ML20077E004
| ML20077E004 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 06/21/1983 |
| From: | WISCONSIN PUBLIC SERVICE CORP. |
| To: | |
| Shared Package | |
| ML111671195 | List: |
| References | |
| PROC-830621-01, NUDOCS 8307270506 | |
| Download: ML20077E004 (78) | |
Text
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Page.1 of 5 REVISED 6-21-83 EMERGENCY PLAN IMPLEMENTING PROCEDURES
}.
-index-Procecure #
TITLE REVISION DATE EP-AD-1 Plant Emergency Organization D
03-10-83 E?-AD-2 Emergency Class Detemination C
03-10-83 EP-AD-3 Unusual Event -
B 03-10-83 EP-AD-4 Alert B
03-10-83
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EP-AD-5 Site Emergency B
03-10-83 EPL-AD-6 General Emergency B
03-10-83 EP-AD-7
, Notification of Unusual Event F
03-10-32 EP- & 8 Notification, of Alert F
03-10-83 EP-AD-9 Notification of Site Emergency F
03-10-83 s
EP-AD-10 Notification of General Emrgency F
03-10-83 EP-AD-11 Emergency Radiation Controls C
06-21-83 EP-AD-12 Personnel Assenbly and Accountability D
03-13-83 EP-AD-13 Personnel Evacuation 03-03-83
\\
EP-AD-13A Limited Area Evacuation DELETED 03-1-83 EP-AD-13B Emergency Assembly / Evacuation DELETED 03-1-83 EP-AD-13C Site Evacuation DELETED 03-1-83 EP-AD-14 Search and Rescue A
03-10-83 4
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EP-AD-15~
Recovery Planning A
03-10-83 l
l EP-AD-16 0ccupational Injuries o'r Vehicle Accidents A
03-10-83 During Emergencies i
{
EP-AD-17 Communications D
03-10-83 EP-AD-18 Availability of Inorganic Iodine Salts for A
03-10-83 Iodine Saturation of the Human Thyroid Gland 0
EP-EW-1 Environnental Monitoring Team Organization B
03-10-83 EP-ENV-2 Site Access Facility (SAF) Activation B
03-10-83
-t 8307270506 830719 PDR ADOCK 05000305
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REVISED 6-21-83 Rage 2 of 5 f
.h EMERGENCY PLAN IMPLEMENTING PROCEDURES
-Index-(cont'd)
' REVISION
, ATE Procedure #
TITLE EP-ENY-3A Environmental Protection Director Actions and Directives H
06-21-83 EP-ENV-38 EM Team Actions E
06-21-83 EP-ENV-3C
- Primary Dose Projection Calculation - IBM 06-21-83 Personal Computer EP-ENY-3D Prnnary Detemination of Meteorological Data 06-21-83 EP-ENY-3E Manual Detemination of X/Q (KNPP Meteorological Data)
E 06-21-83 EP-ENY-3F Manual Detemination of X/Q (Green Bay Meteorological Data)
D 06-21-83 EP-ENY-3G Manual Dose Pr'ojection Calculation 0
06-21-83 h
EP-ENV-3H Protective Action Recamendations B
06-21-83 EP-ENY-4A Sam'ple Acquisition, Portable Instrument Use C
03-10-83' EP-ENY-4B Sample Acquisition, Air Monitoring Devices B
05-21-82 EP-ENY-4C Sample Acquisition, Environmental Sampling Techniques B
05-21-82 EP-ENY-SA LCS-1 Operition B
4-21-83 a
l EP-ENV-5B MS-3 Operation B
4-21-83 C
03-10-83 EP-ENY-SC I'N TI Operation EP-E NV-5' 3, 0-4G Operation A
12-21-81 EP-ENY-cl
%ter-Stokes Operation A
03-10-83 EP-ENY-6 Data Analysis, Dose Projections and Protective Action Recamendations DELETED EP-ENV-6A Relocation of Site Access Facility (Habi tabili ty)
A 03-10-83 EP-ENV 6B SAF Enviromental Sample Analysis Relocation A
11-24-82 EP-ENY-7 Site Access Facility Cmmmications B
03-10-83 EP-ENY-8.
Total Population Dose Estimate Calculations 12-21-81 4
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Pagm 3 of 5 REVISED 6-21-83 EMERGENCY PLAN IMPLEMENTING PROCEDURES F)x Y.
-Index-(cont'd)
Procedure #
TITLE REVISION' DATE EP-EOF-1 Corporate Staff Emergency Response Organization G
03-10-83 EP-EOF-2 Emenjency Operations Facility (EOF) Activation D
03-10-83 EP-EOF-3 Corporate Response to an Unusual Event F
03-10-83 EP-EOF-4 Corporate Response to an Alert G
03-10-83 EP-EOF-5 Corporate Response to a Site Emergency G
03-10-83 EP-E T-6 Corporate Response to a General Emergency G
03-10-83 EP-EOF-7 Communti:ations Documentation E
03-10-83 EP-EOF-8 Relocation of EOF DELETED ~ 03-01-83 EP-EOF-9 Interface with Support Organizations E
03-10-83 EP-0P-1 Control Room Emergency Organization A
1-03-83 EP-0P-2 Emergency Control Room Activation for B
1-03-83 Emergency Response EP-0P-3 Control Room Communications' A
1-03-83 e
EP-0SF-1 Operational Support Facility (OSF) Organization A
1-15-82 i
EP-0SF-2 OSF Activation A
05-21-82 EP-OSF-3 Wort Requests During an Emenjency A
1-15-82 EP-0SF-4 OSF Canmmications 53 03-10-83 EP-RET-1 Radiation Emergency Team (RET) Organization C
03-10-83 g
EP-RET-2 Inplant RET C
03-10-83 l,
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,Page 4 of 5 REVISED 6-21-83 EMERGENCY PLAN IMPLEMENTING PROCEDURES
-Index-(cont' d)
Procedure #
TITLE REVISION DATE EP-RET-2A RP0/RAF Activation C
03-10-83 EP-RET-2B Gaseous Effluent Sample and Analysis C
03-01-83 EP-RET-2C Containment Air Sampling and Analysis DELETED 03-01-83 EP-RET-2D Emergency Radiation Entry, Controls and B
03-10-83 Implementation EP-RET-2E Handling of Injured Personnel A
03-10-83 EP-RET-2F Personnel Decontamination B
03-10-83 EP-RET-3 Emergency Chemistry Team C
03-10-83 EP-RET-3A Liquid Effluent Release' Paths A
12-21-81 EPIET-3B Post-Accident Reactor Coolant Alternate B
03-10-83 Sampling Procedure O
EP-RET-3C Pos.t Accident Operation of the High Radiation Sample Room 06-18-82 EP-RET-30 Containment Air Sampling Analysis Using CASP A
06-21-83 EP-RET-4 Site RET C
03-10-83 EP-RET-4A ET Radiological Monitoring A
DELETED EP-RE'T Radiological Controls at Site Access Facility (SAF) A 03-10-83 EP-RET-4C Site Radiological Monitoring A
03-10-83 EP-RET-5 Plume Projections A
12-21-81 EP-RET-5A Plume Projections (Backup Method)
A 12-21-81 EP-RET-6 Dose Projection A
12-21-81 EP-RET-7 RAF/RP0 Communications A
03-10-83 EP-RET-8 Contamination Control at the Two Rivers A
03-10-83 Community Hospital h
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......Page 5 of 5 REVISED 6-21-83 EMERGENCY PLAN IMPLEMENTING PROCEDURES W
Index-
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.(cont'd)
Procedure #
TITLE REVISION DATE EP-SEC-1 Security Organization A:
03-10-83 EP-SEC-2 Security Force Response to Emergencies C
03-01-83 EP-SEC-2(a)
Manual Activation' of Emergency Sirens DELETED 1-29-82
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EP-SEC-3 Personnel Accountability (Initial and Maintaining) D 03-10-83 EP-SEC-4 Dosimetry Issue at SAF A
.03-10-83 EP-TSC-1 Technical Support Center (TSC) Organization 12-21-81
C. _,,;,
03-10-83
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EP-TSC-3 P1 ant Status Procedure B
03-10-03 EP-TSC-4 Emergency Design Change, Major Equipment Repair 12-21-81 I
l EP-TSC-5 TSC Commmications A
03-10-83 EP-TSC-6
- Assess;nent of Reactor Core Damage A
.03-10-83
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I WISCONSIN PUBLIC SERVICE CORPORATION l
NO.
EP-AD-ll REV. C I
Kewaunee Nuclear Power Plant l
TITLE : Emergency Radiation Controls l
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EMERGENCY PLAN IMPLEMENTING PROCEDURE l
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1 DATE:
l PAGE 1 of 8 M 211983 A
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//M//dsad' APPROVED BY REVIEWED BY
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l.0 PURPOSE The purpose of this procedure is to maintain exposure to emergency workers As L_ow A_s Reasonably Achievable ( ALARA).
2.0 APPLICABILITY This procedure will be implemented during an Alert, Site Emergency or General
, Emergency.
3.0 REFERENCES
3.1 Emergency Plan, Kewaunee Nuclear Power Plant 3.2 NtREG-0654 FEMA-REP-1, REY.1, Criteria for Preparation and Evaluation of.
Radiological Emergency Response Plans and Preparednes in Support of 1
Nuclear Power Plant (Nov.1980).
3.3 EPA-520/1-75-001, Kinual of Protective Action Guides and Protective Actions for Nuclear Incidents (June 1980)
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3.4 Code of Federal Regulations 10 CFR F'rt 20.
3.5 Radiation Protection Manual and Health Physics Procedure Manual Kewaunee Nuclear Power Plant.
3.6 EP-RET Emergency Radiation Entry, Controls and Implementation.
l 4.0 RESPONSIBILITIES 4.1 All personnel involved with the Emergency are responsible for adhering to the requirements of this procedure.
4.2 The Radiological Protection Director (RPD) and Emergency Director (ED) are l
responsible for reviewing and approving all requests for exposures in excess of 10 CFR 20 limits.
4.3 The RPD has the overall responsibility for inplant personnel monitoring.
(h' 4.4 The In-plant Radiation Emergency Team (RET) is responsible for performing l
those activities necessary to implement the requirements of this procedure.
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. WISCONSIN PUBLIC SERVICE CORPORATION l
NO.
EP-AD-11 1
Kewaunee Nuclear Power Plant l
TITLE : - Emegency Radiation Controls EMERGENCY PLAN IMPLEMENTING PROCEDURE l
I DATE:
i PAGE 2 of 8 M 21 %
g 5.0 REQUIAEMENTS 5.1 All Emergency Personnel 5.1.1 The requirements of the Health physics Procedure Manual and the Radiation Protection Manual shall be applicable during all radiological emergencies, except as authorized by the RPD or ED.
5.1.2 Prior to entering a Radiation Hazard Area or highly contaminated area during an Emenjency, an Emergency Radiation Work Pennit (ERWP, Fonn AD-ll.1) must be completed.
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5.1.3 For emenjency actions requiring immediate access to radiation hazard areas, the ERWP may be bypassed. Approval of the RPD or ED is required and the ERWP must be completed as soon after the entry as possible.
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5.1.4 For any entry wtierian exposure greater than 10 CFR 20 limits is likely, an Authorization For Increased Exposure (Form AD-ll.3) must be completed.
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l NOTE: For the purposes of emergency repair / operation, personnel r
I will not be allowed to recei.ve a dose exceeding 25 REM to the whole body.
5.2 Emergency Entry Team l
5 2.1 An Emenjency Entry Team shall be fonned for entries into highly radioactive or contaminated areas for the purpose of search and rescue on life saving missio'ns.
5.2.2 The RPD shall designate an Entry Team Coordinator.-
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5.2.3 Communications will be maintained via two-way radios.between the Entry Team Coordinator and the In-Plant RET.
5.2.4 Only self-contained pressure demand respiratory equipment shall be used for worker protection during emergency entries.
5.2.5 Each team shall be briefed prior to entry.
The briefings shall cover: purpose of the mission; exposure limits; work methods for reduced. exposures; conditions expected to be encountered; abort instructions; stay times; personal dosimeter nonitoring; respiratory l
protection equipment and anti-C clothing requirements.
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WISCONSIN PUBLIC SERVICE CORPORATION l
NO.
EP-AD-ll i
Kewaunee Nuclear Power Plant l
TITLE: Emergency Radiation Controls l
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EMERGENCY PLAN IMPLEMENTING PROCEDURE l_
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1 PAGE 3 of 8 JUN 211983 5.3 Radiological Protection Director 5.3.1 Any exposure to radiation in excess of 10 CFR Part 20 limits shall be authorized by the RPD with the concurrence of the ED (Form AD-ll.3).
In the absence of the RPD, the ED may authorize an overexposure directly after concurring with the on-shift HP or an In-plant RET member.
- 5. 3. 2 The RPD will infom personnel of the availability of thyroid blocking agents (Potassium Iodide) for use in accordance with EP-AD-18; 5.3.3 ERWP's must be reviewed and approved by the RPD.
5.4 In-plant Radiation Emergency Team 5.4.1 All inplant radiological conditions will be -reported to the Radiological Protection Director 5.4.2 The RET will make radiological assessments of all inplant areas requiring access and occupation during an emergency.
5.4.3 The projected amount of time inplant emergency workers will be allowed to stay in a radiation and/or contaminated area shall be detemined in accordance with Stay Time (Fom AD-ll.2) and shall include a review of:
a.
Projected route exposures b.
Measured dose rates and airborne concentrations c.
Personnel exposure history d.
Projected duration of task e.
Infomation on current plant conditions and the plant area under consideration 5.4.4 Continous radiation monitoring coverage will be provided in occupied areas when the potential for increased radiation levels exist and the area is occupied.
5.4.5 Radiation surveys need not be perfomed in areas of extremely high radiation levels. Rather, surveys should be perfomed only if entry into these areas is required for other emergency actions.
5.4.6 Air sample surveys and radiological assessment surveys shall be completed depending on the nature and seriousness of the emergency.
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l WISCONSIN PUBLIC SERVICE CORPORATION l
NO.
EP-AD-ll I
Kewaunee Nuclear Power Plant l
TITLE:
Emergency Radiation Controls h
l EMERGENCY PLAN IMPLEMENTING PROCEDURE l-l l DATE:
l PAGE 4 of 8 21 E
-5.4.7 For all entries into a Radiation Hazard area, exposures to airborne concentrations of radioactivity shall be limited by the following:
a.
Whenever practicable, total exposure of any individual during an energency should be limited to 40 MPC-hours. MPC hours are calculated by multiplying the concentration in tenns of the number of MPC's by the total time of exposure (in hours).
b.
If emergency operations demand, total exposure of any individual shall be limited to 1,200 MPC-hours. This is roughly equivalent to the 3 Rem / quarter limit for external radiation exposure.
c.
Limits for exposure to Xe-133 and other noble gases are based on beta plus gamma dose limits to the skin and whole body.
d.
An integrated exposure of 10,000 MPC-hours for nuclides with short effective half-lives is. roughly equivalent to an external, whole-body exposure of 25 Rem.and should be received only with the approval of the Radiological Protection Director or Emergency Di recto r.
