ML20065A059
| ML20065A059 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/02/1983 |
| From: | INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML17320A373 | List: |
| References | |
| PROC-830202-01, NUDOCS 8302180042 | |
| Download: ML20065A059 (26) | |
Text
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ELECTRIC COMPANY c',
DONALD C. COOK NUCLEAR PLANT O
Instruction or Procedure Temporary Sheet
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This temporary sheet applies to 0FF-SITE DOSE ASSESSMENTS Instruction or Procedure No. PMP 2081.EPP.014 K4 vision No. 1 TP-1 The following change ( X )
new requirement (
)
shall be NI b instituted effective (Date) 25 January, 1983 Replace the following pages as indicated:
List of Effective Pages, Page 1 of 2, Revision 1 with Revision 1, TP-1 List of Effective Pages, Page 2 of 2, Revision 1 with Revision 1, TP-1 Page 2 of 7, Revision 1 with Revision 1, TP-1 Page 3 of 7, Revision 1 with Revision 1, TP-1 Page 5 of 7, Revision 1 with Revision 1, TP-1 Fage 7 of 7, Revision 1 with Revision 1, TP-1 Add the following pages:
h EXHIBIT C, Revision 1, TP-1 FEB0S M EXHIBIT X, Revision 1, TP-1 EXHIBIT Y, Revision 1, TP-1
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O REASON FOR CHANGE: Changes were made in response to NRC - Identified Weaknesses in the Emergency Plan involving the incorporation of evacua-tion time estimates into the decision-making process for protective action recommendations.
Ea.
This change should be made a permanent revision to the Instruction or Procedure:
c')o a)Q CXVES ONO a NOT KNOWN, additional review required OO Expiration Cate:
PROCEDURE REVISION Standard Dist. List No.:
5 Originator: N/1AAL d. M<&WV7A Distribution:
OE Managenent Staf F:_. O M/E#l/AU '
Senior Reactor Operator: M MAppl[Arct/
PNSRC E!b1hd5 6te Of /-P3 ([
Plant Manager C!M9deJ rgt, _7,/--pa V Form No. 433[
Rzvtszo 7tra wurTz
- ORIGINAL CANARY - ORIGINATOR COP 1r PINK
- WORKING COPY FORM ho. PMI 201N Rzv. 2
v LIST OF' EFFECTIVE PAGES Pace Number Revision Number and Date 1 of 7 Revision 1 - Oct.12, 1982 2 of 7 Revision 1 - TP-1 3 of 7 Revision 1 - TP-1 4 of 7 Revision 1 - Oct.12, 1982 5 of 7 Revision 1 - TP-1 6 of 7 Revision 1 - Oct.12, 1982 7 of 7 Revision 1 - TP-1 EXHIBIT A. Page 1 of 1 Revision 1 - Oct.12,1982 EXHIBIT B, Page 1 of 1 Does not Exist E7HIBIT C, Page 1 of 1 Revision 1 - TP-1 EXHIBIT D, Page 1 of 1 Revision 1 - Oct.12,1982 EXHIBIT E, Page 1 of 4 Revision 1 - Oct.12, 1982 Page 2 of 4 Revision 1 - Oct.12, 1982
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Page 3 of 4 Revision 1 - Oct.12,1982 Page 4 of 4 Revision 1 - Oct.12,1982 EXHIBIT F, Page 1 of 1 Revision 1 - Oct.12,1982 EXHIBIT G, Page 1 of 1 Revision 1 - Oct.12,1982 EXHIBIT H, Page 1 of 2 Revision 1 - Oct.12, 1982 Page 2 of 2 Revision 1 - Oct.12,1982 ATTACHMENT I, Page 1 of 1 Revision 1 - Oct.12, 1982 EXHIBIT I, Page 1 of 1 Revision 1 - Oct.12, 1982 EXHIBIT J Page 1 of 2 Revision 1 - Oct.12, 1982 Page 2 of 2 Revision 1 - Oct.12, 1982 u
EXHIBIT K. Page 1 of 1 Revision 1 - Oct.12, 1982 EXH EIT L, Page 1 of 1 Revision 1 - Oct.12,1982 EXHIBIT M, Page 1 of 1 Revision 1 - Oct.12, 1982 EXHIBIT N, Page 1 of 1 Revision 1 - Oct.12, 1982 EXHIBIT 0, Page 1 of 1 Revision 1 - Oct.12, 1982 EXHIBIT P, Page 1 of 1 Revision. 1 - Oct.12, 1982 EXHIBIT Q, Page 1 of 1 Revision 1 - Oct.12,1982 EXHIDIT R, Page 1 of 1 Revision 1 Oct.12, 1982 Page 1 of 2 Revision 1, TP-1
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LIST OF EFFECTIVE PAGES Page Number Revision Number and Date EXHIBIT S, Page 1 of 1 Revision 1 - Oct.12,1982
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-l EXHIBIT T Page 1 of 1 Revision 1 - Oct.12,1982
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EXHIBIT U, Page 1 of 1 Revision 1 - Oct.12,1962 EXHIBIT V, Page 1 of 1 Revision 1 - Oct.12,1982 EXHIBIT W, Page 1 of 1 Revision 1 - Oct.12,1982 EXHIBIT X, Page 1 of 1 Revision 1 - TP-1 EXHIBIT Y Page 1 of i Revision 1 - TP-1 o
Page 2 of 2 Revision 1, TP-1
4.0 INSTRUCTIONS NOTE: Initial dose t.stimates may be made by PMP 2080.EPP.006 or by the use of the AEPSC computer programs CPM 002 or MIDAS.
