) Vehicle (NSP or personal) (2) Offsite sample kit (Attachment A) i 5.2.3 Team #3 (1) Normal _ counting room equipment, if available (2) Mobile counting trailer t (3) All radiation protection equipment onsite 6.0 PPOCEDURE 6.1 Team #1 6.1.1 All members of Radiation Survey Team #1 SHALL sasemble at the appropriate location as follows. ./ a l k ;. unless directed by the Emergency Director or the Radiological Emergency Coordinator _(REC): I EP-#05-A,3

~F3-15 Prgo;4 Rev. 1 f. (1)- During normal' working hours, all Team _ (..

1 members shall, assemble in the Oper-ational Support Center (OSC).

(2) During off-normal working' hours,-all-Team #1 members shall assemble at the USP' Red Wing Service Center. NOTE: During off. hours the Shift Emergency Communicator (SEC)1shall ensure that NSP-personnel are contacted to open.up the NSP : Red' Wing District Service Center. .If personnel are not available at the service center when Rad Survey teams arrive, at-tempt to call one of the following: i ~C (3) Obtain the necessary information from the Control R n Operator-or TSC_ personnel regataing the type and amount of release, wind direction, etc. (4) Designate two (2j'nembers of Team #1 (if available) to perform offsite surveys. The other members of Team

1 SHALL report to the REC for assignments for onsite sampling, monitoring, analysis, etc.

tioTE: Any plant staff member may be designated as the driver for a single team member. (5) Obtain the necoscary equipment (Attacament A)- from the Emergency Lockers,'as.follows: (a) During normal work hours, proceed to the Training / Construction Building Emergency Locker and obtain the Field Team Survey Kits; ib) During off nor. mal work hours, obtain the Field Team Survey Kits from the NSP Red Wing Service Center Emergency Locker. EP-905-A,4 w...,____________=--.________________-__-_-________-_2

F3-15 Page 5 Rev. 1 (o) V' NOTE: Response check all meters with source prior to departing. (5) Obtain an NSP vehicle or personal vehicle. (6) Survey team members shall keep their personal TLD's if available. (7) Zero and record dosimeter readings on locker signout sheet. (8) Proceed to perform offsite surveys depending on the wind direction and time of emergency: (a) If the wind is from the north or west, proceed on the Emergency Route from the plant, or the NSP Red Wing Service Center, through Red Wing, to Diamond Bluff, to Prescott, to Hastings, and back to the plant as shown on Figure 1. () (b) If the wind is.from the south or east, proceed on the Emergency Route from the plant, or the NSP Red Wing Service Center, to Hastings, to Prescott, to Diamond Bluff, to Red Wing, and back to the plant, as shown on Figure 1. (9) Perform beta and gamma surveys in accordance with applicable procedures, Attachment B, as directed by the Radiological Emergency Coor-dinator. (10) Report results to the Radiological Emergency Coordinator via the portable radio or tele-phone. (11) After completing tae emergency route (Figure

1) report to the REC for further instructions.

(12) When directed by the REC, obtain airborne samples at locations requested by REC as per applicable procedures, Attachment C and D. (13) Report results to the REC via portable radio or telephone. 7-%, C/ EP-#05-A,5-

F3-15 Page 6 Rev. 1 ( 6.2 Team #2 (1) All members of Radiation Survey Team #2 S!!ALL assemble at the appropriate loca-tion as follows, unless directed by the Emergency Director or the Radiological Emergency Coordinator (REC): (a) During normal working hours, all Team #2 members shall assemble in the Operational Support Center (OSC). (b) During off-normal working hours, all Team #2 members shall assemble at the NSP Red Wing Service Center. NOTE: During off hours, the Shift Emergency Communicator (SEC) shall ensure that NSP per-sonnel are contacted to open up the NSP Red Wing District Service Center. If person-nel are not available at the service center when Rad Sur-vey teams arrive attempt to call one of the following: i l (2) Obtain the necessary information from the Control Room Operator or TSC personnel regarding the type and amount of release, wind direction, etc. (3: Eesignate tuo (2) members of Team #2 (if available) perform offsite surveys. The other uemocrs of Team '!2 JUALL report to the F:::C fa. assignment for onsite sampling, c.o a i t.:r l a g, n 11'/31 s, etc,

' 2 '.: :

, id an t staff member may ne ~ .s..- <jesignated as the driver for a single team member. i (4) Obrai.n th9 'wceraary equipment ( At t a ch*".a n t is )

f r:;u the, iae ra-3 ncy Lockers, as rollows:

EP-405-A,6

r F3-15 Page 7 Rev. 1 (-} (a) During normal working hours, proceed '( j to the Training / Construction Building Emergency Locker and obtain the Field Team Survey Ki'.s: ~ (b) During off normal working hours, obtain the Field Team Survey Kite from the NSP Red Wing Service Center Emergency Locker. NOTE: Response check all meters with source prior to departing. (5) Obtain an NSP vehicle or personnel vehicle. (6) S 2rvey Team members shall keep their personnel-TLD's if available. (7) Zero and record dosimeter readings on locker signout sheet. (8) Proceed to the first designated sample loca-tion in the affected sector per instructions frcm the REC. (a) Perform beta and gamma surveys in accord- [ }s ance with applicable procedures, Attach-ment B, as directed by the Radiological Emergency Coordinator. (b) Collect airborne samples, (particulate, iodine and gas), in accordance with applicable procedures, Attachment C and D, as directed by the Radiological Emergency Coordinator. (9) Report results to the REC via the portable r;lio or telephone. (10) Proceed to the next sample location as per inst-ructions from the REC and take requested surveys and samples in accordance with applicable pro-cedures. (11) When directed by the REC, deliver samples to designated location for pickup by member of Team #3. 6.3 Team #3 (1) Report to the Operational Support Center when the emergency is declared, unless directed by the Emer-f"N gency Director or the Radiological Emergency Coor-dinator (REC). EP-#05-A,7

2 F3-15 Page 8 Rev. 1 L,j (2) Perform all operations requested by the Emer-gency Director or REC. (3) Control radiation exposure onsite (internal and externsi). (4) Analyze air samples obtained by the onsite and offsite survey teams, using the Count Room facilities and/or the mobile. trailer. Store all samples for future analysis. (5) Perform'onsite surveys as requested by the Emergency Diractor and/or REC per F3-14 "Onsite Radiological Monitoring". (6) Perform required personnel monitoring at the emergency operating centers and supervise any necessary personnel decontamination per F3-19 " Personnel and Equipment Monitoring and Decon-tamination". (7) Obtain and process samples from the reactor coolant system, containment air, stack re-release,etc., as requested by the REC per F3-21 " Emergency Sampling" and F3-20 ,<-}3 ( " Manual Determination of Release Rates". (8) Report all results to the REC via available communication system. i /s s EP-#05-A,8 l l b