Similar exposure to nuclides with long effective
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F half-lives are to be avoided and should be restricted to 1,200 MPC-hours as in b above.-
l e.
Since the effects of external and internal exposure are
. additive, personnel should avoid exposures over 1,200 MPC-l hours, even in the event of life-saving or rescue action, l
unless external radiation fields are minimal and unless effective hal f-lives are short.
f.
Personnel who have been exposed to more than 10,000 MPC-hours shall be removed from further emergency duty, sole body counted, and referred to a physician for attention.
5.4.8
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For all special entries the RET shall review with the team members the task to be performed including the following where applicable.
a.
Potential stress conditions and problems b.
Work methods c.
Number of personnel required d.
Allowable exposure limits e.
Tools, equipment, and parts f.
Lighting l
g.
Communications requirements l
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. WISCONSIN PUBLIC SERVICE CORPORATION l
NO.
EP-AD-11 i
Kewaunee !1uclear Power Plant l
TITLE: Emergency Radiation Controls EMERGENCY PLAN IMPLEMENTING PROCEDURE l
i l DATE:
JUN 211983 l PAGE 5 of 8 I
I 5.4.9 A Radiation Emergency Team Member shall accompany any personnel entering any radiation or contaminated area where radiological conditions are unknown.
5.4.10 Any individual who has exceeded 10 CFR 20 limits shall be temporarily removed from radiation exposure work.
His exposure record shall be reviewed by the RPD and ED prior to further radiation work.
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WISCONSIN PUBLIC SERVICE CORPORATION KEWAUNEE NUCLEAR POWER PLANT EP-AD-ll
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JUN 211983 EMERGENCY Page 6 of 8 RAOIATION WORK PERMIT Form AD-11.1 Associated Work a.amtier:,
E-Number Date Prepared:
REGULAR EXTENDED
' E FFECTIVE:
through TO BE COMPLETED BY WORK SUPERVISOR: (Attach Work Request if available)
.5b l.ocation and
Description:
EXP.
TOTAL EXP.
TOTAL ASSIGNED WOR KERS LIMIT R EC'O ASSIGNED WORKERS LIMIT R EC'D 9
TO BE COMPLETED BY HEALTH PHYSICS:
e,aral Area Radiation:
Instrument Used:
antamination Levels:
- HP Coverage Req. YES/NO
- aborrie Actiuty:
Surveyed By:
DiVIOUAL REQUIREMENTS: (Circle Required items)
Dosimetryl TLD Badge Dosimeter Wrist Badge Finger Badge Protective Labcoat' Skullcap / Hood Liners
' ubber Gloves
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l R
l Clothing:
l Coverails Plastic Suit Plastic Hood Rubber Overshoes Plastic Boots Other:
l PECIAL INSTRUCTIONS:
i l
APPROVAL TERMINATION
?. ark Supervisor:
By:
RADIOLOGICAL PROTECTION DIRECTOR Date/ Time:
EMERGENCY DIRECTOR Reason:
r~^ODITION AL: Overexposure Authorization
. h Predicted Exposure An Airborne Exposure Analysis must be l
completed for each assigned worker following cxit from an Airborne Contaminated area (Form AD 11.2)
Rad Protection Director
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. WHITE COPY - - - - Monitor Room Emergency Director PINK COPY - - -
. Job Location
Time:
Airborne Emergency EP-AD-11 Date:
Exp~osure Radiation JUN 211983 Location:
Analysis Work Permit Page 7 of 8 (Page 2 of 2)
Form AIT-ll.T" (h>0 TOPE t1/2 OBSERVED OCCUPATI0fal RATIO BODY BURDEN CONCEN.
'MPC CONC./MPC REG. NO.
30 MINUTE EXPOSURE i Ar-41 1.827 h 2 E-6 1
- Kr-85 10.720 y 1 E-5 2
i Kr-85m 4.480 h 6 E-6 3
I Kr-87 76.300 m 1 E-6 4
l Kr-88 2.840 h 1 E-6 5
i Xe-133 5.245 d 1 E-5 6
l Xa-133m 2.190 d 1 E-5 7
i Xe-135 9.110 h 4 E-6 8
! Xe-135m 15.360 m 1 E-6 9
l Xa-138 14.130 m 1 E-6 10 I
J PARTICULATES: Less than 8 day tl 7p i Na-24 15.000 h 1 E-6 11
. Mn-56 2.578 h 5 E-7 12
} Rb-88 17.800 m 1 E-6 13 1 Sr-92 2.710 h 4 E-7 14 i Mo-99 66.020 h 2 E-7 15 i Te-132 78.200 h 2 E-7 16 l Cs-138 32.200 m l 1 E-6 17 l La-140 40.220 h l
2 E-7 18 PARTICULATES: Greater than 8 day tifp 1Cr-51 27.704 d 2 E-6 19 L'en-54 312.700 d 4 E-8 20 5U7Co-58 70.800 d i
5 E-8 21 Fe-59 44.630 d 5 E-8 22
- Co-60 5.271 y 9 E-9 23 i Zn-65 244.400 d 6 E-8 24
! Nb-95 35.060 d 1 E-7 25 i Lr-95 64.020 d 3 E-8 26 i
l Cs-134 2.062 y 4 E 27 l Cs-136 13.160 d 4 E-7 28 i Cs-137 30.170 y 6 E-8 29
! Ba-140 12.789 d 1 E-7 30 ice-144-284.300 d 1 E-8 31 HALOGENS 1 F-18 109.740 m 5 E-6 32 i Br-84 31.800 m 1 E-6 33 I I-131 8.040 d 9 E-9 34 i 1-132 2.300 h 2 E-7 35 i 1-133 20.800 h 3 E-8 36 I I-134 52.600 m 5 E-7 37 i I-135 6.610 h 1 E-7 38 i TRITIUM 12.280 y 2 E-3 39 i Sr-90 28.600 y I
1 E-9 40 STAY TIME CALCULATION: (based on TOTAL:
WORKER NAME:
a 40hr week)
TIME IN IIME OUT 40 hrs
=
TOTAL STAY TIME x 60 =
STAY TIME (hrs / week)
(min./ week)
((TO TAl[l ( IN MINUTES } ton nia) = (
)((
) ((bu Muu =
(EXPOSURE TIME) ( HR
)
(
)
)
)
NfC-HOUR CALCULATION:
' '3 MPC-HOURS
__ RESPIRATOR P'ROTECTION FACTOR
(
)
RECEIVED
(
)
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JUN 211983 Page 8 of 8 FOIN AD-11.3 0
WISCONSIN PUBLIC SERVICE CORPORATION
.KEWAUNEE NUCLEAR POWER PLANT AllTHORIZATION FOR E!ERGENCY RADIATION EXPOSURE DATE:
Name:
Soci al Securi ty No.:
Employer:
Date of Birth:
Reason for Emergency Exposure:
Requeste'. by:
Titie:
d Presen t Expos ure Limi t i s.........................................
REM Increased Expos ure Limi t Wil l Be..............................
REM Total Li fetime Exposure at Start of thi s Quarte r was..............
REM Accumul a ted Expos ur e fo r thi s Qua rte r is.........................
REM l
Total' Li fetime Expos ure to date i-s................................
REM l
5(N-18) Limi t is...
REM Onused Li fetime Exposure Remaini ng i s.............................
REM Fo m N RC-4 u p-to - da te ?........................................ Ye s No NOTE: Environmental Protection Agency guidance states that emergency worker exposures should be limited to 25 REM for emergency repair / operation.
This limit may be exceeded for life saving operations.
"I agrc; that I have not previously received a once in a lifetime dose of 25 REM and that
. my rad';; ion exposure limit can be increased."
Signed:
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l Approved by Radiological Protection Director:
O EmenJency Director:
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I SISCONSIN PUBLIC SERVICE CORPORATION l
NO. EP-ENY-3A REY. H s
l Kewaunee Nuclear Power Plant I TITLE: Environmental Protection Director
)
l Actions and Directives EliERGENCY. PLAN IMPLEMENTING PROCEDURE l
l
[ DATE:
1 PAGE 1 of 17 l
JUN 211983 l
I
/*,ff h m t v REVIEWED BY )V/#fd 1 APPROVED BY
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1.0 APPLICABILITY Upon the classification of an incident as a Site or Ceneral Emergency, or during an Alert if conditions warrant, the Environmental Protection Director (EPD) will execute this procedure.
2.0 PRECAUTIONS 2.1 Projected dose rates, concentrations and meteorological conditions must be known prior to dispatching the Environmental Monitoring Teams (EM Teams).
2.2 Ensure proper protective actions are taken for the Enviromental Monitoring Team members prior to dispatch.
2.3 Utilize the Field Map with Plexiglass Cover in recording field results.
3.0 REFERENCES
i 3.1 EP-AD-11, Emergency Radiation C'ontrols 3.2 EP-RET-2, Inplant Radiation Emergency Team l
l 4.0 DIRECTIONS I
Environmental Protection Director i
4.1 If notified by pager, confinn contact with a telephone call to the control room at 4.2 If infonned of ET activation by the ERM:
l a.
Notify members of the Environmental Monitoring Team per Form ENV-3A.l.
l NOTE:
If unable to contact a sufficient number of personnel from the l
group by using home or office telephone numbers, activate the pager system per attached Table ENY-3A.2 or call System Operating at and provide your name and title and the names and titles of the individuals you wish to page. Also provide a brief (20 seconds) message to be s
broadcast over the pagers. Systen Operating personnel will r
attempt to contact these individuals via the paging system.
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b.
Proceed to the EOF.
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' WISCONSIN PUBLIC SERVICE CORPORATION I
NO. EP-ENV-3A l
~
Kewaunee Nuclear Power Plant l TITLE: Environmental Protection Director
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l Actions and Directives EMERGENCY PLAN IMPLEMENTING PROCEDURE I
i l DATE:
i PAGE 2 of 17 JUN 211983 l
l l
4.3 Perform dose projection calculation via EP-ENY-3C, Primary Dose Projection I
Calculation - IBM Personal Computer and EP-ENY-3D, Primary Determination i
of Meteorological Data.
l l
NOTE:
If the IBM Personal Computer is not available for use, refer to l
I l
NOTE:
If the WPS IBM Computer is not available for use, refer to EP-ENV-3E, 1
Manual Detennination cf X/Q-KNPP Meteorological Data; EP-ENY-3F, 1
Manual Detemination of XQ/-Green Bay Meteorological Data; and i
EP-ENV-3G, Manual Dose Projection Calculations as are appropriate.
4.4 Determine Protective Actions needed via EP-ENY-3G, Protective Action Recommendation Determinations.
NOTE:
See Decision Flow Chart, Figure 3A.1.
4.5 Maintain a log of all significant events reported and directed.
5.0 PERSONNEL DISPATCH 5.1 Evaluate the radiological consequences in consultation with the f
4 Radiological Protection Director (RPD) from the above data and advise Environmental Monitoring Teams accordingly of the appropriate protective actions.
5.2 Dispatch Environmental Monitoring Teams, via the Environmental Monitoring Team Coordinator, to the prpjected plume path as follows:
NOTE: As Form ENY-3A.2 is initiated for Tracking EM Team Sampling, I
record Dose Projections (ENV-3C or 3G) for the sample points on I
the form.
l l
5.2.1 Dispatch EM teams to predetemined sample points, TABLE ENY-3A, I
near tb projected plume edges. Spacing the teams to define the l
plume s' ape and characteristics.
I NOTE:
If lake breeze effect exists as detennined in Form ENV-3D.2, l.
3E.3 or 3F.3 refer to step 6.0 for guidance in directing environ-
,I mental monitoring teams.
I 5.2.2 Observe caution when sending EM teams into a plume, especially I
to point near the centerline.
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' WISCONSIN PUBLIC SERVICE CORPORATION l
NO. EP-ENV-3A I
Kewaunee Nuclear Power Plant l TITLE: Enviromental Protection Director ~
l Actions and Directives EMERGENCY PLAN IMPLEMENTING PROCEDURE I
I l DATE:
JUN 21 Igg 3 l
PAGE 3 of 17 I
I 5.2.3 After the plant has discontinued releases, continue tracking the plume to 'the perimeter of the EPZ.
l 5.2.4 Record sampling results and. locations on Fona ENV-3A.2, using i
Base Map sector designate and predetennined sample location number.
EXAMPLE:
Log: Sector "A" at " point 122" 5.3 Record the following data for each enviromental sample location on Fonn ENV-3A, den received from EMT Coordinator.
5.3.1 Date and Time results received.
5.3.2 Direct radiation readings.
5.3.3 Particulate activity.
5.3.4 I-131 concentration.
5.3.5 Noble gas concentration.
I 5.4 Mark the most recent results on the plexiglass covered field maps.
I 5.5 Transmit the' most current data recorded on the field maps to the Technical l
Support Center Director.
5.6 Redirect the' Environmental Monitoring Teams to take subsequent samples l
as necessary.
5.7 Transmit the measured data, and any plume track changes, to the Radiological Protection Director promptly.
NOTE: Meteorological conditions should be checked periodically.
l l
5.8 Direct the Enviromental Monitoring Team Coordinator to take appropriate I
precautions for the collection of samples and the storage of all environ-mental samples obtained at the Site Access Facility.
5.9 Continue to update plume path sample results on the Field Map as results are reported.
5.10 Transmit results and recemendations to the Emergency Response Manager.
5.11 Keep the SAF and EM team infonned on plant conditions.
I I
1(ISCONSIN PUBLIC SERVICE CORPORATION l
NO. EP-ENV-3A I
Kewaunee Nuclear Power Plant i TITLE : Enviromental Protection Director l
Actions and Directives g
EMERGENCY PLAN ' IMPLEMENTING PROCEDURE I
I l DATE:
JUN 211983 l PAGE 4 of 17 I
I 6.0 EFFECT OF LAXE BREEZE ON' PROJECTED EXPOSURES l
6.1 Actual dose rates west of the Lake Bree'ze " front" (where the lake l
breeze meets the prevailing wind) will be lower than projected.
6.2 Exposure from the plume may occur in areas not encompassed by the X/Q or Xu/Q overlays since the plume is directed back toward the lake in the direction of the prevailing wind.
6.3. Monitoring Considerations l
Figure ENY-3A.2 shows a method for detennining the location of the l
Lake Breeze front. Following the guidelines below and Figure ENY-3A.2
'l will aid in determining the radiological effects of the lake breeze on I
the plume track.
6.3.1 One tean should be sent to the predicted lake breeze front position via the plume edge downwind of the prevailing wind.
}
The. team should then begin searching for the lake breeze front to verify the predicted lake breeze position. Once discovered i
the. team should be sent downwind of the projected plume with l
respect to the prevailing wind. The objective is to look for radiation or plume recirculation in the lake breeze.