4.1 The RAD shall perform the following functions and record all data on the appropriate exhibits:
4.1.1 Determine the Pasquill Category and record meteorological
[TP-1 data on Exhibit C of PMP 2081 EPP.020.
4 4.1.1-1 If meteorological data is available from the computer, obtain and record Pasquill Category, wind speed and direction, aT and precipiptation on Exhibit C of PMP 2081 EPP.020.
l TP-1 4.1.1-2 If meteorological data is not available from the computer, obtain it from Exhibit B, the Technical Information Sheet.
4.1.1-3 To determine Pasquill Category using AT infor-mation. use the following guide:
Pasquill AT= (T,180ft-T,30f t),UC C/100m Category U
-0.87
-1.9 A
Os
-0.87 to -0.78
-1.9 to -1.7 8
-0.78 to -0.68
-1.7 to -1.5 C
-0.68 to -0.23
-1.5 to -0.5 D
-0.23 to 0.68
-0.5 to 1.5 2
0.66 to 1.83 1.5 to 4.0 F
1.83 and above 4.0 and above G
4.1.1-4 If information about AT is unavailable from meteorological tower or Exhibit 5, Pasquill Cat.egory may be estimated using this chart:
Sunny Cloudy Cloudy Clear Day
_ D_ay___
Night Night light wind or c' alm (<9.8 mph)
B C
E F
moderate, strong wind (<9.8 mph)
C D
D D
4.1.2 Completc the lower two-thirds of information on Exhibit C of PMP 2081 EP?.020 (from Basis for Projected Dose l TP-1 onward). This includes calculation of dose rates and projected doses to whola body and thyroid as well as making recommendations for support or emergency actions e
based on this data. Also complete Exhibit C of this
(_)
procedure and use this information in making protective TP,1 action recommendations.
Page 2 of 7 Revision 1, TP-1
!O 4.1.3 Coordinate information being used to complete each TP-1 Exhibit C, previously described, in the TSC and E0F as the transition from TSC to EOF is made using Exhibit A, Off-Site Dose Assessment: EOF /TSC Coordination Checklist.
4.2 Calculation of dose rates and projected doses to the whole body and thyroid is performed using the method outlined below:
NOTE:
Reference for details of using the hand calculator pro-
,j gram is Exhibit E, Off-Site Dose Program.
Flow sheet 1
for this program is Exhibit F, Off-Site Dose Program Flow Sheet.
i; 4.2.1 Load both sides of both program cards.
4.2.2 Entar the program by specifying the Pasquill Category.
l TP-1 4.2.3 When 610 appears, specify boundary distance in meters.
R/S 4.2.4 When 0.01 appears, specify wind speed in mph. R/S I
4.2.5 When 0. appears, enter release rate in Ci/sec. R/S (For details on calculating release rates, see Exhibit E).
O 4.2.6 when 2. appears, enter release classification (as de-fined in Exhibit G).
If classification is 7, Isotopic Mixture program, Exhibit H should be used. R/S 4.2.7 Read whole cody (thyroid) dose rate at site boundary.