I FIG.URE i ";'5 c9 3I RADIATION SURVEY TEAM ai Rev: 1 yI SURVEY ROUTE p q --- Q l f l l 1 / / / /~ ~s y - - r - I. ~^' s# t / l l 2 I i I to i z l_ _ L J 5 s s ) s__s-j e ( j^ % - s _ E r l a b"%s-Q p I 6 ig* ~/ y 8 Q\\ e\\ o / /

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} (_) O 1 r~'s U M LE ggSULTS Q DATE d t TIME SAMPLE RESULTS DOSE RATE RESULTS - MREM /hr INSTRUMENT 3tc.rt / Survey Sample Sample Sample WINDOW WINDOW TRUE BETA Model 4 Foint Flow Volume Gross BKCD Net pCi/cc Type

Open Closed (See back Serial Stop Rate (ce)

CPM CPM CPM Beta-Camma Gamma for formula) Number-4 4 I U e i w d 4 r "S listed oa back

SanP10 t7Pe includes-Particulate
88e us, Radiolodine* Liquid, Area Done Rate 2-Re 7 TECHNICIAN SIcyg g

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F3-15 Page 11 .Rev: 1 FIGURE 2 (CON'T) Formulas: 1. Gross Counts Per Minute - Background Counts Per Minute = Net' Count Per Minute . CPM.(gross) CPM (bk;d) = CPM (net) 4 2. Cubic feetix~2.83 x 10 = cubic centimeters Ft x 2.83E4 = cc 3. pCi/cc = (CPM (ne t) ) (4. 5E UCi/dpm) (particulate) (inst. eff. (Total sample volume (cfm). x 2.83 x 10}) (CF) (see note 2 & 4) 4. TRUE~ BETA = (WINDOW OPtN READING - WINDOW CLOSED READING) X Beta Correction factor - (see Note 1) NOTES: 1. Assume 5.0 if correction factor is unknown. [-- 2. Instrument efficiency. depends on probes. If using 2" GM pancake probe,.Af,SUME 10% (0.10) efficiency; if using GM tube probe, ASSUME 2% (0.02) efficiency. 3. List factors affecting reading; height of probe, reading inside vehicle, etc. 4. CF (Correction factor for air samples) = 0.3 for a 4 inch filter size paper counted with a 2 .2 inch GM pancake probe I. I i EP-#05-A,9

I F3-15 Page 12 Rev: 1 ATTACHMENT A (_) OFFSITE SURVEY TEAM EQUIPMENT PACKAGE 1. Each offsite survey team shall be equipped with a kit of the following: QUANTITY REQUIRED ITEM 1 Dose rate instrument RO-2 or equivalent 1 Count rate instrument RM-14 or equivalent 2 2" GM pancake probes 1 Battery powered air sampler 2 Personnel self-reading dosimeters (low range) 2 Personnel self-reading dosimeters (high range) 2 TLD's (if individual have a normally assigned TLD they should wear those assigned) 1 (package) Plastic Sample Bags (approx. 100) 1 (box) Garbage bags (approx.10) 1 (package) Paper towcis or handiwipes 2 (roll) Masking tape 20 Silver zeolite cartridges 2 Gas Sample Chambers 1 Filter assembly (gas sampler) 1 Suction bulb (gas sampler) 1 (package) Filter paper (gas sampler) (~T 10 One liter poly bottles (_) 1 Box air sampler filter papers 1 (package) Survey sample labels (approx. 30) 1 Portable radio 1 Flashlight 4 D-Cell batteries 1 Compass 1 Clipboard 2 Pens 1 Pad of paper (8 1/2" x 11" minimum size) 1 Road man cf State of Minnesota 1 Road map of State of Wisconsin 1 Umbrella 1 Watch or clock 1 Procedures binder (see 1 2) 2 (pair) Foul weather (rain) gear 1 Line (approx. 100 feet) 1 Weighted poly bottle holder 2. The Procedur0s Binder shall contain: 1 package of the following maps: (a) Prairie Island Radiological Sampling Points Map and related list of location discriptions (b) Monticello Radiological Sampling Poi.tts Map and related list of location discriptions 7-s i 2 Copy of EPIP 1.1.10, "Offsite Surveys" 10 Emergency Sample Results Forms 1 Cooy of EPIP 1.1.8, " Communications Equipment and Information" EP-#05-A,10

F3-15 ~ Page 13 Rev: 1 ATTACHMENT A (Continued) (~') OFFSITE SUrtVEY TEAM EQUIPMENT PACKAGE \\_/ 1 Copy of F3-15, " Responsibilities of the Radiation Survey Teams During a Radioactive Airborne Release" 1 Copy of F3-16 " Responsibilities of the Radiation Survey Teams During a Radioactive Liquid Release" i (.)"h EP-105-A,11

F3-15 Pcge 14: Rev:-l ATTACHMENT B s-RETA AND GAMMA SURVEY I.~ Precautions '(1) ' Meter shall-have been source response checked prior to use. (2) Checx aatteries by swite':Ing to'. BATTERY CHECK position.' ' Replace if necessary.- (3) Observe the cold weather operation restrictions (ATTACH-MENT E). ~ (4) All surveys shall be taken at approximately one meter from ground level unless specifically directed by the REC. II. Procedure (1) Energize the instrument. (2) Allow meter to stabilize and zero meter if necessary. (3) Switch to the highest scale and scale ~down until a - () onscale reading is-obtained. (4) Hold the' instrument approximately one meter from grouno level-and scan area for maximum reading. i (a) Open probe window for beta-gamma reading and record' on Figure 2 as " Window open" reading. (b) Close the probe window for gamma _ reading and record on Figure 2 as " Window Closed" reading. (5) Determine the beta and gamma dose rates as follows: 1 GAMMA (mrem /hr) = " Window Closed" reading 4 BETA (mrem /hr) = " Window Open" reading minus " Window Closed" reading times CF or (w/o - w/c) CF 4 j Where 1. CF = beta correction factor for meter or assume 5. 2. Beta dose rate reported in mrem /hr a.'suming a quality factor of 1. (6) Record results on Figure 2. (7) Report results to REC. EP-405-A,12

F3-15 Page 15 Rev: 1 ATTACHMENT C (~ '> () PARTICULATE AND IODINE SAMPLING I. PRECAUTIONS 1. The air sampler shall be placed in an area that will ensure a representative sample. DO NOT place the sam-pler on the ground or on contaminated surfaces. 2. Particulate filters and silver zeolite absorbers must be installed and removed carefully to prevent cross-contamination from "oreign objects. 3. The sample should be a standard 25 cubic foot sample. Sample collection time may be affected if the activity is too high. 4. All samples SHALL be labeled properly with the required information and saved for further analysis. II. PROCEDURE 1. Carefully instal: a particulate filter and silver zeo-lite absorber into the cartridge / filter paper holder, n i i ~ NOTE: Install the silver zeolite absorber as fol-lows: INLET liiQ AgZ Flow U Outlet 2. Connect the air sampler to the vehicle power supply as follows: A. CF-18V Air Sampler (1) Connect to 12 Volt battery termiraals. Insure there is a good connection. NOTE: Engine should be running to main-tain a steady battery voltage. (2) Set the TIMER toggle switch to either the TIME cr the MANUAL POSITION.