6.3.2 The other team should sample the plume between the lake shore and the lake breeze front.
i l
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l EP-ENY-3A JUN 'e 11983 Page 5 of 17 0+
FIGURE ENV-3A.1 DECISION FLOW CHART I Dose Projection l l
Cal cualtion l
I I
l(EP-ENV-3C or 3G)l l
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l l Results l<-------<---------------l l on Field l l
l Maps l
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' l Determinations l l
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l l Conditions lT l
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l Results l 1 Reports l V
I Record -l 1 Results l I on l
l Field l
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EP-ENY-3A JUN 211983 Page 6 of 17 FIGtRE ENV-3A.2 LAKE BREEZE EFFECTS DIAGRAM h
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Team Dispatched to Sample lake breeze front and retrun flow.
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Team Dispatched to Sample plume between plant and lake breeze front.
3 NOTE: This Drawing is for Illustration Only.
jJ The Actual sampling points are designated by the Enviromental Protection Director.
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JUN 211983 Page 7 of 17 1'0 2
FORM ENY-3A.1
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EP-ENV-3A JUN 211983 Page 9 of 17 TABLE ENV-3A.1 TLD MONITORING AND SAMPLING LOCATIONS (1 of /)
Lake Shore Rd (M) 1/4 mile north of Zander Rd 1.
J. Lake Shore Rd (M) 1/4 mile south of Two Creeks Rd 3,
thy 42 1/4 mile North of Two. Creeks Rd Intersection A.
Two Creeks Rd 3/4 mile west of Hwy 42,1/4-mile N. on Blaha Road S.
County BBB and County BB Intersection 6.
County BBB 1/2 mile. south of BB
/. 3/4 mile west and 1/2 mile south of County Hwys. BB and BBB inersection (trailer park) 11. County BB 1/4 mile east of Saxonburg Rd 9.
County BB 1/2 mile east of State Hwy 163 l0. County B 1/4 mile north of Zander Rd
)). Saxonburg Rd 1/2 mile north 'of Zander Rd 12 Two Creeks Rd l/2 mile west of Saxonourg Rd
\\3. Two Creeks Rd 1/4 mile east of State Hwy 163
)4. Two Creeks Rd 1/2 mile east.of Saxonburg Rd
- 15. Tannery.Rd 3/4 mile north of Tappawingo Rd 1
- 16. Access Rd off of Tappawingo Rd 1/4 mile eas of Tannery Rd
- 17. Tappawingo Rd 3/4 mile west of Tannery Rd 13 Tappawingo Rd 1/4 mile west of Saxonburg Rd
- 19. Tappawingo Rd 1/4 mile west of State Hwy 163 30 Tappawingo rd and Janbo Creek Rd Intersection
?l. Jambo Creek Rd 1/4 mile north of Holmes Rd
- 32. County Hwy BB 1/2 mile west of State Hwy 163
- 23. Lakeshore Rd (M) 1/4 mile north of Nuclear Rd (M)
?4. Nuclear Rd (M) 1/2 mile eas of State Hwy 42
- 3) - Kewaunee County
,p, 3
(M) - Rinitovoc. County
>I s
~
JUN 211983 Page 10 of 17 TABLE ENV-3A.1 (cont' d)
(2 of 7)
- 25. Lakeshore Rd (M) and Nuclear Rd (M) Intersection-26.
Irish Rd 1/4 mile east of Meyer Rd
- 27. State Hwy 1771/4 mile west of County Hwy. 0
- 28. Elmwood Rd and Ravine Rd Intersection
- 29. Tannery Rd 1/4 mile north of Elmwood Rd
- 30. 1/4 mile east-of County Hwy V and State Hwy 42 Intersection
- 31. State Hwy 421/2 mile north of Irish Rd
- 32. Senzinger Rd 1/4 mile west of Tannery Road
- 33. County Ny V and Saxonburg Rd Intersection
- 34. Corners Rd and Division Dr. Intersection Q
- 35., State Hwy 421/4 mile north of Rawley Rd
- 36. South, entrance road' to Point! Beach State Park,1/4 mile east of County Hwy. O f
s
- 37. Nuclear (M) 3/4 mile wes't of' Tannery. Rd
- 38. 1/4 mile southland'l/4 dile west of_ Saxonburg Rd and Nuclear Rd (M) Intersection
- 39. Tappawingo Rd 0.1 mile east of State Hwy 42
- 40. State liwy 163 and State by 147 Intersection
- 41. Prince Rd 1/4 mile north of Rockledge Rd
- 42. Jambo Creek Rd 1/4 mile north of Rockledge Rd
- 43. County Hwy Q and Intersection with Factory Rd
- 44. County Hwy Q 1/4 mile north of Zander Rd
- 45. County Hwy BB 0.4 mile east of Harpt Lake Rd
- 46. Nuclear Rd (K) 0.4 mile west of State Hwy 42
- 47. Nuclear Rd (K) 1/2 mile west of Hwy 42
- 48. - County Hwy BB and state Hwy 42 Intersection
- 49. German Lane 1/4 mile west of State Hwy., 42 4
(K? - Kewaunee Count (MJ - Mani towoc Coun
EP-ENY-3A JUN 211983 Page 11 of 17 TABLE ENV-3A.1 (cont'd)
(3 ot /)
50.
~
State Hwy 421/4 mile soutn of Nuclear Rd '(K)
- 51. State Hwy 42 and Nuclear Rd (K) Intersection
- 52. State Hwy 42 and Nuclear Rd (K) Intersection
- 53. State Hwy 42 and Intersection of Nuclear Rd (K)
' 54. State Hwy 42 0.4 mile north of Nuclear Rd (K) 55.
State Hwy 421/4 mile south of Sanciy Bay Rd
' 5 6.
State Hwy 42 and Intersection of Sandy Bay Rd
- 57. Sandy Bay Rd and Intersection of Cemetary Rd
- 58. Cenetary Rd 1/4 mile north of Sandy Bay Rd.
- 59. Lake shore Rd (K) and Interection of Cemetary Rd
- 60. Lake Shore Rd (K) 1/2 mile east of State Hwy 42
- 61. Lake Shore Rd (K.) and State Hwy 42 Intersection
- 62. Lake Shore Rd (K) 1/2 mile west of State Hwy 42
- 63. Sandy Bay Rd 1/2 mile west of State Hwy 42
- 64. Sandy Bay Rd and Intersection of Woodside Rd P
- 65. Woodside Rd 1/2 mile north of Nuclear Rd (K)
- 66. Woodside Rd and Intersection of Nuclear Rd (K) l
- 67. Woodside Rd 1/4 mile south of Nuclear Rd (K)
- 68. Woodside Rd 3/4 mile north of County Hwy BB
- 69. Town Hall Rd 1/4 mile north of County Hwy BB
- 70. Town Hall Rd 1/4 mile north of Nuclear Rd (K)
- 71. Town Hall Rd 3/8 mile south of Sandy Bay Rd
- 72. - Town Hall Rd 1/2 mile south of County Hwy G
- 73. County Hwy G 1/2 mile east of town Hall Rd 4
d 4.
.j EP-ENV-3A JUN 211983 Page 12 of 17 h
TABLE ENV-3A.1 (cont'd)
(4 of 7)
- 74. Woodside Rd and County Road G Inte'rsection
- 75. Old Settlers Rd and Cemetary Rd Intersection
- 76. Old Settlers Rd and Ny 42 Intersections
- 77. Old Settlers Rd 1/4 mile east-of Woodside Rd
- 78. Woodside Rd.1/2 mile south of Old Settlers Road s._
- 79. Old Settlers Rd. and Town Hall Road Intersection 80.
Norman Road 1/4 mile north of County Hwy. G
- 81. County Hwy B 1/4 mil'e west of Norman Rd
- 82. Saint Peters Rd 1/4 mile north of '01d Settlers Rd
- 83. Wochos Rd and intersection of Old settlers Rd
- 84. North Intersection of Range Line Rd and County Hwy G
- 85. County Hwy B 1/4 mile north of County Hwy G i
- 86. Normn Rd 1/4 mile north of Sandy Bay Rd l
87.
Sandy Bay Rd and Intersection of Saint Peters Rd Co' nty Hwy B 1/2 mile south of Sandy Bay Rd 88.
u i
89.
Nuclear Rd (K) 1/2 mile east of Range Line.Rd l
- 90. Nuclear Rd (K) and Norman Rd Intersection 91. Nonnan Rd 1/4 mile north of County Hwy,BB
- 92. County Ny B 1/4 mile north of County hwy BB I
- 93. Range Line Rd 1/4 mile north of County hwy BB 1
l
- 94. Collegiate Rd 1/2 mile west of Range Line Rd 95.
State Hwy 1631/4 mile west of Sleepy Hollow Rd
- 96. Bolt Rd and County Hwy Q intersection 97.
Bolt Rd 1/4 mile west of Collegiate Rd
- 98. Knutso'n Rd and State Hwy 96 Intersection
- 99. Manitowoc Rd and Langes Corners Rd Intersection 4
(K) - Kewaunee County (M) - Mani towoc County
EP-ENV-3A JUN 211983 Page 13 of 17 i
TABLE ENV-3A.1 (cont'd) l}
(5 of 7) 100. State Hwy 1631/4 mile south of Old Settlers Rd 101. County Hwy J 1/4 mile west of State Hwy 163 102. Sleepy Hollow Rd and Kassner Rd Intersection, 103. Church Rd 1/2 mile north of County Hwy J 104. saint Peters Rd and Town Line Rd Intersections 105. County hwy B 1/4 mile South of County Hwy J 106. County iky J 1/4 mile west of Town Hall Rd 107. Town Hall Rd and Town Line Rd Intersections.
108.' Town Line Rd 1/2 mile west of Woodside Rd 109. Town Line Rd and State Hwy 42 Intersection 110. Town Line Rd 0.3 mile east of Mile Rd
(]
111. Lake Rd 1/2 mile east of State Hwy 42 112. County hwy J 1/2 mile west of State iky 42 113. County hwy J 1/2 mile east of Town Hall Rd 114. Krok Rd 1/4 mile west of Sleepy Hollow Rd 115. Krok Rd 1/4 mile west of Church Rd 116. Krok Rd 1/4 mile east of Saint Peters Rd 117. 1/4 mile south of Angle Rd and Krok Rd Intersections 118. State Hwy 421/4 mile south of Hospital Rd 119. State Hwy 42 3/4 mile south of County hwy F 120. County Hwy C 1/2 mie west of Kewaunee City
' 121. County Hwy C l/2 mile north of County Hwy F 122. Birchwood Rd and County Hwy F Intersection h
123. Lilac Lane 1/4 mile north of County F (K).- Kewaunee County s.
(M) - Manitowoc County
Ei EP-ENV-3A
- j JUN 211983 Page 14 'of 17
'!h TABLE ENV-3A.1 (cont'd) 16 of /)
t 124. State Hwy 29 and County hwy B Intersection 12'5. Church Rd 1/4 mile north of State Hwy 29 126. Town Hall Rd 1/2 mile south of State Hwy 29-127. Angle Rd 1/4 mile south of State Hwy 29 128. Hospital Rd 3/4 mile north of State Hwy 42 129. East end of Krok Rd, along the Lakeshore 130. Old Settlers Rd 1/2 mile east of Twn Hall Rd 131. 1204 Milwaukee St., Kewaunee 132. County Hwy. O,1 1/2 miles south of County Hwy. YV 133. Lake Shore Rd 1/2 mile north of Kewaunee City 134. Lakeshore Rd (K) 1/2 mile north of First Road (Barnett Sub.)
135. County Hwy F 1 1/4 miles west of State Hwy 42 l
136. Maple Lane 1/2 mile west of County Hwy C l
137. Church Rd and Town Line Rd Intersection (northeast of Ellisville) l 138. Sleepy Hollow Rd 1/4 mile north.of Hwy 29 139. Reckelberg Rd 1/4 mile south of Krok Rd 140. Schweiner Rd 1/2 mile south of County hwy J 141. Schultz Rd and State Hwy 96 142. Lyons Rd 1/4 mile southof Zander Rd 143. County hwy Q 1/4 mile north of State Hwy 147
.144.
Fisherville Rd and Cherney Rd Intersection
' 145. Steiners Corners Rd.1/2 mile west of State Hwy.147 (K) - Kewaunee County (M) - Manitowoc County m
I y
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J, s,
EP-ENY-3A l, i
..juN 211983
~
~
-Page 15 of 17
,h TABLE ~ ENV-3A.1 (cont' d)
(z.of /)
-.. /
~
~
.(
146. Meadow Dr.1/4 mile north of E. Hillcrest Rd.
147. County Hwy. 01/2 mile south of County Hwy. VV
/
148. Coast Guard Station, Two Rivers 149. WPS Operations Building, Two Rivers j
150. City Hall Roof, P.anitowoc y
~
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s EP-ENV-3A JUN 211983 Page'16 of 17 aO Table ENY-3A.2 PAGING SYSTEM OPERATION
- .1 Ei
]
A.1 Tone and Voice Radio Pagers are assigned to personnel as shown with call
- j numbers on the Emenjency Call List.
('See EP-AD-17 ).
11 1
A.2 Whenever it is necessary to contact a person on the Emergency Call List W
and he is not on site, the home telephone number should be called first.
1 If he cannot be reached at home, contact should then be attempted by using l!
the person's individual call number. A group of individuals may be
?
, contacted by using the grou' call nunter. Tone and voice contact by pagers p
d is effective within a 15 mile radius of the transmitting station. Only s
7 tone contacts can be made outside the 15 mile radius.
S j
'A 3 How to Place a Fage 3.1 Detennine the two. digit pager code for the party or group you wish to contact from the paqer assignment list.
l PLANT EXTENSION PHONES
}
3.2 Dial the tenninal access code on any plant extension.
a
~
5 Kewaunee site transmitter -
~
Green Bay transmitter -
~
When the tenninal answers and responds with a beep, go to step 3.3.
a.
b.
If you near a " busy" signal, hang up and try again.
1
- 3.3 Dial the two digit pager code for the party or group you wish to a
contact fran the pager assignment list.
NOTE: This number must be preceded by a "1" when using the Green Bay
?
y transmi tter.
~
3.4 Listen for the i;cknowledge -(beeping) tone, indicating page being
]
transmitt'ed.
' 3.5 When the beeping tone stops, speak your message to the called party.
You have about 20 seconds to talk. A " click" signals that your allotted time has expired.
N&
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'm**-*%We~'#
?
~
~
JUN 211983 Page 17 of 17 TABLE ENY-3A.2 (cont'd)
)
i GP.EEN BAY EXTENSION PHONES 3.6 Dial:
j a.
For Kewaunee site transmitter --
b.
For Green Bay transmitter -
/
Ji 3.7 When the tenninal answers and responds with a beep, go to step 3.8.
If you hear a " busy" signal, hang up and try.again.
a.
3.8 Of al the two digit pager code for the party or group you wish to 2
contact from the pager assignment list.
NOTE: This number must be preceded by a "1" when using the Green Bay transmitter.
3;9, Listen for the acknowledge (beeping) tone, indicating page being
})
transmitted.
'3.10 When the beeping tone stops speak your message to the called party.
You have about 20 seconds to talk. A " click" signals that your allotted time has expired.
9
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4 mv
l WISCONSIN PUBLIC SERVICE CORPORATION l
NO.