R/S 4.2.8 After site boundary distance flashes, read whole body (thyroid) dose rate at site boundary. Record this value for Dose Rate, R/hr, on Exhiait C, Accident :nformation Reporting Data Sheet.
Record values to three significant figures; if values are <0.001, record as "<0.001".
R/S 4.2.9 After 2 (representing 2 miles) flashes, read and record values as described in 4.2.8.
R/S 4.2.10 Repeat step 4.2.9 for distances of 5 and 10 miles. R/S 4.2.11 When 15. appears, specify exposure time in minutes. R/S 4.7_.12 Read whole body (thyroid) boundary dose for this case.
R/S 4.2.13 Read whole body (thyroid) dose at boundary integrated from beginning of event. Record values on Exhibit D, Integrated Dose and Projected Dose Worksheet. R/S s
I; d hge 3 of 7 j
Revision 1, TP-1
,4
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To reset integrated doses to zero in both registers, press GTO, then CLR. When numbers ".ppear in the display, press D and go to step 4.2.13.
4.2.22-If. classification in 4.2.6 is entered as 7, the number 0.04249 will appear. The program, Isotopic Mixture (Exhibit H and I), is to be used according to instruc-tions contained therein. For more details. refer to Exhibit E.
.1 NOTE:
If meteorological conditions change, the program can be restarted at step 4.2.2 without
- J losing any integrated dose data. -Any time the it calculator is not con uting, the program may j
be redirected or restarted by pressing any of the user-defined keys-(A-E or A'-E') without losing integrated dose totals.
4.2.23 If evacuation is suggested, project the most recently calculated dose rate (start at 4.2.7) or dose (start at 4.2.12) out for the i.stimated time required for evacuation 7p.)
(Exhibit Y) by entering that time (in minutes) at step 4.2.14.
The value of projected dose obtained could then be said to be that which would be received by the last individual to be evacuated from the area.
4.3 Definition of Exhibits O
NOTE:
Other pertinent information that may be required for analysis or decision taking may be found in the Radia-tion Assessment Director (RAD) Data Book.
4.3.1 Exhibit A: Off-Site Dose Assessment: EOF /TSC Coordina-tion Checklist This is for use during the transition of operations from i.
It is used to ensure that the same-information is being used as the basis for calculations of dose rate and dose in both the TSC and the E0F.
4.3.2 Exhibit B: Technical Information Sheet l:
The Dose Parameters section of this sheet is used to obtain meteorological and release data essential for use with the hand calculator and/or CPM 002 programs.for dose rate calculation.
I 4.3.3 Exhibit C: Protective Action Recommendation Data Sheets I
l-Data concerning evacuation times and associated dose and C
risk projections on this sheet are to be used by the Radiation Assessment Director in recommending protective TP-1 actions. Space is provided for making protective action recommendations for population, workers and livestock /
l,
agricultural products.
O 4.3.4 Exhibit D:
Integrated Dose and Projected Dose Worksheet This is to function as a worksheet for recording the 3
values for whole body and thyroid dose at the site boundary integrated from the beginning of event.
Page 5 of 7
_ __._ Revision l, TP-1
O 4.3.17 Exhibit Q: Graph of radiation levels at 6 inches from Unit i Gland Seal Exhaust line, R/hr, vs. release rate, Ci/sec 01 cfm.
4.3.18 Exhibit R: Graph of radiation levels at 6 inches from j
Unit 2 SJAE line, R/hr, vs. release rate, C1/sec 01 cfm.
4.3.19 Exhibit S: Graphs of radiation levels ht 6 inches from Unit 2 Gland Seal Exhaust line, R/hr, vs. release rate, Ci/sec 0 1 cfm.
4.3.20 Exhibit T: Recommendg Protective Ac' lons for Popula-tion and Workers For use with Exhibit C for detemining recomnded pro-tective actions.
4.3.21 Exhibit U:
flap of Donald C. Cook Nuclear Plant Site For use with Exhibits J and K for detemining sampling site locations.
4.3.22 Exhibit V: Description of Sampling Site locations For use with Exhibit U for obtaining geographical data of sampling sites.
O 4.3.23 Exhibit w: riein Stee Svstem Emergencv Reieese Detemination For use in detemining release rate when given a reading in R/hr at a sampling location. Use in conjunction with Exhibit E.
4.3.24 Exhibit X: flap of Berrien County with Sectors For use with Exhibit Y in detemining projected dose during evacuations of 45' sectors.