- 3 f

i \\.) EP-#05-A,13

F3-15 Page 16 Rev: 1 / ~ ' ATTACHMENT C (Cont.) N )s NOTE: (1) If in the TIME position, set the TIMER DIAL to selected time. When the timer times out, the sample pump will automatically stop. (2) If in the MANUAL position, the sample pump must be stopped manually when a designated sampling time has. elapsed. (3) Set the PLOW TOGGLE switch to the VARIABLE pos-- ition. The air sampler will now start. Record start time on Figure 2. NOTE: (1) DO NOT use HIGH cwitch posi-tTon (causes high flow and motor damage). <~S (2) If the sampler begins to run (,,) hot, (flow decreasing contin-uously) stop the air sampler to prevent damage to the unit. (4) Adjust the flow, using the flow adjustment knob to 2 CFM. (5) When the sample collection time is complete, stop the air sampler. Record time on Figure 2. NOTE: If the TIMER was in the TIME pos-ition, the sampler will auto stop when the timer times out. (6) If the TIMER was in the MANUAL position, the air simpler must be stopped manually by placing the FLOW toggle switch to the OFF position when the selected sample time has elapsed. B. Modified Staplex NOTE: To use the modified staplex, the vehicle nust be equipped with a power converter. 7-s I \\ (1) Stop the truck engine and open the hood. Load the air sampler with new filter and silver zeolite absorber. EP-#05,A,14

F3-15

Pcge 17 ~

Rev: 1 ATTACHMENT C (Cont.) (2) Flip the power converter control switch to the " Power Use" position. NOTE: DO NOT change power converter switch while truck.is running. Engine.must be stopped before changina switch position. (3) Start-the engine and raise the engine speed by pulling the manual throttle control out until the red light on the power converter is illum-inated. (4) Plug in the air sampler and start the air sampler. (5) Adjust engine speed as necessary to keep the red light' illuminated. (6) Record the sampler start. time and. flow rate. ~ (7) After about five einutes, record the flow rate and tile and turn the sampler off. (8) Return' engine speed'to normal with manual throttle control. (9) Turn the truck off, close the receptacle dust cover and flip the toggle switch to the " Normal" position. 3. Average the initial sample flow rate and the final flow rate. Calculate the total sample volume and record results on Sample Results Log, Figure 2. 4. Carefully remove the particulats filter and silver zeolite absorber and pit ee in a plasti, sample bag. 5. Place a samplo label on the' sample and ensure that all in-formation is completed. 6 Make gross activity estimatas in the field by the following methods: A. Particulate Activity - count the particulate filter using an RM-14 (or equivalent) with a 2"'GM pancake probe. Estimate ~ the gross pac E latlate activity using the following formula: Activity (pCi/cc) = (Background Corrected Count Rate) (4.5x10 '7pC1/dpm s ) .(Probe Ef ficiency) (Sample Voluma, cc 's)- (CF) -g EP-905-A,15 pp ry --y ym-+ a .-.-7me= w.ww we y---ey%-ny--m-- --,--,,---4g,.my-9., -r

F F3-15 Pcgs 18 Rev: 1 ATTACHMENT C (Cont.) NOTE: (1) Probe ef ficiency =0.1 for RM-14 tiith a 2" GM pancake probe. (2) Place the 2" GM pancake probe about 1/8" from the filter, with filter outside poly bag. CF= Correction factor for sample size is.3 for 4 inch paper counted with a 2 inch probe. B. Iodine Activity - count the silver zeolite absorber using an RM-14 or equiva'.ent. Calculate sample act-ivity using the following formula: Iodine Activity (pCi/cc)= (p Ci's on absorber) (Sample Volume in ce's) NOTE: (1) pCi's on absorber = activity on 6bsorber determined from Fig-ure 3 using the cor-(~N rected count rate. b (2) Place 2" GM pancake probe directly on absorber, with absorber inside poly bag. (3) If background exceeds 1000 cpm, notify the REC and,Joceed to an area of lower background, <1000 cpm for counting, if so instructed by the REC. 7. Record the air sample results on the Sample Results Lor. (Figure 2) and report the results to the Radiological Emergency Coordinator. 8. Save all samples for future analysis. /^\\ \\ %) EP-#05-16

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F3-15 Pega 20 Rev: 1 ('~*) ATTACHMENT D GASEOUS ACTIVITY SAMPLING I. Precautions 1. If hands are contaminated, handle shamber with cotton liners.. II. Procedur_e 1. Remove S.S. Gas chamber, suction bulb and filter ass-embly. 2. Install new filter in filter assembly. 3. Assemble kit so air passes through filter, gas chamber, then suction bulb. 4. Squeeze suction bulb 10 times to obtain representative sample. 5. Shut petcocks on gas chamber. 6. Using an RM-14 or equivalent and a 2 inch GM pancake g-') probe obtain a count rate of the chamber volume by q_ placing the probe over the mylar window. Log the result as " gross CPM". 7. Obtain a second chamber labeled " Background". Do not cpen the stop cocks of the background chamber. Deter-mine a background count rate by placing.the 2 inch GM pancake probe over the mylar window. Log the results as " Background CPM". 8. Determine the " Net CPM" by subtracting the " Background CPM" from the " Gross CPM". 9. UsingFigure4,applythe"NetCPM"yggtainedtodetermine the gross gas-activity in pCi/cc Xe equivalent. 10. Record the air sample results on the Emergency Sample Results Log, (Figure 2) and report the results to the Radiological Emergency Coordinator using the portable radio. 11. Save the sample for future analysis. ('T kl EP-#05-A,17