EP-ENV-38 REY. E I
Kewaunee Nuclear Power Plant l TITLE: EM Team Actions a Q.
l ci V EMERGENCY PLAN IMPLEMENTING PROCEDURE l.
l
}
l DATE:
i PAGE 1 of'8 M 21 E I
h (LW REVIEWED BY h(//#d m
APPROVED BY
/
1 1
1.0 APPLICABILITY In the event of a Site or General Emergency, Enviromental Monitoring Team
^
(EMT) Members will be activated. The Emergency Response Manager (ERM) or Emergency Director may activate the team during an Alert if conditions warrant.
2.0 PRECAUTIONS 2.1 Check to see if all equipment is operational prior to use in the field.
2.2 Ensure all protective clothing / devices are inspected for damage prior to use.
3.0 REFERENCES
3.1 EP-ENV-2, SAF Activation 3.2 EP-ENY-7, Site Access Facility Communications 4.0 INSTRUCTIONS 4.1 EMT Coordinator Actions 4.1.1 Upon pager activation or notification of EOF activation, report to the Site Acc'ess Facility (SAF) and assume the responsibility of coonfinating the environmental monitoring teams.
4.1.2 Establish a communications link with the Emergency Operations Facility (EOF) or the Radiation Protection Office / Radiological Analysis Facility (RP0/RAF) per EP-ENY-7, Site Access Facility Communications.
4.1.3 Establish EM Teams as personnel arrive at SAF and give them each I
a letter (i.e. A,B,) designatiori for radio communication purposes.
I inidm the Enviromental Protection Director (EPD) of the designations I
of the EM Teams.
4.1.4 Direct EM Teams to assemble the needed equipment for the appropriate type of field monitoring assigned the team.
4.1.5 Ensure each Environmental Monitoring Team has the following equipment:
O i
aesP reter ror eech tee e der e-b.
Anti-contamination clothing i
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yISCONSIN P',3LIC SERVICE CORPORATION l
NO. EP-ENY-38 l
l Xewaune<: Nuclear Power Plant i TITLE: EM Team Actions I
f.MERGENCY PLAN IMPLEMENTING PROCEDURE l
l l
l DATE:
JUN 211983 i PAGE 2 of 8 I
I s
c.
Dosinetry (high and low range pocket dosimeters and TLD's) d.
Hand held radiation detection equipment 4.1.6 Ensure that each team has the equipment specified for the EMT kit (Table ENY-3B).
4.1.7 Report to the EPD when a team is available and ready for assignment.
4.1.8 Upon order fra the EPD, direct the designated teams to the appro-priate sample locations and infonn them of the type and quantity of samples to be obtained.
4.1. 9 Maintain Radio Contact with the EM Teams at all times NOTE: Contact should be made every 15 minutes.'
4.1.10 Track the EM Teams locations on the Field Map and record sample times and locations using Fonn ENV-3B.2.
4.1.11 Periodically request radiological condition updates from EPD and pass this information to the field teams.
~
4.1.12 Have the EM Teams report their pocket dosimeter readings during communication contacts.
4.1.13 Record EM Team Member's pocket dosimeter readings on Fonn ENY-3B.l.
4.1.14 Verify operability of counting equipment has been completed per EP-ENY-SA, B and C TCounting Equipment Operating Procedures) and if not, perform applicable checks.
a.
Commence counting samples on the appropriate analytical instrument as soon as field samples return.
b.
Log results on the. applicable Counting System Worksheet, and sample activities in the appropriate columns of the Radiological Environmental Monitoring and Sampling Worksheet, Form ENY-38.2.
4.1.15 Report sample analysis results to the EPD.
NOTE:
Repeat all communications transmitted, to assure accurate transmission of data.
-4
1 i
WISCONSIN PUBLIC SERVICE CORPORATION l
NO. EP-ENV -38 1
i Kewaunee Nuclear Power Plant l TITLE: EM Team Actions
+O
\\
l EMERGENCY PLAN. IMPLEMENTING PROCEDURE l
l l DATE:
JUN 211983 l PAGE 3 of 8 I
I 4.1.16 As EM Teams return, direct the team members to. resupply their equipment and await further direction.
NOTE: Ensure they have perfomed appropriate personnel frisking for contamination.
4.1.17 At all times keep the EPO infomed of EM Teams availability.
4.2 EM Team Actions 4.2.1 Report to the SAF and assume the responsibilities for.
conducting environmental moni toring.
4.2.2 Obtain personnel TLD and High and Low Range Pocket Dosimeters.
4.2 3 Assenble proper equipment and check for satisfactory operation in accordance with EP-ENV-4A, B, and C; Sample Acquisition Procedures.
]
4.2.4 When equipment is assenbled and operation checks have been completed, report to the EMT Coonfinator for direction and assignment.
4.2.5 Perform the following upon assignment from the EMT Coordinator:
a.
Load equipment into the designated vehicle.
b.
Check communications with EMT Coordinator by contacting the SAF:
1.
Approximately every 15 minutes, 2.
Any time that an increase of 4 times general area radiation reading is found, 3.
Any time there is any confusion as to the. dispatch order or whenever clarifying infonnation is needed.
l' c.
Proceed to the designated area, obtaining general area radiation i
l readings during transit and record readings in Log Book as well I
as reading location.
d.
Report to SAF by radio upon arrival at the designated monitoring site.
l9 l:
-q
l l
WISCONSIN PUBLIC SERVICE CORPORATION l
NO.
1 l
Kewaunee Nuclear Power Plant i TITLE: EM Team Actions
~ t i
EMERGENCY PLAN IMPLEMENTING PROCEDURE l
1 l DATE:
JUN 211983 i PAGE 4 of 8 I
I Acquire the samples and readings as directed by the EMT Coordinator,
- e.. in accordance with EP-ENV-4A, B, and C, Sample Acquisition Procedures.
O NOTE: Beta / Gamma measurements for the purpose of Plume Tracking should be made over an approximately 30 second time span at approximately 3 to 4 feet above the ground.
In the same location measurements at approximately 6 inches above the ground should be taken. If the 6 inch reading is lower in magnitude than the 4 foot measurement, the assumption should be that the predominant radiation source is the airborne Plume, and this should be noted and reported to the SAF (EMT Coordinator).
f.
Maintain accurate records of samples taken and the time acquired.
When all samples have been collected, contact SAF by radio, g.
and report conpletion.
If no further samples are ordered at the present location, request direction from.the EM Team Coordinator.
O' 4.2.6 Upon return to the SAF, perform the following steps:
i Take collected samples to SAF monitoring station before a.
transporting to counting room, Decontamination instructions, if necessary, should be obtained b.
i from site RET Member.
NOTE: Care must be taken to prevent contaminating the entire SAF Area when te'ams return to SAF from the field.
4.2.7 Replenish su'pplies.
4.2.8 Report to the EM Team coordinator when ready for redeployment.
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EP-ENY-38 JUN 211983
- g Page 7 of 8 TABLE ENY-3B SAF E M TEAM KIT INITIALS
- 1 PRM 7 uR meter
- 1 PIC 6A fon chamber
- 1 E530 with HP-190 probe & survey tube
- 1 RAP-1 Lo Volume Sampler
- 1 RAP-1 Sample Jumper
- 1 Staplex'Hi Vol Sampler
- 1 Hi Band Two-way Radio
- 1 Emergency' Generator 1 Flashlight with Batteries
- '2 Full-face Masks with Particulate Cartridges 1 Stopwatch (Pocket Watch) 1 Calculator 4 Hartnelli Beakers in Plastic Bags 12 Silver Zeolite Cartridges 12 4" Particulate Filters
,12 2" Particulate Filters 41 liter wide mouth poly bottles filled with water 1 Pkg Swipes 1 Pkg Sample Labels u
4 Garden Trowels 3 Grass clippers 16' Measuring Tape h
4 Funnels i
l 4 Ladles l
-4 l
.-l
t l
EP-ENY-3B s 0N 211983 1
Jage 8 of 8 i-TABLE ENY-3B (cont'd)
SAF E M TEAM KIT INITIALS 2 dz Small Ziplok Bags 10" x 12" 2 dz poly bags 12" x 18", Clear 3 Tweezers 1 Reflective Vests 4 Poly Bags, 33" x 40", yellow 1 Set EMT Area Maps (large. sector map) 2 Clipboards l' Set Pens & Pencils
~
12 pr Gloves & Liners
-]
6 pr Canvas Booties 1 roll Tuck Tape I book of ENY Procedures and Spare Foms (EP-ENY-1, 2, 3B, 4A, 48, 4C, SE & 7)
- NOT LOCATED.IN SEALED TRUNK 4
1
I WISCONSIN PUBLIC SERVICE CORPORATION l NO.
Primary Dose Projection Kewaunee Nuclear Power _ Plant l TITLE Cal cula tion -
h
' EMERGENCY PLAN IMPLEMENTING l
IBM Personal Computer PROCEDIRE l
l l DATE:
JUN 211983 l PAGE 1 of 4 1
I REVIEWED BY )R / A c/a APPROVED BY
[/
n lav
(
l I
I 1.0 APPLICABILITY This procedure will be utilized by the Environmental Protection Director during any incident that involves a significant release of radioactive' materials to the environment, for the purpose of projecting a radiological dose inpact.
2.0 P'RECAUTIONS 2.1 Ensure all data on the fonns of the procedure is accurately recorded.
2.2 Check all calculations for accuracy.
2.3 Ensure that all-cable connections on the computer are secure.
2.4 If the IBM personal computer is not available for use, proceed to EP-RET-5, Plume Projection, and EP-RET-6, Dose Projection, for per-r fonning dose projection calculations.
E.5 If both IBM personal computer and IBM mainfram computer are not available for use, proceed to ENV-3E, 3F, and 3G for performing dose projection cal culations.
l 2.6 Meteorological data must be re-evaluated every 30 minutes or whenever significant changes occur, to determine if dose projection ~ should be recal cula ted.
3.0 REFERENCE 3.1 U.S. NRC Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, %ppendix I, Revision 1, October 1977.
3.2 U.S. EPA, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, EPA-520/1-75-001, September 1975. Appendix D Technical Bases for Methods the Estimate the Projected Thyroid Dose and Projected Whole Body Gamma Dose from Exposure to Airborne Radioiodines and Radioactive Noble Gases.
O e
-q
t I
WISCONSIN PUBLIC SERVICE CORPORATION l NO.
Primary Dose Projection Kewaunee Nuclear Power Plant l TITLE Calculation -
1 IBM Personal Computer EMERGEPCY PLAN IMPLEMENTING PROCEDURE l
l l DATE:
JUN 211983 l PAGE 2 of 4 I
I 4.0 INSTRUCTIONS 4.1 Starting the IBM Personal Computer 4.1.1 Acquire the 51/2 inch diskette labeled " Dose Projection" fran the office supplies storage file in the EOF bullpen.
4.1.2 Insert the diskette into the IBM personal computer's disk drive A.
When facing the computer, the diskette label should be on the right in the corner nearest you. C1ose the door on disk drive A.
4.1.3 Turn the conputer on. Turn the printer on.
It should take approximately 40 seconds.before the caputer responds.
4.1. 4 The Dose Projection Program is now executing. A menu will soon appear on the screen.
Instructions will appear at the bottom of the screen.
4.2 Dose Projection from Plant Release Data 4.2.1 Acquire the plant release data on Fom ENV 3C.1, Plant Release Data, from the RAF or the TSC and complete the appropriate section of the Form.
r 4.2.2 Acquire meteorological data on Foms ENV-3D.1 or ENV-3F.1, (Section I & II), Meteorological Data Worksheet and ENY-3C.1, l
IBM Personal Computer.
l 4.2.3 Enter data collected in IBM personal computer.
4.2.4 Proceed to procedure EP-sNV-3H, Protective Action Recommendation,
' to determine the appropriate protective action recommendation.
4.3 Dose Calculation from Field Sample Data 4.3.1 Acquire the field sample data on Fom ENV-3C.2, Field Sample Data, from the D1 team coordinator.
4.3.2 Acquire the meteorological data on Forms ENV-3D.1 or ENY-3F.1, (Section I & II) Meteorological Data Wortsheet, that is closest in time to the time on fom ENV-3C.2, Field Sample Data.
4.3.3 Enter data collected on Foms ENV-3D.1 or ENV-3F.1, (Section I & II),
Heteorological Data Worksheet and ENY-3C.2, Field Sample Data into the IBM personal computer.
4.3.4 Proceed to procedure EP-ENY-3H, Protective Action Recommendation, to detemine the appropriate protective action. recommendation.
-q
~
EP-ENY-3C JUN 211%3 Page 3 of 4 1 (3)
FORM ENY-3C.1 PLANT RELEASE DATA DATE TIME Reactor Trip:
Date Time Expect Release:
Duration:
Hours I.
STACK ANALYTICAL RESULTS Operating Fans: (circle one)
Aux. A / Aux. B /- Aux. A and B SVA
/ SYB
/
SVA and SYB ISOTOPE CONCENTRATION (uCi/cc)
Kr-85 KR-85m KR-87 KR-88 O'~:
Xe-133 Xe-13 3m Xe-135 Xe-135m
~
I-131 II. SPING RESULTS Operating Fans: (circle one)
Aux. A / Aux. B / Aux. A a nd B j
SVA
/ SVB
/
SVA and SVB l
l Latast 10 minute Icdine Average uCi/cc Latest 10 minute Gas Average uCi/cc III. STEAM RELEASE Main Steam Line Monitor:
R/hr SI Flow Rate:
gpm.
-=
EP-ENV-3C JUN 211983 Page 4 of 4 0
FORM ENV-3C.2 FIELD SAMPLE DATA DATE TIME Sample Time:
Sample Location:
Nearest Isopleth:
I.
GAS ANALYSIS ISOTOPE CONCENTRATION (uCi/cc)
Kr-85 KR-85m KR-87 KR-88 Xe-133 Xe-133m Xe-135 Xe-135m I I '. DIRECT FIELD READINGS Whole' Body Dose Rate:
uCi/cc l
b L
l
-q r
x-,--
r-r----e
-r----.-
m-c-
-s, w-,m,-
w.
,-,n
--,,-c-,-.,-----e--
--a-
i I
l NO.
EP-ENV-3D WISCONSIN PUBLIC SERVICE CORPORATION I
Kewaunee Nuclear Power Plant i TITLE: Primary Determination of "Q
l Meteorological Data EMERGENCY. PLAN IMPLEMENTING PROCEDURE l
l l DATE:
JUN 211983 l PAGE 1 of 3 I
i ni. VIEWED BY.)R /nf e d; Mo h
(uhu APPROVED BY
(
Y I
i 1.0 APPLICABILITY This procedure is used to gather the Kewaunee Nuclear Power Plant Meteoro-logical Data.
2.0 PRECAUTIONS 2.1 As a minimum, the following meteorological parameters from the Kewaunee Nuclear Power Plant Meteorological tower are required to u'se this procedure.
a.
One wind speed indication (60 meter elevation or 10 meter elevation).
b.