TP-1 4.3.25 Exhibit Y:
Estimated Evacuation Times for Sectors B-L of Berrien County for 2, 5 and 10 Miles J
For use with Exhibit X in detemining projected dose during evacuations of 45 sectors of Berrien County under favorable and adverse conditions.
O Page 7 of 7 Revision 1, TP-1
'i EXHIBIT C i
RADIATION PROTECTION RECOM4ENDATIONS FOR PROTECTIVE ACTIONS
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TO POPULATION:
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TO WORKERS:
i TO LIVESTOCK / AGRICULTURAL PRODUCTS:
ADDITIONAL BASIS FOR RECOMMENDATIONS & PROJECTED DOSE OUT TO CONDITIONS ESTIMATED ESTIMATED-SECTOR (S)
(DISTANCE (FAV. OR EVACUATION EXPOSURE SPECIAL CONSIDERATIONS IN MILES)
ADV.)
TIME FROM EVAC.
2 O
ADDITIONAL COMMENTS OR R.P. INFORMATION:
3 d
L O.
Page 1 of 1 Revision 1, TP-1 i
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- Information obtained'from Attachments' to Appendix 1 of the Berrien County Basic Plan.
- Page 1 of 1 l
Revision 1, TP-1 t
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p PMP 2081.EPP.014-I, EXHIBIT Y
?i ESTIMATED EVACUATION TIME-
.O; s
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NOTE: Times are shown in hours: minutes. Times in parentheses are in minutes as a convenience for. calculations.
s j
2 Miles 5 Miles 10 Miles Sectors J-Favorable Adverse Favorable Adverse Favorable Adverse BC
- 50 1:20 2:05 4:20 5:10 8:35 (50)
(8G)
(125)
(260)
(310)
(51 5)
)
- 80 1:40 1:45 2:10 3:20 4:05 (80)
(100)
(105)
(130)
(200)
.(245)
FG 1:20' 1:40 1:45 2:30
'2:55 4:35 (80)
(100)~
(105)
(150).
.(175)
(275)
HJ 1:20 1:20 1:40 2:35 3:25 4:25 i
(80)
(80)
(100)
(155)
(205)
-(265)
K 1:00 1:25 1:25 2:35 3:05 4:35 (60)
(85)
(85)
.(155)
(185)
(275)
BCDE 1:40 2:20 3:15 5:45 5:55 7:35 (100)
(140)
(195)
(345)'
(355)
.(455)
'FGHJ 1:50 2:50 3:00 4:20 5:40 7:05 1
(110) -
-(170)
(180)
(260)
(340)
(425)
!O 8C0eFGHJ 4:05 4:30-5:40 e:20 e:05 7:50
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(245)
(270)
(340)
(380)
(365)
(470)
Special Considerations
-BC Memorial Hospital; Oles Homestead for the Aged; Park Wayne Manor; Shoreham Terrace DE Fancher Adult Foster Care FG Gateway, Inc.
HJ Bethany Retirement Home; Jordan's Rest Home; Lake Valley Adult Foster Care K
Warren Dur.es This information originated from Attachments 29, 31, 33, 35 and 37 to Appendix 1
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of the Berrien County Basic Plan.
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Pase 1 of i Revision 1,-TP-1
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~ bs INDIANA & MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT PLANT MANAGER PROCEDURE Index identification Revision No.I Cc:rrents Tid e Number And Date l l
PMP 2091 EPP.001 Emergency Telephone Rev. 1 Commu,11 cations 6-24-32 EPP.002 Sarring of the PABX Revision 1 6-29-82 EPP.003 Follow-Up Off-Site Revision 1 Communications 11-16-82 EPP.004 Drotective Action Guides Revision 1 (PAGs) and Protective Actions 9-28-82 O
Eee 005 eersonnel gyacuation Revision 1 5-25-82 EPP.006 Activation of the Reentry Revision 1 and Rescue Team 9-28-82 EPP.007 Security Actions Durin9 Revision 1 Emergency Conditions 5-5-82 EPP.008 Emerger y Medical Plan Revision 1 TP-1,11-30-82 Exp NA Guidelines 9-28-82 EPP.009 Health Physics Procedures Revision 1 i
9-29-82 3
EPP.010 Activation of Radiation Revision 1 Monitorir.g Teams 2-1-83 EPP.011 On-Site Radiological Revision 0 Monitoring 4-1-81 EPP.012 Off-Site Radiological Revision 1 TP-1,1-25-83 Exo NA Monitoring 9-8-82 EPP.013 Environmental Monitoring Revision 0 TP-1,2-25-82 Exp N/A and Analysis 4-1-81 0
Page.2 Rev. Da ta $2 *.-2 2.3
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PPP EPP INDEX
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INDIANA & I4ICHIGAN POWER COMPANY CONALD C. COOK NUCLEAR PLANT PLANT MANAGER PROCEDURE Index
]
Identification evision N.!