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F3-15 Pago 22 Rev: 7 ATTACHMENT E ["J 's COLD WEATHER OPERATION 1. If outside temperature is greater than 32 F (O C), instru-ment use is unlimited. 2. If outside temperture is between 32 F IO C) and 0 F (-18 C), no instrument should be used for more than 5 minutes. 0 3. If outside temperature is between 0 F (-18 C) and -20 F (-28 C), no instrument should be used for more than 2 minutes. 4. If the outside temperature is below -20 F (-28 C), no instru-ment should be used unless special batteries (alkaline or Ni-CD) are in instrugent and this would increase the temperature range to -40 F (-40 C). The instrument should only be used for g very short times (less than 30 seconds). ,-m ~. ws# EP-405-A,18

5 ? PAGE 1 OP 16 's EMERGENCY PLAN IMPLEMENTING PRAIRIE ISLAND NUCLEAR PROCEDURES GENERATING PLANT NORTHERN STATES POWER COMPANY Number: F3-16' Rev: 1 1 History Copy Retention Time: 5 Years Reviewed by:f) g I / A/,ff.M rik TITLE: Supt Rad Prot Approved by: RESPONSIBILITIES OF THE Mh,mM RADIATION SURVEY TEAMS DURING Plant Managjf ' ~ A RADIOACTIVE LIQUID RELEASE OCt: lO- $ - V/ l.0 PURPOSE The purpose of this Instruction is to describe the responsibilities of the Radiation Survey Teams during a liquid radioactive release to the offsite environment. i 2.0

SUMMARY

Three radiation survey teams exist, each consisting of a minimum of four Radiation Protection Specialists. O One Radiation Protection Specialist is required per j team (minimum) to perform the required offsite sampling; all other personnel should report to the Radiological Emergency Coordinator (REC) onsite, for further assign-ments and/or instructions for onsite sampling, monitor-ing, analysis, exposure control, etc. t In the event of an offsite liquid release, the Radio-logical Emergency Coordinator may request support for l offsite sampling from the Monticello Radiation Protection Group. When the Monticello Radiation Protection Group arrives at the Prairie Island Near-Site EOF, they will i accept the responsibility for offsite sampling from the i Prairie Island Survey Teams. This allows the Prairie l Island personnel, who have completed the initial offsite j sampling to augment the onsite Radiation Survey Team. All offsite monitoring will continue the direction of the Emergency manager at the Prairie Island Near-Site EOP. i 3.0 APPLICABILITY This Instruction SHALL apply to all members of the Prairie i Island Padiation Protection Group. O I EP-#21-A,1

e F3-16 Rev. 1-Page 2 ( 4.0 PRECAUTIONS AND SPECIAL' CONSIDERATIONS (1) Nachteam.shallobtaininformatJonpertainingtothe magnitude of the liquid release, either from the Control Room Operator or the Radiological Emergency Coordinator (REC). (2) Report all liquid sample results to.the REC in round' numbers, (e.l., with no decimal places) micorocuries per milliliters. (3) Report all numbers individually (e.g. one hundred thirty _{ive shall be reported as one-three-five and 5 x 10 shall be reported as five times ten to the minus three). (4) Preface each communication with the title or name of the receiving party and then your title or name. For example: " Prairie Island TSC; Radiation Survey Team

1...".

After the communication is complete, request the receiving party to repeat the message, if numerical data was relayed. () End message transmission with an appropriate termi-nation phrase. For example: " Radiation Survey Team fl, out." (5) The normal means of transporation for survey teams during any emergency are NSP vehicles. Extreme 7nvironmental conditions (blocked roads, snow, bridges out, etc.) i may preclude the use of these vehicles. The following-alternate transportation is available. NOTE: This does noE prohibit the use of per-sonal vehicles in esses where NSP vehicles are not available in suffici-cient numbers. (1) Power Boats - Sheriff's Department, NSP environmental moni t'*inq team, Red Wing Police (2) Four Wheel Drive vehicle - at Prairie Island (3) Amphibious Duck - at Prairie Island O' -Helicopter - Avsilable during suitable weather (4) conditions from charter services in Minneapolis and St. Paul. Arrangements to be made via the Corporate Emergency organization at the EOF. EP-621-A,2

I F3-16 Rev. 1 Page 3 ( 4.0 PRECAUTIONS AND SPECIAL CONSIDERATIONS (CON 'T) 6. The normal means of communication for the survey teams is the portable (scrambled channel) ' radios stored in the lockers. The normal telephone sys-tem will serve as a backup communication system. Telephone numbers in the TSC for the Radiological Emergency Corrdinator (REC) are: 5.0 EQUIPMENT AND PERSONNEL REQUIRED 5.1 Team Members Team I Team II Team III m NOTE: Rad Protection Coordinators shall assume on-site responsibilities as directed by the Radiological Emergency Coordinator (REC). 1 5.2 Team Equipment Required 5.2.1 Team #1 (1) Two vehicles (NSP or personal) (2) Offsite sample kit (Attachment A) 5.2.2 Team #2 (1) Two vehicles (NSP or personal) (2) Offsite sample kit (Attachmnet A) 5.2.3 Team 43 (1) Normal counting room equipment, if avail- {- able (2) Mobile counting trailer (3) All radiation protection equipment onsite-EP-#21-A,3 l'

-1 c, F3-16 Rev. 1 Page 4 6.0 Procedure 6'.1., Team #1 2 . (1) All members of Radiation Survey Team #1 SHALL ^ assemble at the appropriate location as follows, ,unless directed the Emergency Director or the /RaGiologicalEmergency-Coord'uator (REC): e J. t L (a), During normal working hours, all Team #1 [ members shall. assemble in the Operational 1 Support Center (OSC). 4 2 [4 /(o) During off-normal working hours, all Team #1 , r.nembers shall n' semble at the NSP. Red Wing s _ Service Center. ? NOTFt During off hours, the Shift 7 Emnrgency Communicator (SEC) i ~ } shall ensure that NSP person-al are. contacted to.open up ' o, c p," the NSP Red Wing Service Cen-ter. 1f personnel are not 3 available at the service cen- '( r I (~ ter when Rad Survey Team mem- . /,!, bers arrive, attempt to-call

+

one of the following: S r ? e 4 l 's f>(2)- Obtain the necessary information from.the e

Control' Ro,om Operator or TSC personnel re-garding the5cype and amount of release, etc.