One wind direction indication (60 meter elevation or 10 meter el eva tion).
c.
Vertical Temperature' Difference indication (Delta T between 60 meters and 10 meters)or Sigma Theta.
If this minimum sta is not availabl, acquire and use data from EP-ENV-3E, Manual Detemination of meteorological eta (Green Bay Meteorological Data).
2.2 Meteorological data must be re-evaluated every 30 minutes or whenever significant changes occur.
3.0 REFERENCES
3.1 NRC Regulatory Guide 1.145, Atmospheric Dispersion Models.for Potential Accident Consequence Assessments at Nuclear Powr Plants, August 1979 3.2 NRC Regulatory Guide 1.23, Rev 1 (Proposed), Meteorological Programs In Support of Nuclear Powr Plants, September 1980.
4.0 INSTRUCTION 4.1 Gathering the Meteorological Data 4.1.1 Record the meteorological parameters available in section I on Fom ENV-3D.1, Meteorological Data Worksheet.
4.1. 2 Record the additional release infornation in Section II on Fom ENY-3D.1, Meteorological Data Wortsheet.
4.2 Lake Breeze Determination Detennine if lake breeze exists using Fom ENV-3D.2, Lake Breeze Effect Worksheet.
If lake breeze condition exists, enter the data on Form ENY-3D.2 into the Dose Prediction Program.
-4
EP-ENV-3D PbhEof FORM ENY-3D.1 METEOROLOGICAL DATA WORKSHEET DATE TIME I.
METEOROLOGICAL PARAMETERS Data Source (circle one):
Primary Tower / Backup Tower Parameter Description Parameter Name Parameter Indications a.
Wind Direction at 60 meter level WD 60 Degrees b.
Wind Direction at 10 meter level WD 11 Degrees c.
Wind Speed at 60 meter level WS 60 MPH d.
Wind Speed at 10 meter level WS 10 MPli e.
Vertical Temperature Di fferences Delta T
'F f.
Standard deviation of horizontal Sigma Theta Degree s wind direction f
II. RELEASE INFORMATION Circle one answer per question:
a.
Is a primary to secondary leak in progress?
YES /
NO b.
Is the release from the Steam Genera, tor Safety Valves, l
Steam Generator Power Operated Relief Valve or Turbine Driven Auxiliary Feed Pump Steam Exhaust?
YES /
NO O
e
-Q
+
JUN 211983 O...
Page 3 of 3 FORM ENY-3D.2
~
LAKE BREEZE EFFECT WRKStiEET DATE TIME I.
Is local wind direction (WD l'0 from Fonn ENY-3D.1 or WD 60 if WD 10 is not available) between 20* and 170' clockwise?
NO - No lake breeze effect (ignore the rest of form)
YES - Proceed to step 'II.
II.
Call Green Bay National Weather' Station for the following data:
(Phone a.
Green Bay wind direction:
degrees
- b.. Average opaque sky cover from sunrise to present tenths c.
850 millibar wind speed from Green Bay norning sounding knots.
i III.
Is Green Bay wind direction between 210* and 330' clockwise?
No lake breeze effect (ignore rest of form)
NO YES There is a lake breeze effect (go to step IV) t IV.
Determine the onset time of the lake breeze from a review of the strip chart wind direction data record in TSC. A sudden wind shift from the SW-NW sector to an easterly component will mark the onset time.
Lake Breeze Onset Time:
1 4
-Q
?
l WISCONSIN PUBLIC SERVICE CORPORATION l NO.
EP-ENV-3E REV. E l
Kewaunee Nuclear Power Plant l TITLE : Ma~nual Detemination of X/Q l
(KNPP Meteorological Data)
EMERGENCY PLAN IMPLEMENTING PROCEDURE l
i l DATE: (
21 E l PAGE 1 of 6
[ /I, /g n;p REVIEWED BY JX //14 M 1 APPROVED BY
/
m 1.0 APPLICABILITY This procedure is used to estimate the atmospheric dispersion factor (X/Q) using Kewaunee Nuclear Power Plant Meteorological Data.
2.0 PRECAUTIONS 2.1 As a minimum, the following meteorological parameters from the Kewaunee Nuclear Power Plant Meteorological tower are required to use this procedure.
a.
Average wind speed indication (60, meter elevation or 10 meter elevation).
b.
Average wind direction indication (60 meter elevatT6'n or 10 meter elevation).
~~
(M.
c.
Vertical Temperature Difference indication (Delta T between 60 V
meters and 10 meters).
If this minimum sta is not available, use EP-ENV-3F, Manual Determination of X/Q (Green Bay Meteorological Data), to.detemine atmospheric dispersion.
2.2 Meteorological sta must be re-evaluated every 30 minutes or whenever significant changes occur, to determine if X/Q must be recalculated.
2.3 When detemining X/Q or Xu/Q for a point of interest that falls between two isopleths on an overlay, select the value of X/Q or Xu/Q that corresponds to the isopleth lying closest to the plume centerline.
If a point of interest lays between an isopleth and plume centerline, select the value of X/Q or Xu/Q that corresponds to the nearest mile maricer on the centerline.
2.4 the WIND DIRECTION CIRCLE on the Base Map may appear to the user to be shifted 180 degrees. This is not an error. the WIND DIRECTION CIRCLE reflects the direct uselfTnTdirection infomation.
3.0 REFERENCES
3.1 NRC Regulatory Guide 1.145, Atmospheric Dispersion Models for Potential
("7 Accident Consequence Assessments at Nuclear Powr Plants, August 1979 3.2 NRC Regulatory Guide 1.23, Rev 1 (Proposed), Meteorological Programs In Support of Nuclear Power Plants, September 1980.
I WISCONSIN PUBLIC SERVICE CORPORATION l NO.
Kewaunee Nuclear Power Plant i TITLE: Manual Dete'mination of X/Q O
i (x"e" "ete r 'o9'c ' o te)
EMERGENCY PLAN IMPLEMENTING PROCEDURE l
I l DATE:
PAGE 2 of 6 21 E 4.0 INSTRUCTIONS 4.1 Record Meteorological ParametersSection I on Fonn ENV-3E.1, Meteorological Data Worksheet.
~
4.2 Det'ennine the stability class using the Vertical Temperature Difference (item I-E on Form ENY-3E.1) and the table in Section II of Fonn ENY-3E.1).
4.3 Detennine release elevation from Section III of Fom ENV-3E.1.
4.4 For Elevated Releases complete steps 4.4.1 through 4.4.8.
If the release is ground level, proceed to step '4.5.
(.4.1 Place the elevated overlay for.the stability class determined in step 4.2 on the Base Map.
4.4.2 Align the centerline of the overlay with the actual wind
]
direction value from WD60 (item I-A on Fom ENY-3E.1) on the Base Map Wind Direction Circle.
NOTE:
If WD60 value is not ava_ilable, use WD10 value.
4.4.3 ecord points of interest in the path of the plume in column 1 on Fonn ENV-3E.2 and record the corresponding sector in column 2.
4.4.4 Detennine the distance from the release point to each point of interest and record in column 3 of Fom ENV-3E.2 (Base Map' Scale: 2 inches = 1 mile).
4.4.5 Record wind speed WS60 in column 4 of Fonn ENY-3E 2 (Wind Speed is the same for all points of interest).
NOTE:
If WS60 is not available, use WS10 value.
4.4.6 Calculate impact time (IT) using the formula on Fom ENY-3E.2 and recorti in column 5.
4.4.7 Detennine X/Q for each point of interest from the overlay and record in column 7 of Fonn ENV-3E.2.
4.4.8 Proceed to step 4.6 (step 4.5 is not required for elevated releases).
ba
-4
g I
WISCONSIN PUBLIC SERVICE CORPORATION I NO.
Kewaunee Nuclear Power Plant l TITLE: Manual Determination of X/Q l
(KNPP Meteorological Data) h EMERGENCY PLAll IMPLEMENTING PROCEDURE l,
I l DATE:
PAGE 3 of 6 21 E 4.5 For Ground Level Releases, complete steps 4.5.1 through 4.5.8 4.5.1 Place the ground level overlay for the stability class determined in step 4.2 on the Base Map.
- 4.5.2 Align the centerline of the overlay with the actual wind direction value from WD10 (item I-B on Fonn ENV-3E.1) on the Base Map Wind Direction Circle.
NOTE:
If WD10 is not available, use WD60 value.
4.5.3 Record points of interest in the path of the plume in column 1 of Form ENY-3E.2 and record the corresponding sector in column 2 4.5.4 Detennine the distance from the release point to each point of
~
interest and record in column 3 of Fom ENV-3E.2 (Base Map Scale: 2 inches = 1 mile).
4.5.5 Record wind speed WS10 in column 4 of Fonn ENY-3E.2 (Wind
. Speed is the same for all points of interest).
NOTE:
If WS10 is not available, use WS60 value.
~
4.5.6 Calculate impact time (IT) using the formula on Fom ENV-3E.2 and record in column 5.-
4.5.7 Detemine Xu/Q for each point of interest from the ' verlay and o
. record in column 6 of Fom ENY-3E.2.
4.5.8 Calculate X/Q for each point of interest using the fonnula on Fom ENY-3E.2 and record in column 7.
4.6 Detennine if lake breeze exists using Fom ENV-3E.2.
If lake breeze conditions exist, implement special field moni toring in accordance with EP-ENV-3A, section 6.0.
O
EP-ENV-3E khe of 6 FORM ENY-3E.1
.}
METEOROLOGICAL DATA WORKSHEET DATE TIME I.
Meteorological Parameters Parameter Parameter Paramenter Description Name Indication A.
Wind Direction at 60 meter level WD60 Degrees B.
Wind Direction at 10 meter level-WD10 Degrees C.
Wind speed at 60 meter level WS60 mph x 0.447 =
m/sec D.
Wind speed at 10 meter level WS10 mph x 0.447 =
m/sec E.
Vertical Temperature Difference VTD
'F F.
Standard Deviation of Horizontal Wind Direction SIGMA THETA Degrees II. Stability Class Use below table to detennine stability class.
.]
Stabili ty Pasquill Sigma Theta Classification Categories (degrees)
~VTD ('F)
VTD
< - 1.71
~
7g>,22.5 Extremely unstab,le A
22.5 > 6g > 17.5
-1.71< VTD
< - 1.53 Moderately mstable B
i7.5 > 6g > 12.5
-1.53< VTD
< - 1.35 Slightly unstable C
-1.35< VTD.
< - 0.4 5 12.5 > Cg > 7.5 Neutral D
-0.45 < VTD 1.35 7.5 > 6g > 3.8 Slightly. stable E
3.8 > 6g >~ 2.1 1.35< VTD 3.60 Moderately stable F
l Extremely stable G
2.1 > U@
3.60< YTD NOTE: If YTD and Sigma Theta do not agree use VTD classification.
l III. Release Elevation An Elevated release must meet all of the below criteria, otherwise the release is considered Ground Level.
a.
Primary to Secondary Leak is in progress.
b.
Release is from Steam Generator Safety Valves, Steam Generator Power Operated Relief Valve or Auxiliary Feed Pump Turbine Exhaust.
c.
Wind speed is less than im/sec.
d.
Stability class is A, B, C or D.
^
Elevated Ground Level
i EP-ENY-3E JUN 211983 O
Page 5 of 6 FORM ENY-3E.2 RELEASE WORKSHEET DATE TIME 1
2
_3
_4
_5
_6
_7 (D)
(WS)
(TT)*
Point of Distance Wind Speed Impact Time Xu/Q**
X/Q***
Interest Sector (miles)
(meters /sec)
(minutes)
(meters-2 (sec/ meters 3}
~
O ll.
- IT = D/WS x 27
- N/A for Elevated Release F
(Xu/0)
- When calculating for Ground Level Release: X/Q =
Wd L
4 1
EP-ENV-3E Jun 2 1 1983 Fage 6 of 6 0
FORM ENV-3E.3 LAKE BREEZE EFFECT WORKSHEET DATE TIME I.
Is local wind direction (WD10 from Form 3E.1 or WD60 if WD10 is not available) between 20' and 170* clockwise?
s No - No lake breeze effect Yes - Proceed to Step II-II. Call Green Bay National Weather Station and get wind direction in degrees.
~
]
(Phone Number r
Wind Direction III.
Is Green Bay wind direction between 210and 330' clockwise?
No - No lake breeze effect Yes - Lake breeze ef fect s,
I WISCONSIN PUBLIC SERVICE CORPORATION l
NO.
EP-ENV-3F REV. D J
i Kewaunee Nuclear Power Plant l TITLE: Manual Detennination of X/Q
.h l
(Green Bay Meteorological Data)
EMERGENCY PLAN IMPLEMENTING PROCEDURE l
l i
l DATE:
JUN 211983 l PAGE 1 of 7 I
REVIEWED BY IXf///..di @ Mas #
APPROVED BY
/*
g,,mg
(
l 1.0 APPLICABILITY This procedure is used to estimate the atmospheric dispersion factor (X/Q) using Green Bay National Weather Service Meteorological Data sen Kewaunee Nuclear Power Plant Meteorological Data is not available.
2.0 PRECAUTIONS 2.1 This procedure is to be used only den the following minimum meteorological parameters are not available from the Kewaunee Nuclear Power Plant Meteorological tower.
a.
One wind speed indication (60 meter elevation or 10 meter elevation).
Q b.
One wind direction indication (60 meter elevation or 10 meter el eva tio n).
c.
Vertical Temperature Difference indication or Sigma Theta.
2.2 Meteorolog,ical data must be re-evaluated every 30 minutes or whenever significant changes occur to detennine if X/Q must be recalculated.
2.3 When determining Xu/Q for a point of interest that falls between two isopleths on an overlay, select the value of Xu/0 that corresponds to the isopleth lying closest to the plume centerline.
l If a point of interest lays between an isopleth and plume centerline, select the value of Xu/Q that corresponds to the nearest mile i
marker on the centerline.
2.4 The WIND DIRECTION CIRCLE on the Base Map may appear to the user to be shif ted 180 degrees. This is not an error.
The WIND DIRECTION CIRCLE reflects the direct use7f7nTdirection infonnation.
3.0 REFERENCES
3.1 NRC Regulatory Guide 1.145, Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Powr Plants, August 1979.
3.2 NRC Regulatory Guide 1.23, Rev 1 (Proposed), Meteorolegical Programs ilO In Support of Nuclear Power Plants, September 1980.
i Q) m
-Y l
l
i WISCONSIN PUBLIC ' SERVICE CORPORATION l
NO.
.i Kewaunee Naclear Power Plant l TITLE: Manual Detennination of X/Q
h l
(Green Bay Meteorological Data)
EMERGEtCY PLAN IMPLEMENTING PROCEDURE l
l l DATE: JUN 211983 i PAGE 2 of 7 I
I 4.0 INSTRUCTIONS 4.1 Call the National Weather Service Station at Green Bay (
for meteorological param6ters I.A B, C and D on Form ENV-3D.l.