Title Ccmments Numbor And Date l_ -
l PMP 2081 EPP.014 Off-Site Dose Assessments Revisioni1
'TP-1,1-25-83 Exp. NA 10-12-82 EPP.015 Sampling and Analysis of Revision 0 Waterborne Releases 4-1-81 EPP.016 Collection and Analysis of Revision 0 Liquid and Gaseous Samples 4-1-81 EPP.017 Interpretation of Liquid Revision 0 and Gaseous Samples 4 l-81 T
EPP.018 Transportation Accidents Revision 1 (wJ Involving Radioactive 6-24-82 Material EPP.019 AEP Emergency Response Revision 0 Organization Activation and 4-1-83 1
Management EPP.020 Activation and t;peration of Revision 1 TP-1,9-9-82 Exp NA the Technical Support Center 8-24-82 (TSC)
EPP.021 Activation and Operation of Revision 1 the Operations Staging Area 5-25-82~
l' (0SA) and Personnel
}
Accountabili ty EPP.022 Activation and Operation of l Revision 3 the Emergency Operations 1-28-83 Facility EPP.023 Activation and Operation of CANCELLED the Emergency Control Center 6-4-82 (ECC) (An Erergency Operations Facility)
O EPP.024 Activation and Operation of Revision 1
'u/
the Joint Public Information 6-24-82 I
I Center (JFIC) (An Emergency Operations Facility) p3gg 3
Rev. Cata A-d-D
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PMo EPP INDEX s n(_)
6 LIST OF EXHIBITS PMP 2081 EPP.010 EXHIBIT A RADIATION PROTECTION DIRECTOR ACTIVATION PRIORITIES (1) fj EXHIBIT B RADIATION MONITORING TEAM MISSION DIRECTIVE l;
PMP 2081 EPP.011 EXHIBIT A DIRECT RADIATIO;i SURVEY DATA EXHIBIT B SAMPLE ENVELOPE DATA PMP 2081 EPr OR EXHIBIT A 0FF-SITE SURVEY MAP (10 MILE EPZ)
O exHI81T B ESTA8L1SHED SuavEv e0 INT MAeS EXHIBIT C RADIATION MONITORING TEAM MISSION DIRECTIVE EXHIBIT D DOSE RATE FORM EXHIBIT E SAMPLE ENVELOPE DATA EXHIBIT F 0FF-SITE RADIOLOGICAL MONITORING PMP 2081 EPP.013 EXHIBIT A ON-SITE ENVIRONMENTAL SAMPLING STATIONS EXHIBIT B 0FF-SITE ENVIRONMENTAL SAMPLING STATIONS
^;
EXHIBIT C DCCNP ENVIRONMENTAL MONITORING PROGRAM EXHIBIT D INGESTION DOSE PROJECTION CALCULATIONS EXHIBIT E VERTICAL DISPERSION COEFFICIENT AS A FUNCTION OF DOWNWIND DISTANCE FROM THE SOURCE EXHIBIT F HORIZONTAL DISPERTION COEFFICIENT AS A FUNCTION OF DOWNWIND DISTANCE FROM THE SOURCE O
EXHIBIT G DOSE AT vAaIOUS DISTANCES FROM Ct0uD CeNTEat1NE PAGE 9
DATEo7-D-Er3
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INDIANA & MICHIGAN ELECTRIC COMPANY
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DONALD C. COOK NUCLEAR PLANT PROCEDURE COVER SHEET Procedure No. PMP 2081 EPP.010 Tsevision No. 1 TITLE ACTIVATION OF RADIATION MONITORING TEAMS SCOPE OF REVISION Revision 1 - Corrected to reflect current operational methods.
Deleted unnecessary organization chart.
~ 3CR FEB 0 21983 0
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SIGNATURES ORIGINAL Rev.I REV.2 Rev.S
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PREPARED BY I,(Of/
QUALITY ASSURANCE g
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REVIEW pL INTERFACING DEPARTMENT //
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HEAD CONCURRENCE L
N.A.