IS d (3) Desiha, ate two (2) members of Team #1 (if i L avail able) to perform offsite sampling. The otherime.mbers of Team #1 SHALL report ' 'ha'the Radiological, Emergency Coordinator i for assigt.ments for'onsite sampling, monittrirg,{ge.alysis,etc.

g

'F i NOTE: Any plant; staff member may be designated as the driver -i for a single team member. ' C ~ ' '.. x t [.,, EP-#21-A,4 j 'Q. \\( '/ a

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~ F3-16 t r Rev. 1 Page 5 v(~h ' (4) -Obtain vehicle,.and a second vehicle'(if ~ necessary) for _ transporting' samples back to -the plant or designated location for analysis. ?S) Obtain.the necessary' equipment-(AttachmentcA) " ~~

from the-NSP Red Wing District Service Center:

Emergency' Locker. NOTE: Response check all meters with source prior to-de-1 parting. vm J (6) Proceed to Eisenhower Bridge and obtain.a - 3 one liter. sample from middle of.the Minne- -3 ~ sota channel, and then one liter sample from the middle of'the Wisconsin ~ channel in. accordance with Attachment B. _Obtain liquid samples at thirty minute intervals or as di.rected by the REC. ~ ~ NOTE 1: If rivermis frozen and unable: to sample river; contact the: Radio-(f logical Emergency Coordinator for 97 ~ further instructions. f* NOTE 2: Traffic control assistan'ce on the 'e Eisenhower Bridge can be ob-r taineo from the Fed Wing doJice if-necessary. (7) Report all results to the Radiological Emergency + Coordinator via the portable radio or telephone. (8) Label bottles correctly for-further analysis and stofage at the plant site. ~ (9); One-team member shall continue the sampling schedule while the other member transports the samples to the location designated by-REC <+ f, - for analysis by Team #3. Additional bottles may also be obtained at this location. (10) Continue sampling _until. directed by the Radio-- logi.21 Emergency Coordinator. Ci?" j. 6.1.2 Team is f a j#. ~., -(l) All members of Radiation Survey Team #2 SHALL assemble at the appropriate location as tollows, y unless directed the Emergency Director'or the - e' if _ _ Radiological Emergency Coordinator (REC): k'y ~ ;$P-921-A,5

hy '

~ __/ ^ _s> y.

i

' 2 '" J _._____ _ _ _ _ _ _. _ _ _ _ _ _. _ _ _. _ _ _ _ _ _. _ _ _. _

F3-16 Rev. 1 Page 6 4 \\ 'U. During normal working hours, all-(a) Team #1 members shall assemble-in the Operational Support Center! (OSC).. (b) During-off-normal working hours, all Team #2 members shall assemble at the Training /ConstructionLBuild-ing. (2) Obtain tne necessary_information from'the Control Room Operator or'TSO personnel regarding the type and amount of_ release, etc. (3) Designate two (2) members.of Team #2-(if. l available) to perform offsite sampling. l The other members of Team #1:SHALL report to the Radiological-Emergency Coordinator for assignments-for onsite sampling, mon- ~ j itoring, analysis, etc. -es NOTE: Any plant staff member may _ '( ) be designated as the driver for a single team member. (4) Obtain a vehicle for' sampling, and a second vehicle (if necessary) for transport of samples. (5) Obtain the'necessary equipment (Attach-ment A) from the Training / Construction Building Emergency Locker. NOTE: Response check all meters with prior to departing. (6) Proceed to outfall canal or point of dis-charge and obtain one liter samples of water flowing from the nlant in accordance with Attachment B. (7) Proceed to the-intake canal barrier and obtain a one liter sample on the upstream side of the barrier for background acti-vity determination as per Attachment B. (8) Report all results to Radiological Emerg-ency Coordinator via portable radio or telephone. EP-#21-A,6

r F3-16 Rev. 1 Page 7 ((~/ (9) _ Deliver samples to designated locheion for pickup by member of Team #3. (10) Proceed to Lock & Dam #3. (11) Obtain a one liter sample every 15 minutes from the roller gate area in accord-ce with Attachment B. (12) Report all results to Radiological Emerg-ency Coordinator via portable radio or telephone. (13) Label all sample bottles properly for further analysis and storage by Team #3. (14) When directed by REC, one tean member shall deliver samples to designated location for pickup by member of Team #3 and a new supply of sample bottles may be obtained at this location. (17) Continue sampling until directed by the Radiological Emergency Coordinator. f-~ 5 (18) Additional samples may be required at the discharge canal. If possible, spare team #3 members can obtain these samples and allow Team #2 to stay at Lock and Dam #3. 6.3 Team #3 (1) Report to the Operational Support Center unless otherwise directed by the Emergency Director or the Radiological Emergency Coordinator. (2) One member should be designated as a runner to pickup all samples at the designated loca-tion from Team #1 and Team #2. (3) Assist plant operations in minimizing and con-trolling the release. (4) Analyze samples obtained by Teams 1 and 2 or-as required by the Radiological Emergency Coordinator. (5) All results shall be reported to the Radiological Emergency Coordinator. ( ) \\~/ (6) Store all sample bottles for further analysis. EP-#21-A,7

C?' ?O a T?w ta E?. w R eso T D NE l l r a M e ae e U d ib r R o rm A T M eu S SN N d I iuq i L )a E l e R r Aku n U h Tcm i T / Ear d A M Bbo o N E f i G R Ee o I m Uer i S RS o d T(f a N R A S I T C E L Wd s I T U O ea u N A S Dsm o H D E Nom e C R Il a s E WCG a T E G TA a R m e G m t O E W a a L S OnG l O De-u S D Npa c T IOt i L W e t U B r S a E P R e* i l e E pp L my s P aT e M S d A u S l c c Y c n C / i N i E C e G p p R y E t M tM E eP e NC lp m S D a T CM S 1 KP L BC SER ssM E aP L rC P G M A S ee l m) puc ml c ao( SV k e c l we a pot b ml a aPR n S o d y e et t ) vn s ri i uo l SP s: as / p lk o ur E t ma I rm S D / oe T t FR r / l a t 12 3 ill ll I

F3-16 Rev. l-Page 9' .O FIGURE l' (Con't) FORMULAS: 1.- Gross Counts Per Minute - Background Counts Per Minute = Net Count Per Minute CPM (net) CPM (grcss) - CPM (bkgd) = 4 2. Cubic feet x 2.83 x 10 = cubicfcentimeters Ft x 2.83E4= cc 3. p Ci/cc - _(CPM (net)

4. 5E-7d Ci/dp.n)