4.2 Call Point Beach Nuclear Plant for meteorologicsl parameters II.A & B on Fonn ENY-3F.1.
4.3 Detennine the stability class from step III of Fonn ENY-3F.1.
4.4 Place the ground level overlay 'for the stability class determined in step 4.3 on the Base Map.
4.5 Align the centerline of the overlay with the wind direction value on the base map wind direction circle.
NOTE: Use local wind - direction if available. Use Green Bay wind direction (paraneter I.A on Fonn ENY-3F.1), if not available at the plant.
4.6 Record points of interest in the path of the plume in column 1 of Fom ENY-3F.2 and record the corresponding sector in column 2
~
4.7 Detennine the distance from the release point to each point of interest and record in column 3 of Fom ENY-3F.2 (Base Map Scale: 2 inches =
1 mile).
4.8 Record local wind speed (parameter II.B on Fonn ENY-3F.1) in m/sec in column 4 of Fonn ENY-3F.2 (wind speed is the same for all points of interest).
NOTE:
If local wind speed is not available, use Green Bay wind speed (parameter I.B on Fonn ENV-3F.1).
4.9 Calculate impact time (IT) using the fonnula on Fonn ENV-3F.2 and record in column 5.
4.10 Detennine Xu/Q for each point of interest from the overlay and record in column 6 of Fonn ENY-3F.2.
4.11 Calculate X/Q using the fonnula on Fonn ENY-3F.2 and record in column 7.
4.12 Detennine if lake breeze exists using Fonn ENV-3F.3.
If lake breeze conditions exist, implement special field monitoring in accordance with EP-ENY-3A, section 6.0.
-q
,O O
EP-E NV-3F JUN 211983 Page 3 of 7 FORM ENV-3F.1 h
METEOROLOGICAL DATA WORKSHEET DATE TIME I
I.
Meteorological Parameters (Green Bay)
Parmeter Parameter Parameter d
Description Name Indication A.
Wind Direction WD(GB)
Degrees B.
Wind Speed WS(GB)
Knots x 0.515 =
meters /sec C.
Opaque Cloud Cover CLCVR (tenths)
D.
Cloud Cefling CLCEG
( feet)
E.
Observation Time of above (time)
II. Meteorological Parameters (Point Beach)
A.
Wind Direction WD(PB)
Degrees B.
Wind Speed WS(PB) nph x 0.447 meters /sec
=
III. Stability Class O-A.
Detennine the Insolation Class Number (INCLNO) from the below table.
INCLNO l
HOUR OF DAY From/To (Military Time)*
~"i f
l l 0001 10601 10701 10801 10901 11001 l 1 101 11201 11301 1 1401 11501 11601 11701 l I DATE 106001070010800109001100011100112001130011400115001160011700124001 lI/5-1/22 l
1l 1 11 11 12 12 12 12 12 11 11 11 11 1
11/23-2/6 l
111 11 11 12 12 12 12 l 2 l 1 11 I1 l 1 l
12//-2/21 1
111 11 12 l 2 l 2 l 2 l 2 l 2 12 11 11 11 l
l2/22-3/8 1 1 11 11 12 l 2 l 2 13 12 12 l 2 l1 i1 l1 l
(
l3/9-3/23 1
111 l 2 12 12 13 13 l3 l 2 12 l 2 l 1 11 l
l l3/24-4//
I 1 l 1 l 2 12 l 3 13 13 13 I3 l 2 l 2 l 1 11 l
l l4/8-4 /22 1
1 11 12 13 13 l' 3 13 13 13 13 l 2 l 1 11 l
l 14/23-5/7 l
1l 2 12 13 13 13 13 13 13 13 12 !2 l 1 l
l5/8-5/22 1 1 l 2 12 13 13 13 14 13 13 13 12 12 11 l
15/23-6/6 l 1 12 l 2 13 13 14 14 14 13 13 12 12 11 l
l6/7-6/21 1
112 12 l 3 13 l 4 14 14 13 13 l 2 l 2 l 1 l
l6/22-//o I
1 12 l 2 13 13 14 14 I4 13 13 l 2 l 2 11 l
l///-//21 l
1 12 l2 13 13 14 14 14 13 13 l 2 12 11 l
l7/22-8/5 l
112 l 2 13 13 13 l 4 13 13 13 l 2 l 2 11 l
l8/6-8/20 1 112 12 l 3 13 13 13 13 13 13 12 12 11 l
18/21-9/4 1 1l 1 l 2 13 13 13 13 13 13 13 12 l 1 TI l
19/5-9/19 l
111 12 l 2 13 13 13 13 13 12 l 2 l 1 11 I
i 19/20-10/4 1 1 l 1 l 2 l 2.
I2 13 13 13 12 12 l 2 11 l1 1
110/5-10/191 1 11 11 12 l 2 12 13 l 2 12 l 2 l 1 11 11 1
110/20-11/31 1 11 l 1 12 l 2 12 13 l 2 12 12 11 11 l 1 1
111/4-11/181 111 l1 12 -l Z l2 l2 l 2 12 12 11 11 l 1 1
111/19-12/31 111 l 1 l1 12 12 12 l2 12 11 l 1 11
!1 I
l_12/4-12/181 111 l1 11 l 2 12 l2 12 l 2 11 l 1 l1 11 l
l 112/19-1/4 1 1 11 l 1 11 l 2 l2 l 2 12 l 2 11 11
_1 1_
l 1 l
n aaylignt savings time is in er rect, suotract i nour tron locas time.
4 l
l 1
O EP-ENV-3F JUN 211983
.: Q Page 4 of 7 i
FORM ENY-3F.1 (cont'd)
' V METEOROLOGICAL DATA WORKSHEET DATE TIME B.
Determine Net Radiation Index (NRADI) from opaque cloud cover (CLCVR step I.C above), cloud ceiling (CLCEG -
step I.D above), isolation class nuuber (INCLNO - step III.A above), and the below table:
- 6 lbi NRADI During Daytime (function of CLCVR and CLCEG) and Nighttime Conditions
- I l
Daytime ll Nighttime ***
l l
l 1
CLCEG l
ll l
l CLVR l
< 7,000 f t l
7,000-15,000 f t I
>16,000 f t ll l
1 1
I l
11 1
10/10 I il i
11/10 I 11 I
12/10 1 NRADI = ICLN0 ll NRADI = -2 l
13/10 l II I
14/10 I 11 I
15/10 l ll l
16/1D l l
1 ll l
17/10 INRADI*= ICLN0 -21 NRADI* = ICLN0 -1 I
ll l
18/10 l l
l l l NRAD I*~* = -1 1
19/10 l l
l ll l
110/10 1 NRADI = 0 I
iI I
- If NRADI is less.than 1, set NRADI equal to 1.
- If CLCVR is 10/1,0 and CLCEG is less than 7000 f t, NRADI equals 0.
- Nightime is defined as that period of time fran 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> before sunset to one hour after sunrise (see TABLE ENY-3F).
C.
Dete'rmine the Stability Class ~from wind speed in meters per second (WS(PB) step II.B above) and Net Radiation Index (NRADI - step III.B above) from the below table:
NOTE:
If WS(PB) is not available, use WS(GB) from step I.B above.
STABILITY CLASS Stability Class as a Function of NRADI and Wind Speed l
l NRADI l
l WS I
l l m/sec i
4 3
2 1
0
-1
-2 1
10-0.77~
l A
A B
C D
F G
I 10.78-1.60 l A
B B
C D
F G
I 11.81-2.83 l A
B C
D D
E F
I 17.84-3.35 l B
B C
D D
E F
1 13.36-3.86 i B
B C
D D
D E
l 13.87-4.89 l B
C C
D D
D E
l 14.90-5.41 1 C
C D
D D
D E
l 15.42-5.92 i G
G D
D D
D D
I l> 3.u i
c u
D D
D D
D i-4
I, EP-ENY-3F JUN 211983
.. g '
Page 5 of 7 FORM ENY-3F.2.
'.' C '
]
t RELEASE WORKSHEET D TE TIME
=
1 2
3 4
5 6
7 s
(D)
(WS)
(IT)*
l Point of Distance Wind Speed Impact Tine Xu/Q X/Q** m Interest Sector (miles)
(meters /sec)
(minutes)
(meters-2 (sec/ meters 2)
/
\\
w r
l l
s S
- IT = D/WS x 27
- X/Q = (Xu/0)
(W5) e M
e 6
/
%^
4
^~ ~
.. _.... ~.
. ~,,. _, _.
~1'.
l EP-ENV-3F i
nw 211%3
~
MTe' 6 of 7 FORM ENY-3F.3 i
LAKE BREEZE EFFECT WORKSHEET DATE TIME
'l s
I.
Is local wind direction (WDPB - step II.B on Fonn ENY-3F.1) between 20* and 170* clockwise?
No - No Lake Breeze
-Yes - Proceed to step' II s
II.
Is Green Bay wind direction (WDGB - step I.B on Fonn ENY-3F.1) between 210' and
~
330' clockwise?
O No - No Lake Breeze Effect i
Yes - Lake Breeze Effect e
8 6
/
e 1
e h
O 6
--y,--
4 c
___,y,-,
-,-y
m.
.y c
EP-ENV-3F 3 2 1 1983 Page 7 of 7 0
i SUNRISE AND SUNSET AT MEWAUKEEe WISCONSIN No.1322 CENTRAL STANDARD TIME fer.
rts.
MAR.
Al's l 14AY ft:NE I rit.Y A110. I SE3T OCT.
(f.
54 t,
see P=
9 P.
54 -
Em 5,e 24 = %
t-t*
Le f*
M tm 54 h See t,
see AM P M.
AM Pu AM PM A tt PM AM of AM PM AM PM AM PM l AM PM AM PM AM PM AM PM 1
723 428 7 07 5 C4 628 541 5 34 6 17 446 652 415 724 4 16 7 34 442 713I516 627 548 533 626 444 703 419 2
723 429 7 C6 5 05 6 26 5 41 533 619 4 45 e 53 4 15 7 24 4 17 7 34 4 43 712f 5 2',6 25 550 532 627 443 7 C4 6 18 3
723 429 705 537 625 54) 531 620 443 654 415 725 4 17 7 34 4 44 7 11 515 623 551 533 628 442 7 C5 418 4
723 432 7 C4 5 C5 623 544 521621 442 655 4 14 7 26 415 734 445 709 5 19 4 22 552 528 629 443 7 C6 413 5
723 431 7 C3 5 C1 622 546 527 622 441 657 4 14 7 27 413 733 4 46 7 Ca 522 620 553 526 631 439 707 417 6
723 432 701 511 623 547 526 623 439 658 413 727 4 19 7 33 447 707 521 618 5 54 5 25 632 439 7 CS 417 7
723 433 7 C0 512 618 549 5 24 6 24 438 659
+ 13 7 28 420 733 449705 522 616 555 523 633 437 7 C1 4 17 8
723 434 6 59 5 13 6 16 5 49 522 626 4 37 7 C3 4 13 7 29 420 732 4 49 7 04 523 615 556 521 635 436 713 417 9
722 435 655 515 615 550 520 627 4 36 7 01 413721 4 21 7 32 4 51 7 on 524 6 13 5 53 523 6 36 4 35 711 417 10 722 437 6 56 5 16 6 13 % 52 519 628 4.34 7 Ce, 412 730 422 731 4 52 7 01 525 611 559 515 6 37 4 33 712 417
=
11 722 434 655 517 611 553 517 629 463 703 412 733 423 731 453 703 5 26 6 C9 6 C0
- 16 638 432 712 417 12 721 439 6 54 5 19 613 554 515 630 4 32 7 C4 412 731 423 733 4 54 6 59 5 25 6 C8 601 515 640 431 713 417 13 7 ?! 4 43 652 521 6 C3 'S 55 5 14 6 31 431 705 412 731 4 24 7 30 455 657 5 29 6 06 6 C2 5 13 6 41 4 33 7 14 4 17 14 721 441 651 521 6 C6 5 56 512 633 33 7 06 4 12 7 32 425 729 4 56 6 So 5 33 6 C4 6 03 5 11 642 429 715 418 15 720 442 650 52) 6 C4 5 53 510 634 4 29 7 C8 412 732 426 729 457 654 5,31 602 6 C5 510 6 44 4 26 716 418 16 720443 648 528 6 C3 5 59 509 635 4 28 7 C1 4 12 7 33 427 728 4 58 6 53 5 32 6 C3 6 C6 5 C8 645 428 714 418 17 719 445 6 47 5 25 6 Cl 6 00 507 636 4 27 7 10 412 733 427 727 4 59 6 51 533 559 607 506 6 to 4 27 717 419 18 719 446 645 527 5 59 6 C1 5 06 6 37 4 26 7 11 4 12 7 33 421 727 5 CO 6 53 5 34 5 57 6 C3 5 C5 647 426 7 !! 4 19 19 718 447 6 44 5 28 5 57 6 C2 5 04 6 35 425 712 412 733 4 20 7 26 5 O! 6 44 535 555 6 09 5 C3 6 49 4 25 7 IS 419 20 717 443 642 527 5 56 6 C4 5 C2 6 31 4 24 7 13 412 734 433 725 5 C3 6 47 536 553 611 502 653 424 7 19 4 lj 7
21 717 453 641 533 5 54 6 05 501 641 423 714 412 734 431 724 5 04 6 45 537 551 612 503 651 424 719 420 22 716 451 6 39 5 32 5 52 o C6 4 59 6 42 422 715 413 734 432 723 505 643 5 39 5 50 o l) 4 50 652 423 723 423 23 715 452 638 533 5 50 6 C7 418 643, 421 716 413 734 433 722 504642 543 548 6 14 4 57 653 422 723 421 24 7 14 4 14 6 36 5 34 543609 4 56 6 44 4 21 7 17 413 734 4 34 7 21 5 C7 6 40 541 546 616 455 655 422 721 422 25 714, 355
&35 536 5 4 7 6 C1 455 645 420 718 4 14 7 35 415 721 5 C8 6 39 542 544 617 454 656 421 721 422 76 7.13 456 633 537 545 611 453 646 419 714 4 14 7 35 436 720 509 637 543 542 618 453 657 423 722 423
=
27
?12 451'631 5 38 543 612 452 647 4 18 7 19 4 14 7 35 4 37 7 18 5 la 6 35 5 44 5 41 619 451 658 420 722 424 28 711 459 633 539 5 41 6 13 450 649 416 720 415 735 438 717 511 634 545 539 621 450 6 59 4 19 722 424 29 710 5 +0 629 540 540 614 449 653 4 17 7 21 415 735 4 39 7 16 512 632 546 537 622 448 7 C3 419 722 425 30 7 0C S CV 538 615 447 651 417 722 416 734 440 715 513630 547 535 623 447 7 C2 419 723 426 31 7 C8 S E i 536 616 416 723 441 714 515 629 624 446 723 427
. Adi me hour for Do7 ght Sovmg Lme d and when in use.
h 8
v 0
-:l
I g
q
- WISCONSIN PUBLIC SERVICE CORPORATION l NO.