(cfm) ef f.g ((Total sample volume particulates (inst. CF) (see note 2_& 4) x 2.83 x 10 . 4. TRUE BETA = (WINDOW OPEN READING - WINDOW. CLOSED READING) X Beta Correction factor - (see Note 1) 4 NOTES: 1. Assume 5.0 if correction factor is unknown. '. O 2.- Instrument efficiency depends on probes.' If using 2" GM-pancake probe, ASSUME 10% (0.10) efficiency; if using GM' tube probe, ASSUME 2% (0.02) efficiency. l 3. List factors affecting reading; heights of probe, reading inside vehicle, etc. 2-C.3 for a 4 it :h 4. CF (Correction factor for air samples) = filter size paper i counted with a 2 inch GM pancake probe. t t lO i EP-421-A,8 i I d e-4 w ee s:v + -w, ~,g-wsv y ,,,,,y--, 7 r, ,g ,,wr -r,7, - - ,-,,--,-,ne---ew v----s-r-~ r ,-e.rn,w a w

r F3-16 Reve 1 Page 10 ATTACHMENT A ,-~ k[)- OFFSITE SURVEY' TEAM EQUIPMENT PACKAGE' s 1. Each offsite survey team shall be equipped with a kit of the following: QUANTITY REQUIRED ITEM e 1-Dose rate instrument RO-2.or equivalent 1 Count rate instrument RM-14 or equivalent 2 2" GM pancake probes-1 Battery powered air sampler 2 Personnel self-reading dosimeters (low range) 2 Personnel self-reading dosimeters (high range) 2 TLD's (if individual have a normally assigned ~ TLD they should wear those assigned) l-(package) Plastic Sample Bags (approx. 100) 1 (box) Garbage bags (approx.10) 1 (package)- Paper towels or handiwipes 2 (roll) Masking tape 20 Silver zeolite cartridges 2 Gas Sample Chambers 1-Filter assembly (gas sampler) 1 Suction bulb (gas sampler) 1 (package) Filter paper- (gas sampler) s 10 One liter poly bottles ~ ) 1 Box air sampler filter papers 1 (package) Survey sample labels (approx. 30) 1 Portable radio 1 Flashlight 4 D-Cell batteries 1 . Compass 1 Clipboard 2 Pens 1 Pad of paper (8 1/2" x 11" minimum size) 1 Road map of State of Minnesota 1 Road map of State of Wisconsin 1 Ombrella 1 Watch or clock 1 Procedures binder (see # 2) 2 (pair) Foul weather ' rain) gear 1 Line (approx.100 feet) 1 Weighted poly bottle holder 5 2. The Procedures Binder shall contain: 1 package of the following maps: (a) Prairie Island Radiological Sampling Points Map and related list of location discriptions (b) Monticello Radiological Sampling Points Map and related list of location discriptions O~' 1 Copy of EPIP 1.1.10,'"Of Lite Surveys" 10 Emergency Sample Results Forms 1 Copy of EPIP 1.1.8, " Communications Equipment and Information" EP-421-A,9

F3 Reva 1 Page ll ATTACHMENT A- (Continued) OFFSITE SURVEY TEAM EQUIPMENT PACKAGE 1 Copy of F3-15, " Responsibilities of the Radiation Survey Teams During a-Radioactive. Airborne Release" 1 Copy of F3-16," Responsibilities of the Radiation Survey Teams During a Radioactive-Liquid Release" !O I 1 l i i i 1 1 r I: i EP-#21-A,10

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r ~ ~ FJ-10 Riva l' Ptga'12~ 6 ATTAsHMENT B [ N /- LIQUID SAMPLING I. Precautions 1. Always collect-full one liter bottles.- 2. For samples at the outfall or point of discharge,- assume that the bottle, weighted sampler and rope could possibly become slightly contaminated. Surgeons gloves should be worn at this sample point-and bottles should be placed in plastic bag. 3. Observe cold weather operation-instructions (At-tachment C). 4. Estimation of gross liquid activity must be made with probe in position shown on applicable calibration-curves. 2 5. All meter readings shall be corrected count rates (subtract background). II. Procedure 1. Obtain a one liter poly sample bottle of liquid {^)T-from the desired sample location. x, NOTE: Place poly bottle in sample-rig in such a position that it will not float out. 2. Throw the weighted sampler into an area of water which will supply a representative sample. 3. Collect a FULL one liter sample of liquid. i 4. Withdraw the weighted sampler and cap the sample bottle. NOTE: Observe precautions as sampler may be contaminated. 4 5. Label bottle properly. 6. Estimate the gross liquid activity by the following methods: t (a) RM-14 or equivalent with 2" GM Pancake f position the probe at midpoint on the one liter sample bottle as shown on Figure 2. Using the ^~' corrected count rate obtained on the instrument, the estimated gross activity in pCi/ml can be l EP-#21-A,11 obtained from Figure 2.

F3 1 i, Ravt 1 Page 13 ATTACHMENT B (CON 'T) + (b) _E120 with HP-177C Probe - position the probe '(shield open) 'in a vertical position, centered ~on the bottle, as shown in Figure 3. Using the corrected count rate obtained on the E120,.the estimated gross activity in UCi/ml can be obtained from Figure 3. -7. Report results on Sample Results Log,-Figure l'.- t h 8. Report results to'the Radiological Emergency Coordinator (REC). 8. All samples SHALL be saved for further analysis, using either the Count Room or mobile trailer equipment. i i )

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F3-16 / Rev: 1 Page'16 -p) ( ATTACHMENT C COLD WEATHER OPERATION 1. If outside temperature is greater than 32 F (O C),. instru- ~ ment use is unlimited. 2. If outside temperture _ is between 32 F_ - (O C) and 0 F (-18 C), ~ U no instrument should be used for more-than 5 minutes. 0 3. If outside temperature is between 0 F -(-18 C) and -20 P ' (-28 C), _ no instrument should be used for more than 2 minutes. 4. If-the outside temperature is below -20 F (-28 C),- no instr'u-ment should be used unless special batteries (alkaline or Ni-CD) are in instrugent and this would increase the temperature range g to -40 F (-40 C). The instrument should only'be used for very short times (less than 30 seconds). O O EP-#21-A,13

I .i I PAGE 1 OF 4 EMERGENCY PLAN IMPLEMUNTING g-m, PRAIRIE ISLAND NUCLEAR PROCEDURES ( ,1 GENERATING PLANT NORTHERN, STATES POWER COMPANY Number: F3-21 Rev: 1 History Copy n. a Retention Time: 5 Years /.//// TITLE: Supt' Rad Prot Approved by: ESTABLISHMENT OF A SECONDARY mat %I ACCESS CONTROL POINT ' Plant Manag/ ~ r' /D - g - Y OCt: 1.0 PURPOSE During an emergency condition, a secondary Access Control point (established in the Guard House or at a designated area further from the plant) for exposure control purpose may become necessary, due to: (a) Evacuation of the normal Access Control point.due to high radiation levels, high contamination levels, and/or high radioactive airborne levels. OR (b) Abnormal radiation levels, contamination levels, f) and/or high airborne problems throughout the plant A' site in non-controlled areas. This instruction shall establish the procedure to establish a secondary access control point ensuriung that.all personnel are properly badged with TLD badges and dos-imeters when the normal Access Control point has been evacuated. 2.0 APPLICABILITY This instruction shall apply to all plant personnel. 3.0 FRECAUTIONS (1) All exposute shall be recorded properly ensuring that it is recorded on the individual's record. (2) Any individual approauhing the administrative limits shall be reported to the Radiological Emergency Coordinator (REC). (3) All personnel shall have completed and have signed a i Form 4 prior to Untry into the plant's controlled area which could result in exposure exceeding 300 millirem. EP-f217-B,1

F3-21 Pcg:S 2 Rev. 1 y 4.0 PROCEDURE f ~' 4.1 The Radiation Survey Teams shall continuously monitor the radiation levels and airborne levels throughout the plant as the emergency progresses. 4.2 All survey results shall be reported and/or routed to the Radiological Emergency Coordinator for review. 4.3 When recommended by the Radiological Emergency Coord-inator, the Emergency Director shall direct the establishment of a secondary Access Control point at the Guard House (or at a designated area further from the plant) when: (a) Access Control has been lost due to high radiation levels, high contamination levels, and/or high airborne activity levels. OR (b) High radiation levels contamination levels and/or high airborne activity levels exist throughout the plant in non-controlled areas. 4.4 If time and radiation conditions allow, transfer all TLD badges, dosimeters (low and high range), dosimeter chargers, TLD issue forms, exposure forms and entry ,s (' ') cards from the normal Access Control point to the designated Secondary Access Control Point. If not, transfer the Secondary Access Control Point Supplies from the Training Building Emergency Locker (Figure 1). 4.5 Radiation Protection Group personnel shall maintain exposure control at the Secondary Access Control Point on a continuous basis (twenty-four hours per day) 4.6 Request assistance from the Security Force in establish-ing and maintaining the Secondary Access Control Point. 4.7 Issuance of TLD's and dosimeters shall be in accordance with Radiation Protection Group SWI's and Section F-2 Operations Manual. NOTES: (a) With the possibility of high radiation areas existing, all personnel shall complete an exposure history, NRC Form 4, prior to entry into a Controlled Area, which could result in exposure exceeding 300 millirem. (\\_) (b) The type of dosimetry issued will be determined by initial survey results and/or expected radiation levels. EP-#21-B,2 m

F3-21 Page 3 Rev. 1 ! )/ (- I 4.,8 Entry cards shall be issued and all exposure shall be recorded on the individual's card. 4.9 The Radiation Protection Group shall periodically obtain a current exposure summary. Any' exposure at or near the administrative limits shall be reported to the Radiological Emergency Coordinator. 4.10 The Secondary Access Control Point shall remain at the Guard House or at the designated area further away from the plant until, as otherwise directed, by the Radiological Emergency Coordinator and/or the Emergency Director. /^) C/ l l l l [ p EP-#21-B,3 l

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~ FIGURE l' Secondary Access Control Point Equipment-(1)- 100:TLD's i (2), 100 0-SR Dosimeters (3) - 50 0-lR Dosimeters ~~(4) 100 0-200mr' Dosimeters (5). Dosimeter charger / spare battery (6) TLD issue' forms (7) NRC Form 4 & 5 's (8) Monticello & Prairie ~ Island Exposure Log Book (9): Pens t (10) RWP's (11) Access Control Cards (12) Laundry marker (13) Marking pen-(fine point) I i. l i r e t i f-i. EP-#21-B,4 L. I i-' _.-,-----~.....,-,_.,-,a-_,_____..-_,__,-..._.__._.._._____-___.________

P; s i PAGE l'OF 9 j EMERGENCY PLAN. IMPLEMENTING PRAIRIE ISLAND NUCLEAR PROCEDURES --()- GENERATING PLANT-NORTHERN STATES POWER COMPANY ' Number: F3-25~ Rev: 1 History Copy Retention-Time: 5 Years Reviewed by: ) N, TITLE: ~ ~ Sept Rad Prot Approved by: RE-ENTRY Plant Man ef ' ~ OCt: /f)-fo ~ l 1.0 PURPOSE This procedure provides instructions and guidelines for re-entry into areas of the plar.t or -plant - site, where radiological ani/or environmental conditions:are'largely' unknown. The re-entry has oeen preceded by: (1) An evacuation of the plant or affected areas of the plant. and (2)- The magnitude and/or nature of the radiological hazards in the affected~ areas are not fully.known'. 2.0 PRECAUTIONS Because of the unknown or expected conditions within the affected areas: (1) Re-entry teams shall be composed of a minimum of two individuals. Maximum number sLall be determined-by the volume of work assigned to the re-entry team. The team members shall remain in visual / voice contact with each other at all times when in the affected areas. I (2) If there is reason to believe that the air-within the area is toxic or an oxygen deficiency exists, the team members shall use self contained breath-ing apparatus which then limits the time avail-l: able to the team. In this case, in addition to the original team, two or more individuals shall be assigned outside of the affected area in standby /"'y (fully clothed and wearing SCBA) ready to enter T,/. the area if necessary. s EP-#21-A,20 L

y F3 Rev. 1 's Paga 2 k. (3) Lifelines shall be used'in areas containing heavy smoke or in areas where visual contact between team members is impossible or hampered. (4' The Re-Sotry team shall have radiation dose rate indicating equipment'when radiological conditions are unknown. (5) One team member shall be designated as the Team Leader. (6) Radiation exposure for the re-entry team personnel shall be controlled by the Radiation Protection Group in accordance with F3-12, " Emergency Exposure Control". (7) All entries into areas of high radiation areas (>10R/hr general area) shall be made with two dose rate meters. 3.0 APPLICABILITY This procedure is applicable to all individuals directinge assisting, or assigned to a re-entry team. -,s

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4.0 PROCEDURE The Emergency Director shall utilize all pertinent data available including area and process radiation monitor-ing channels, survey data, visual observations, observa-tions made by previous re-entry teams and ar.y other source of information applicable to: (A) Which plant areas are affected. (B) Conditions in affected areas (hazards, radiological, temperature, etc.). (C) Actions which can be taken to reduce the potential hazards to the re-entry team prior to or during the re-entry. 4.1 The Emergency Director shall assemble the appropriate re-entry team (s). NOTE: If excessive radiation exposures are expected or possible, the teams shall be composed of volunteers. It is highly recommended that one (; team member should be a Radiation Protection \\' Group member or an individual with extensive training in radiation protection practices. EP-#21-A,21