EP-ENV-3G REV. D 1
Kewaunee Nuclear Power Plant l TITLE: Manual Dose Projection l
Calculation EMERGENCY PLAN IMPLEMENTING PROCEDURE I
I l DATE: M 211983 l PAGE 1 of 8 I
.I T
I REVIEWED BY h/h4, ef; p,
APPROVED BY _
,Ms./
('
I I-1.0 APPLICABILITY This procedure will be utilized by the Environmental-Protection Director during any incident that involves a significant release of radioactive materials to the envirorraent, for the purpose of projecting a radiological dose impact.
2.0 PRECAUTIONS 2.1 Ensure all data on the forms of this procedure is accurately recorded.
2.2 Check all calculations for accuracy.
3.0 REFERENCES
3.1 U.S. NRC Regulatory Guide 1.109, Calculation of Annual Doses to Man
[
from Routine Release of Reactor Effluents.for the Purpose of Evaluating Compliance with 10CFR50, Appendix I, Revision 1, October 1977.
3.2 U.S. EPA, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, EPA-520/1-75-001, Septenber 1975. Appendix D Technical Bases for Methods the Estimate the Projected Thyroid Dose and Projected Whole Body Gamma Dose from Exposure to Airborne Radiotodines and Radioactive Noble Gases.
4.0 INSTRUCTIONS 4.1 Whole Body Dose Projection Estimate If the source term is identified by sample results which quantifies specific nuclide content, then a conservative whole body dose estimate may be calculated using form ENY-3G.1, Estimated Whole Body Dose Calculation Worksheet.
4.1.1 Acquire the data needed for Section I of Fonn ENY-3G.1 from the RAF or TSC.
NOTE: Data Needed:
Release rate of Noble gas in (Ci/sec),
actual or estimatea release duration, and X/Q from (91 EP-ENV-3E or 3F.
Me
I I
WISCONSIN PUBLIC SERVICE CORPORATION l
NO.
Kewaunee Nuclear Power Plant i TITLE: Manual Dose Projection h
I Calculation EMERGENCY PLAN IMPLEMENTING PROCEDURE i
t l DATE:
JUN 211983 l PAGE 2 of'8 1
-l 4.1.2 Calculate the Whole Body Dose Projection Estimate using Section II of Fom ENV-3G.1 and the following equation:
D(REM) = X/Q(Sec/m3) x Q(Ci/Sec) x T(hrs) x DF(REM - m3) ci - nrs dere:
D = projected whole b.ody dose estimate (REM)
X/Q = Atmospheric dispersion coefficient determined on Fom ENY-3E.2 or ENY-3F.2 (Sec/m3)
Q = Nuclide equivalent release rate (Ci/Sec) from EP-RET 5 (Flow rate (cc/sec) x conc. (uCi/cc) r.10E-06)
DF- = Whole body C7se conversion factor (REM - m3)
(Ci - hrs)
NOTE: The whole body dose conversion factor is
}
calculated fron NRC Regulatory Guide 1.109, Rev 1, dated October 1977, y
t 4.1.3 Field Sample Analysis Method (Marinelli Beaker of a Field
~
l
' Drawn RAP Sample).
Complete Sections I & II of Fom ENY-3G.2 and the following equation:
D = Is Dose in REM 3
DF = Whole body dose conversion factor (REM - M )
(Gi - hrs)
T = Release duration in hours FC = Field Concentration of specific nuclide in uC/cc as per Gamma Scan result NOTE: A separate Calculation Fom is required for each point of interest.
-Q
l l
WISCONSIN PUBLIC SERVICE CORPORATION I
NO.
Kewaunee Nuclear Power Plant l TITLE: Manual Dose Projection 0'-
c ' c"'
t' "
EMERGENCY PLAN IMPLEMENTING PROCEDURE l
l l DATE:
1 PAGE 3 of 8 I
JUN 211983 l
4.2 Thyroid Dose Projection Estimate If an Iodine Source Term is identified, calculate the projected or estimated dose for each point of interbst by using a separate Form ENY-3G.2 and one of the following methods.
4.2.1 Inplant Sample Met?tod Complete Section I of Form ENY-3G.2 for each point of interest if the release rate of Iodine-131 (Ci/sec) is available for a thyroid dose projection estimate.
4.2.2 Field Sample Analysis Method Complete Section II of Form ENY-3G.3 for each point of interest if the actual measured Iodine-131 airborne concentration (uC/cc) is available for a thyroid dose projection estimate.
This method is also to be used as a backup for the Inplant Sample Method.
NOTE:
This method assumes only Iodine-131 exposure, so it will only be an approximation of the total Iodine dose.
[
4.3 Record all results of Dose Projections by the method used on Form ENY-3A and the field map. Also, report this data to the Radiological Protection Director, Emergency Response Manager, and Technical Support Center Communicator.
4.'4 Proceed to procedure EP-ENV-3H, Protective Action Recanmendation Deter-mination, to determine the appropriate Protective Action Recommendations.
41
~
e O
.Is?3136T~
Page 4 of G FORM ENV-3G.1 EST1 RATED WHOLE BODY DOSE CALCULATION WORKSHEET FOR SPECIFIC NOUEE GAS RELEASE LOCATION: Sector / Point #
DATE TIME I.
Enter data available below:
A.
(Record in Column 1 of section II below) Noble Gas Nuclides release rates (Data is available from the RPD or TSCD)
B.
X/Q as determined and recorded on Form ENV-3E.2 or 3F.2 (Sec/m3}
C.
(Data available from RPD or TSCD) Release Duration (hrs)
I II.
Calculate dose for each nuclide and sum all doses to get total exposure dose by using'the formula below:
Release Rate (REM-m3)
Nuclide (Ci/Sec) x X/Q(Sec/m3). x Release Duration (hrs) x Dose Factor (Ci-hr)
Dose (REM) l
=
Kr-85 l
4 x
x x 1.84 l
=
Kr-85m I
x.
x x 1.34 x 102 I
l Kr-87 1
x x
x 6.76 x 102
=
I Kr-88 1
x x
x 1.68 x 103 I
Xe-133 i
x x
x 3.36 x 101
=
I
~~
Xe-133m l x
x x 2.87 x 101
=
1 Xe-135 l
x x
x 2.06 x 102
=
1 Xe-135m l x
x x 3.56 x 102 4
Signature of Completing TOTAL W110LE BODY Authority and Title (signature)
EXPOSURE DOSE
=
( l i ti e) 6 h
EP-ENY-3G JUN 21 1983 Page 5 of 8 FORM ENY-3G.2 FIELD SAMPLE ANALYSIS METHOD OF WHOLE BODY DOSE CALCULATION LOCATION: Sector / Point #
DATE TIME Section I (Enter data available below)
A.
Record the Field Conctnrrations of Gamma Scan Iddntified Noble Gases in Section II, Column I. -(Data is available from RP0/RAF or TSCD)
B.
Release Duration (actual or estimated)
Section II - Calculate doses for each nuclide and sum all doses to get total exposure dose by using the formula below.
3 Nuclide Fiel d Dose (REM-m )
Release Concentration Factor (Ci-hr)
Duration (hrs)
Dose (REM)
(uC/cc) l Kr-85 l
x 1.84 x
=
l Kr-85m l
x 1.34 x 102 x
l 2'
l Kr-87 l
x 6.76 x 10 x
=
1 Kr-88 l
x 1.68 x 103 x
=
l 1
Xe-133 l
x 3.36 x 10 *
,x
=
1 Xe-133m l x
2.87 x 10I x
=
l Xe-135 i
x 2.06 x 102 x
=
l Xe-135m l x
3.56 x 102 x
Signature of Completing
. TOTAL WHOLE Authori ty and Ti tle (Signature)
BODY DOSE
=
(Titie) tb
..g
o EP-ENY-3 G
.RIN 211983 Page 6 of 8 FORM ENY-3G.3 ESTIMATED Tr$YR0!D DOSE PROJECTION CALCULATION LOCATION:
Sector / Point #
DATE TIME I.
INPLANT SAMPLE METHOD A.
Iodine-131 Release Rates (Ci/sec)
B.
X/Q at the point of interest from Fom ENY-3E.2 or 3F.2 (Sec/m3)
~
C.
Release Duration (Data available from RPD or TSCD)
(hrs)
D.
Calculated Iodine-131 Concentration a't the point of interest.
X/Q(Sec/m3) uC/cc of I-131 Release Rate (Ci/Sec) x
=
uC/cc of I-131 X
=
E.
Detemine Estimated Total Thyroid Dose frcxn Figure ENY-3G. Use the Calculated Iodine-131 Concentration on the X-axis and go vertically up the graph to intersect the appropriate Release Duration line, then read off the_.Y-axis the Estimated Total Thyroid Dose.
Calculated I-131 Concentration vs. Release Duration => Total Thyroid Dose uC/cc vs.
hrs =>
REM I
F.
Multiply Thyroid Dose (in REM) by 2 and make recommendation based on corrected thyroid dose.
Thyroid Dose (from step "E") x 2 = Corrected Thyroid Dose in REM.
REM REM x 2
=
NOTE: EPA Guidelines state that protective action recommendations based on thyroid dose should use the dose calculated for children in the affected population.
0
-q
o o
g, EP-ENV-3G O
g f.11983 age 7 of 8 FORM ENY-3G.3 ESTIMATED THYROID DOSE PROJECTION CALCULATION II. FIELD SAMPLE ANALYSIS METHOD A.
Field Sample Analysis I-131 Concentration at the point of interest uC/cc B.
Release Duration (Data available from the RPD or TSCD)
(hrs)
C.
Detennine Estimated Total Thyroid Dose from Figure ENV-3G. Use the field sample analysis I-131 concentration on the X-axis and go vertically Op the graph to intersect the appropriate Release Duration line, then read off the Y-axis the Estimated Total Thyroid Dose.
Field Sample Analysis
~
Iodine-131 Concentration vs. Release Duration => Total Thyroid Dose uC/cc vs.
hrs =>
REM D.
Multiply Thyroid Dose (in REM) by 2 and make recommendation based on corrected thyroid dose.
Thyroid Dose (fran step "E") x 2 = Corrected Thyroid Dose in REN.
REM x 2
=
i I
NOTE: EPA Guidelines state that protective action recommendations based on' thyroid dose should use the dose calculated for children in the affected population.
COMPLETED BY
~
(Ti t1e) i
~
'N l
l
e EP-ENV-3 C 1
~
juN 211963 Page 8 W )
~
1o, coo 6
. s i. 4Ti i
a i eea..
., r. i
.-:Ttrn-2 2 BASTS ;
~
Dose :1.48 R*=/f.u. men (nb-i484 reew)
~
~
A550Mcb BREA m WG NAE :
6 l x 10 cc/we roe,ip.,ea?. nrautss 1,00 0 2xt07 cc/3a,,
r-es. enewan dM 62.,
1 30 Days G
Q-
'T L'4s I
/
100.0 5
~
x w
cc w N Ic.c, 2.4 \\\\f,_-
l mo i
~
~
l Q O>o
/
/
Z e
W-
~
o we
/
/ ek//
~
tr y lO g 7
[
OH o
-.s 7
- u. <c l
w o
p l-
/
g' g 2 Hr.
i L
l WC EXPOSURE TIME
~
1 l
0.01 THYP,Olb bow buE To INHALATICO f
~
l Or I -131 l
00l
.r..
,,,o, 1
to-s e-e io.
io..
AlffMR n' T-Rt Cm x c?. % W na
[ '%t o L/m )
s (1)' Values are calculated using the old dose conversion for I-1310 The new constant in the reference is 1.5 x 10. However, the old conversion,1.8 x 10, is used for conservatioifl 6
(2) To approximate the child (6 months to one year worst case) thyroid dose from the adult dose multiply it by a factor of 2
0 l
WISCONSIN PUBLIC SERVICE NRPORATION l NO.
EP-ENV-3H REV. B I
Kewaunee Nuclear Power Plant l TITLE: Protective Action Recommendations l
EMERGENCY PLAN IMPLEMENTING PROCEDURE l
l l DATE:
l PAGE 1 of 6 l
JUN P 11983 1
REVIEWED BY ////rAc.40 4[
l APPROVED BY 8[.39.hl:*
(
l 1.0 APPLICABILITY This procedure applies to all emergency situations when environmental monitoring and dose assessment is necessary, and Environmental Monitoring Teams have been di spatched.
2.0 PRECAUTIONS l
2.1 Accurate recording of data acquired fra the Radiological Protection Director (RPD) or Environmental Monitoring Team (EMT) Coordinator is es se ntial.
2.2 All conclusion ~s drawn fran enviromental data must be accurately docunented.
3.0 REFERENCES
l None l
4.0 INSTRUCTIONS 4.1 Short Term Protective Action Determinations l
l 4.1.1 Obtain the printer output or completed data sheets and worksheets for the dose projection and field sample evaluations.
4.1. 2 Compare these results for all points of interest to TABLES ENV-3H.1 as follows:
i TABLE ENY-3H.1:
Take the projected Dose (s) and enter the chart at the appropriate level by projected Doses listed in the lef t hand column. Read across fran the Doses and obtain the corres-ponding Recommended Actions and cmments.
NOTE:
EPA guidelines state that protective action recommendations should be based on the projected chil d thyroid dose.
V
-gl 1
I WISCONSIN PUBLIC SERVICE CORPORATION l NO. EP-ENY-3H I
Kewaunee Nuclear Power Plant i TITLE: Protective Action Recommendations I
- h EMERGE!CY PLAN IMPLEMENTING PROCEDURE l
l l DATE: JUN 211983 l PAGE 2 of 6 I
I 4.1.3 Record the impact times on the Field Maps at the points of interes t.
4.1.4 Evaluate the impact time, plant conditions (past, present and future), weather conditions, and evacuation time estimates, and detemine the most beneficial and appropriate Protective Actions the public can take to reduce their exposure.
4.1.5 Verify previous recommendations, if any are still valid, for any new data that is now available.
4.1.6 Report Protective Action Recommendations to the Emergency Response Manager.
4.1.7 Repeat steps 4.1.2 through 4.1.6 as necessary as new infomation is received from the Environmental Monitor.ing Teams.
4.2 Long Term Protective Action Determinations 0..
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- 4. 2.1 Obtain data from the results of ground deposition samples reported by the Environmental Consultant.
4.2.2 Compare these results to Tabl'e ENY-3H.2 to datermine the f
i appropriate Protective Action Recommendations as follows.
Table ENY-3H.2:
Section I, Part A: Compare the projected dose above ground, Ground Contamination level measurements, or exposure rates 1 meter above ground and at or above these base limits proceed to Part B for the Recommended Protective Actions.
Section II, Part A: Evaluate the results of the Environmental
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Consultant. The results of a specific nuclide concentration (I-131, Cs-137, Sr-90, and/or Sr-89) and the medium in which it was obtained are listed for comparison against the reported resul ts. For example, if a milk analysis was reported by the Environmental Consultant at 0.012 uc/mi of I-131, proceed to the I-131 column under the heading Nuclide. Then read to the right for the Action Levels and concentrtion in Milk & Water Preventive or Emergency Levels, and cmpare the levels to the reported result.
If the Reported result is less than the preventive level, no protective action is necessary.
If the results are higher than the preventive or Emergency level, then proceed to the next page and recommend the listed protective l
action recommendations, as in the example, the recommendations
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under preventive level.
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I WISCONSIN PUBLIC SERVICE CORPORATION l NO. EP-ENY-3H l
Kewaunee Nuclear Power Plant l TITLE: Protective Action Recommendations I
(])
EMERGENCY PLAN IMPLEMENTING PROCEDURE l
1 l DATE:
1 JUN 211963 l PAGE 3 of 6 1
4.2.3 Record Protective Action Recomnendations in EPD Log Book.
4.2.4 Report Protective Action Recanmendations to the Emergency Response Manager.
4.2.5 Repeat steps 4.2.1 through 4.2.4 as necessary as new information is received from the Environmental Consultant.
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Page 4 of 6 1
TABLE ENV-3H.1 RECOMMENDED PROTECTIVE ACTIONS TO REDUCE WHOLE BODY i
OUS PLUME i
i Projected Dose (Rem) to Individual in General Public Recommended Actions (a) i Whole body
<1 Comments No planned Protective Actions.(b) or Thyroid
<5 State may issue an advisory to seek Previously recommended shelter and await further instructions.
Protective Actions niay Monitor environmental radiation levels.
be reconsidered or terminated.
Whole body 1 to < 5
. Seek shelter as a minimum.
i or Consider evacuation.
Evacuate unless If constraints exist, special Thyroid 5 to < 25 cons traints make it impractical.
consideration should be given Monitor environmental radiation levels.
for evacuation of children and Control access to the affected area.
pregnant women.
Whole body 5 and above Conduct mandatory evacuation..
or j
Thyroid 25 and above Monitor environmental radiation levels Seeki.ng shelter would be an and adjust area for mandatory alternative if evacuation evacuation based on these levels.
were not immediately possible.
Control access to the affected areas.
(a) These actions are recommended for planning purposes incident must take existing conditions into consideration. Protective Action decisions at the time of the (b) At the time of the incident, officials may implement low im principle of maintaining radiation exposure as low as reasonably achievablepact Protective Actions in ke j
i
Reference:
Manual of Protective Action Guides and Protective Actions for Nuclear Incide j
EPA-520/1-75-001, September 1975, U.S. Environmental Protection Agency i
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EP-ENV-3H hoPb Pa
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TABLE ENY-3H.2 GUIDELINES FOR PROTECTION AGAINST INGESTION OF CONTAMINA 1.
GROUND CONTAMINATION A.
Action Levels 1.
Projected whole-body dose above the ground > 1 REM.
2.
Ground Contamination levels > 4.4 x 107 DPM/100cm2 at t = 1 hr post-accident 3.
Exposure rate >l2 mR/hr at 1 meter above ground at t = 1 hr post-accident 8.
Recommended Protective Actions 1.
Evacuation of affected areas.
2.
Restriction of entry to contaminated offsite areas until radiation level has decreased to State approved levels.
II.
FOOD AND WATER CONTAMINATION
]
A.
Action Levels Preventive Level: 0.5 REM WB or bone,1.5 REM thyroid Energency Level: 5 REM WB or bone,15 REM thyroid Concentration in Total Intake via all Pasture Grass Milk or Water Food and Water Pathways (Fresh Weight) i Preventive Emergency Preventive E'mergency Preventive Emergency Level Level Level Level Level Level Nuclide*
(_uCi/1)
(_ uCi/1)
(uCi)
(uCi)
(_ uCi/kg)
(uCi/kg) 1-131 (thyroid) 0.012 0.12 0.09 0.9 0.27 2.7 Cs-137 (whole body) 0.34 3.4 7
70 3.5 35 Sr-90 (bone) 0.007 0.08 0.2 2.0 0.7 7
Sr-89 (bone) 0.13 1.3 2.6 26 13 130 0
If other nuclides are present, Reg. Guide 1.109 will be used to calculate the dose to the critical organ (s).
Infants are the critical segment of the population.
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EP-ENV-3H JUN 211983 Page 6 of 6 0
TABLE ENY-3H.2 (cont'd)
GUIDELINES FOR PROTECTION AGAINST INGESTION OF CONTAMINATION RECOMMENDED PROTECTIVE ACTIONS Preventive Level Emergency 1.
Removal of lactating dairy cows from Isolate feed and water from its contaminated pasture and substitution introduction into commerce after of uncontaminated stored feed.
consi deri ng:
2.
Substitute source of uncontaminated a.
availability of other possible wate r.
actions; 3.
Withhold contaminated milk from market b.
importance of particular food
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to allow radioactive decay, in nutrition;
}'
4 Divert fluid milk to production of dry whole milk, butter, e tc.
time and effort to take action; c.
d.
availability of other foods.
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References U.S. Food and Drug Administration, 21 CFR Part 1090, Federal Register, Vol. 43, No. 242, Dec.15,1978.
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I WISCONSIN PUBLIC SERVICE CORPORATION l
NO.
-EP-RET-3D REY. A 4
1 Kewaunce Nuclear Power Plant l
TITLE : Containment Air Sampling I
Analysis Using CASF
- .MERGENCY PLAN IMPLEMENTING PROCEDURE 1
l l DATE:
JUN 211983 l PAGE 1 of 6 I
I l
REVIEWED BY W=w APPROVED _B.Y
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in a'wau l
l 1.0 PURPOSE Containment samples will be drawn and analyzed following an Alert, Site, or General Emergency, or when directed by the ' Radiation Protection Director (RPD).
I 2.0 APPLICABILITY 2.1 This procedure is to detail the requirements, considerations, and operations I
of the Containment Air Sample Panel (C.A.S.P.) during a post LOCA condition, I
to obtain a grab sample of containment air for gross gas analysis, Iodine analysis, and oxygen analysis.
3.0 PRECAUTIONS _
3.1 Process an Emergency Radiation Work Pennit (see EP-AD-il) 3.2 Contact Health Physics Dept. for:
a.
Proper personnel dosimetry b.
Proper radiation detection instrumentation I
c.
Personnel for continuous HP coverage during sampling d.
Remote aiea monitor readings in area of HRSR.
3.3 Utilize onsite communications with the Radiological Protection Director'as necessary, during sampling.
3.4 Any sample drawn from the post accident containment atmosphere should be assumed to contain specific activity of the following magnitude:
GAS 5.0 Millicuries /cc IODINE 0.2 Millicuries /cc 4.0 EQUIPMENT All necessary equipment shall be on hand prior to beginning to sample the containment atmosphere. This equipnent includes:
4.1 Operable C.A.S.P. Systen with ISC Cart in #1 Sample Station 4.2 A 5.0 microliter gas syringe (2) 4.3 a 1.0 cc gas syringe 4.4 An iodine cartridge holder (1) 4
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l
., WISCONSIN PUBLIC SERVICE CORPORATION l
NO.
Kewaunee Nuclear Power Plant l
TITLE : Containment Air Sampling l
Analysis Using CASP t h EMERGENCY PLAN IMPLEMENTING PROCEDURE l
l l PAGE 2 of 6 l DATE:
JUN 211983 l
I o
4.5 Silver Zeolite Cartridges (1) 4.6 Several small rubber stoppers (3-4) 4.7 Portable shields for use when transporting syringes for counting.
4.8 A 4.0 liter Marinelli Beaker (in Count Room) 5.0 PROCEDURE 5.1 Containment Air Sample Panel Operation 5.1.1 Proceed to HRSR per HP/RPD reconmendations.
5.1.2 Check ventilation on and in "nonnal" position and high vacuun lights indicate "nornal" for the LSP and CAP, and CASP. Check valve lineup per Attachment 1.
5.1. 3 Check radiation levels in HRSR and in maintenance area behind panels if access is required.
O 5.1.4 Insure that N2 supply regulator is set at 150 PSI and bottle contains at least 500 psig N -
[
2 5.1. 5 Verify that CASP and CASP Control Panels are energized and I
ope ratio nal. Ensure that the heat tracing is on.
5.1.6 Check the ISC sample cart in the #1 position and lock in place.
Check cart is properly locked in by trying to pull away.
NOTE: 'Only Sample Station 1 should be used for Iodine Analysis.
5.1. 7 Call Control Room and verify Dome Fans 1 A and 18 are operational.
l 5.1. 8 Have Control Room Operator open 1 set of the following valves:
Loop A Loop B l
i LOCA-2A LOC A-2B l
LOCA-10A LOCA-108 l
5.1. 9 Insure that when selecting sample loop A or B that either I
hydrogen monitor is not operating or loop selected is opposite l
l that being used by H2 monitor. Open AS110A or AS110B.
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6 s
WISCONSIN PUBLIC SERVICE CORPORATION l
NO.
Kewaunee Nuclear Power Plant l
TITLE : Containnent Air Sampling
'l Analysis Using CASP
@Wr EMERGENCY PLAN IMPLEMENTING PROCEDURE l
l i DATE:
JUN 211983 i PAGE 3 of 6 1
1 5.1.10 CASP two minute pre-sample back flush SV-10 OPEN SV-6 OPEN SV-5 OPEN Insure flow monitor on CASP is indicating flow 5.1.11 Three minute sample purge:
t AY-1/SV 1.2 Open SV-5 Cl osed AV-2 Open l
Open manual inlet, (V-4) and outlet (V-6) valves and close manual l
bypass valve (V-5) on I.S.C.
Insure CASP Flow Monitor is indicating I
fl ow.
5.2 Sample Collection l
5.2.1 SV-6 Closed.. Flow Monitor on CASP should go out.
Wait 1 minute O.
1 for pressure equalization.
r 5.2.2 Withdraw a one cc sample and two 5 microliter samples of the contain-ment atmosphere from the I.S.C. and place them in a portable shield l
for transport to the count room.
Insert the needle of each syringe into a small rubber stopper to prevent leakage.
5.2.3 Using a predetennined route to minimize personnel exposure, transport the shielded samples to the count room for' analysis, after completing Step 5.3 5.3 System Shutdown and Cleanout l
5.3.1 Shut AS110A or AS1108.
l 1
5.3.2 Open SV-6, to evacuate the I.S.C. cart for 2 minutes.
5.3.3 Shut I.S.C. cart iniet yalve (V-4) and outlet valve V-5.
Open i
bypass valves (V-6).
5.3.4 Open AS110A or AS110B and shut AY-2.
Continue this backflush for H
2 minutes. F1ow monitor should indicate flow.
i 5.3.5 Open SV-5, shut AV-1/SV1.2. Continue this backflush for 1 minute.
I Flow monitor should indicate flow.
hI I
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I WISCONSIN PUBLIC SERVICE CORPORATION l
NO.
EP-RET-30 I_
Kewaunee Nuclear Power Plant l
TITLE: Contaiment Air Sampling l
Analysis Using CASP j
EMEP.GENCY PLAN IMPLEMENTING PROCEDURE I
i l DATE:
M 211983 lPAGE 4 of 6 l
5.3.6 Shut SV-10, SV-6, SV-5, and AS110A or AS1108.
5.3.7 Call Control Room and have containment isolation valves selected I
in step 5.1.8 closed.
CAUTION: Make'sure correct set is closed to avoid damaging hydrogen moni tors.
l 5.3.8 Af ter cart is flushed, reset " Active / Inactive" indicator lights to Inactive mode.
5.4 Gross Gas Analysis 5.4.1 Perform b'ackground radiation surveys in the count roon and ensure that the multi-channel analyzer (MCA) is operable.
5.4.2 Place a Marinelli beaker on the GeLi detector and run a 5 minute background count. Record the % dead time indication.
l 5.4.3 Af ter the background count, remove the Marinelli from the count cave and inject 5 microliters of sample into it.
Replace on the GeLi and count for one minute using the standard Marinelli Q>T table. Expected results are approxistely 5.0 E - 3uCi/cc for Xe-133 at 5% dead time f
under negligible background radiation conditions.
5.4.4 Dilution factor when injecting 5.0 microliters into a 4.0 liter Marinelli is 8.0 E + 5.
Detemine gaseous isotopes using the following fomula:
(Printout Activi ty'.
(8.0 E + 5) = in Containment Gaseous Activity in uCi/cc )
x
'in uCi/cc l
5.4.5 If the count room is uninhabitable or if the multi-channel analyzer is saturated fraa background radiation and inoperable, the sample m<v have to be sent to Point Beach for counting.
In this case, instead of injecting the 5.0 microliters of sample into a Marinelli beaker, inject it into a 1.0 liter poly bottle. The bottle may then be counted for gross gas activity at Point Beach in the liter bottle geomtry.
If this is done, use a dilution factor of 2.0 E + 5 to detemine actual activity in containment.
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1 WISCONSIN PUBLIC SERVICE CORPORATION 1
NO.
Kewaunee Nuclear Power Plant l
TITLE : Containment Air Sampling l
Analysis Using CASP
- EMERGENCY PLAN IMPLEMENTING PROCEDURE l
l
~
l DATE:
l PAGE 5 of 6 l
JUN 211983 l
5.5 Iodine Analysis 5.5.1 Place a Silver Zeolite sample cartridge in a holder. Attach a hose from the holder to a vacuum source and establish air flow through the filter cartridge.
5.5.2 Inject 5.0 microliters of the samples gas upstream of the filter cartridge allowing the gas to flow through the Silver Zeolite cartridge.
5.5.3 Remove the Silver Zeolite cartridge from its holder and monitor it for radiation.
5.5.4 Insert the CESCO NFRU Q>T table on the MCA.
5.5.5 Run a 5 minute background count on the MCA.
5.5.6 Place the Sihver Zeolite cartridge on the GeLi detector and perfonn a one minute sample count. Activity results will be in uCi/cc times 1.00 E-6.
5.5.7 If the count roon is inaccessible, the cartridge may be sent to Point Beach for analysis. They use an identical geometry for e'
counting iodine samples.
'l 5.6 Hydrogen a'nd Oxygen Analyses l
5.6.1 Refer to chemistry procedure RC-C-61, Operation of the Gas Partitioner.
5.6.2 Ensure that the gas partitioner is turned on, the Argon flow is 30-35 cc/ min., the cell power switch is on, and the heater switch and chart recorder are on.
5.6.3 Once everything is set up on the gas partitioner inject the contents of the 1.0,cc syringe into the gas partitioner and await results on the chart recorder.
5.6.4 Report all results obtained to the Radiological Protection Director.
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<4 JUN 211983 Page 6 of 6 VALVE LINEUP SHEET CASP Control Panel AV-1/SV-1.2 Smpi Pos #1 Inlet /Outl et CLOSE SV-2.1/SV-2.2 Sapl Pos #2 Inlet / Outlet CLOSE SV-3.1/SV-3.2 Smpi Pos #3 Inlet / Outlet CLOSE
,SV-4.1/SV-4.2 Smpl Pos #4 Inlet / Outlet
. CLOSE SV-5 Smpi Bypass CLOSE SV-10 Nitrogen to Eductor CLOSE AY-2 Return to Containment CLOSE SV-6 Eductor Suction Iso CLOSE (At Sample Acquisition Panel) l AS110A Cont Air Smpl A Isol CLOSE hl AS110B Cont Air Smpi B Isol CLOSE O
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