F3-25 Rev. 1 ,() Page 3 \\. J' 4.2 The Radioligical Emergency Coordinator shall ensure that preparation for the re-entry teams (s) are complete, i.e., personnel are properly clothed, badged, respiratory protection is issued and exposure is controlled in accord-ance with F3-12 " Emergency Exposure Control". NOTE: Dose rates for areas of the plant projected for the worst case accident assuming major safety system failure and significant core dam ag e, are shown in Figures A-1 thru A-10 and B-1 thru B-10. 4.3 The re-entry team shall carry portable communication gear allowing continuous evntact with the Emergency Director and/or Radiological Emergency Coordinator. 4.4 The re-entry team shall continuously observe the portable radiation instrument while approaching the affected area. NOTE: If at any time the survey instrument appears to malfunction, immediately return to a safe area and contact the Emergency Director / REC. (' 3I 4.5 Maintain a continuous dialogue between the re-entry team and the Emergency Director concerning observed dose rates and conditions observed. 4.6 When requerted or periodically, the re-entry team shall read and report dosimeter readings. 4.7 If at anytime during the re-entry, observed dose rates exceed a predetermined level or if the ex-posure of team members approaches a predetermined amount, the Team Leader shall return the team to a safe area. 4.8 If exposure or dose rates are acceptable, the re-entry team should complete the functions assigned to it (e.g. surveys, inspections, repairs, valve opera-tions, etc.). 4.9 The Team Leader, upon completion of work, shall direct the team from the area to a safe area (con-trol point). 4.10 The Radiation Protection Group shall assist the team members at the control point assuring an accurate [~') dose assessment and proper removal of protective K/ clothing and respiratory protection equipment. EP-#21-A,22

F3-25 Rey, 1 Page 4 4 4.11 The Radiation Protection Group shall complete the dose assessment for team members in accordance with F3-12, " Emergency Exposure Control". 4.12 The Radiological Emergency Coordinator shall insure that all follow up actions are completed.

O EP-#21-A,23

F3-25 Rev. 1 ('~l Page 5 \\-,) / ATTACHMENT A DOSE RATE CALCULATION DESCRIPTION Floor plans have been developed to show the Design Basis Accident dose rates throughout the plant. The Design Basis Accident dose rates are a result of safety system failure leading to major core damage with release to the containment atmosphere of 100% of the core noble gar inventory, 50% of the core equilibrium Radiciodine inventory and 1% of all others. In all cases, the accident has been assumed to be instantaneous, and the release of the fission products from the core has occurred at time T = 0. The fission products are assumed to be uniformly mixed within the containment atmosphere. Dose rates from the containment structure itself have been included in the dose rates to the vital and general areas of the plant. Dose rates in the Auxiliary Building have been calculated. These calculations take credit for the floors and walls within the Auxiliary Building. Large shield penetrations have also been analyzed. The penetrations that have been analyzed include ventilation penetrations on the 755' level, and the Main Steam penetrations on the 715' level. Where appropriate, values shown 73 ) include the sum of the dose rates from containment itself and from \\~' the shield wall portals. Feedwater penetration: were assumed to be filled with water, resulting in no portal effect. Two floor plans for the 695 ' level are shown. One shows the dose rates at T = 0 assuming the recirculation mode is not in use. Dose rates en this floor plan are from the containment and the CVCS lines. The other floor plan of 695 ' level shows the dose rates at T = 0 assuming recirculation mode is in use. Dose rates shown here are the totals from the containment, CVCS lines, RHR, SI, and CS lines. The dose rates from the CVCS have been calcula-ted assuming Letdown was isolated after a gap activity release accident. Dose rates in the plant from the RHR, SI and CS Systems have been eclculated assuming 100% of the core equilibrium radio-active Noble Gas inventory and 50% of the core equilibrium radio-active Halogen inventory have been diluted into the combined volume of the Reactor Coolant System and the Refueling Water Storage Tank (RWST). This assumes that the water in the RWST has been injected and that the RHR recirculation mode is in use. These dose rate calculations are conservative because they are based on a T = 0 hours ac'.ivity and no degassing of the recircula-tion water by the blowdown into containment. In reality, it would take at least 15 minutes before alignment of the recirculation mode would commence and the noble gases would be stripped when the liquid depressurizes. ( \\ \\_/ Floor plans of the 715 ' and 735 ' levels are at T = 0 assuming the RHR recirculation mode is in progress. EP-#21-B,24

F3-25 Rev. 1-fs Page 6 .!--) ATTACHMENT A DOSE RATE CALCULATION DESCRIPTION Dose rates at T = 0 are shown for the 755 ' level. These dose rates are from the containment and include the shield wall portals. Dose rates on 755 ' level at T = 1/2 hour are also shown. These dose rates are from the containment:and the Shield Building Vent System (SBVS) and Aux. BuildingSpecial Vent : System (ABSVS) filters. Dose rates from the filters peak at approximately 1/2 hour after-the event due to the build-up on the charcoal beds. The design-criteria leakage of.25 w/o per day from the containment vessel to the shield building was used as the basis of the SBVS filter isotope build-up. The effect of Containment Spray has been included in the analysis. Dose rates from the ABSVS were also-calculated. These dose rates are based on the RHR pump seal failure tin combination with the design criteria of.1 w/o per day leakage which by-passes the SBVS and is. deposited on the ABSVS filters. This is conservative because if the.1.w/o is deposited _ on the ABSVS filters only. 15% w/o would.be deposited on the SBVS filters. It has been-assumed that.25 w/o is deposited on the-SBVS filters and.1 w/o is deposited on the ABSVS tilters. In addition, the RHR seal failure has also been included-as a source of build-up on the ABSVS filters. Dose rates at times later than T = 0 for all levels except 755' i may be determined using Dose Rate vs Time Curves and the following formula: %D.R. Dt = 100-Do Where Dt = Dose rate at some time, t %D.R. = Percentage of T = 0 Dose Rate from Dose Rate vs Time Curves (Fig. 1 or 2) Do = Dose-rate at T = 0 s./ EP-#21-B,25 3 --w.- _v

rern c = l ~a F3-25 Rev. 1 Page 7. FLOOR ~ PLAN INDEX ' Set A Set B Dwg No.- Dwg No. Floor Plan A-1 B-1 695' Aux Bldg-No. Recire. A-2 B-2 695 ' Turb Bldg No Recirc. A r;-3 695' Aux Bldg.Recirc. In A-4 B-4 695 ' Turb - Bldg. Recirc. - In A-5 B-5 ' 715 Aux Bldg. Recirc. In A-6 .B-6 715 ' Turb Bldg Recirc. In A-7 B-7 735 ' ' Aux Bldg Recirc. In A-8 B.735 ' Turb L Bldg Recirc. In - A-9 B-9 755 ' Aux Bldg.T = 0 'Recirc In i j A-10 B-10 755 ' Aux ~ Bldg T. = 1/2 ' hr. 4 Recirc. In f 4 i l Set A' Unit.1 AFFECTED DBA i Set B Unit 2 AFFECTED DBA 1 j 7 EP-#21-B,26-i.

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