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DEPARTMENT HEAD U
APPROVAL N.A.
g PLANT NUCLEAR SATETY COMMITTEE
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PLA?TT MANAGER gj APPROVAL e_
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DATE Of ISSUE 3-31-81 4~/~8d
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V Form Ne PMI 20L1-mav. 2
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LIST OF' EFFECTIVE PAGES PAGE NUMBER REVISION NUMBER AND DATE Page 1 of 5 Revision 1, Feb.1,1983 Page 2 of 5 Revision 1, Feb.1,1983 Page 3 of 5 Revision 1, Feb.1,1983 Page 4 of 5 (EXHIBIT A)
Revision 1, Feb.1,1983 Page 5 of 5 (EXHIBIT B)
Revision 1, Feb.1,1983 O
f O
Page 1 of 1 Rev. 1, Feb.1,1983
PMP 2081 EPP.010 INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT ACTIVATION OF RADIATION MONITORING TEAMS 1.0-OB.TECTIVES This procedure includes suggested priorities for_ activation of radiation monitoring personnel based on emergency
-conditions and describes functions of the Radiation Protection Director.
This precedure shall be implemented by the Shift Supervisor or On-Site Emergency Coordinator upon recognition of a potential or actual' unplanned release of radioactive gas or liquid.
2.0 RESPONSIBILITIES 4
The Shift Supervisor (SS) or Plant Manager (acting as the On-Site Emergency Coordinator) is responsible for activating the Radiation Protection Director upon recognition of a potential or actual unplanned radioactivity release.
The Radiat3on Protection Director is responsible for O
activating Radiation Monitoring Teams as required to assess radiation conditions.
3.0 INSTRUCTICNS NOTE:
REFER TO EXHIBIT A: RADIATION PROTECTION DIRECTOR ACTIVATION PRIORITIES, TO DETERMINE TEAMS TO BE ACTIVATED BASED ON PRIORITIES AND EXISTING CONDITIONS, 5.1 Eased on personnel availability, the Radiation Protection Director'shall:
NOTE:
THE SHIFT SUPERVISOR OR PLANT MANAGER MAY SERVE AS THE RADIATION PROTECTION DIRECTOR UNTIL THE PRIMARY OR ALTERNATE RPD IS ACTIVATED.
h 3.1.1 Designate Radiation Monitoring Team Leaders and Team members based on emergency conditions.
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p Page 1 of 5 Rev. 1
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NOTE:
. EACH RADIATION MONITORING TEAM SHALL BE MADE UP OF AT LEAST ONE TECHNICIAN QUALIFIED IN RADIATION PROTECTION-ANG AT LEAST ONE OTHER PERSON.
3.1.2 Document teams and assignments on EXHIBIT C, RADIATION MONITORING TEAM MISSION DIRECTIVE.
3.1.3 Upon arrival of designated personnel at the OSA, brief all reporting RMT personnel on plant conditions, source and conditions of the release, anticipated dose rates or ranges anticipated at specific locations, and protective equipment to be used.
3.1.4 Direct implementation of emergency procedures.
3.2 Upon being assigned to a Radiation Monitoring Team:
3.2.1 Ensure you are' properly briefed by the RPD or RMT Leader on expected radiation levels, stay times, form of results expected, monitoring routes and locations.
(])
3.2.2 Obtain the required protective and monitoring equipment from. locations designated or approved by the RPD.
3.2.3 Prior to leaving the area where monitoring equipment is~obtained, perform an instrument check to assure pcwer supply is adequate, calibration sticker is current, limitations of instrument are acceptable, and (if time permits), perform a source check.
3.2.4 Proceed to the* specific locations to be monitored or sampled with monitoring instruments in operation.
3.2.5 Perform assigned functions in accordance with specified EPP's or existing plant procedures, and record readings in all areas encountered.
NOTE:
INFORMATION OS SOTH HIGH AND LOW RADIATION AREA $ MAY BE SIGNIFICANT DURING EMERGENCIES.
3.2.6 Ensure exposure does not exceed limits set in PMP 2082 EPP.001, Emergency Exposure Guidelines.
O Page 2 of 5 Rev. 1 l
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O 3.2.7 Record and report all results and your exposure to the RPD or his designee.
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I LO Page 3 of 5 Rev. 1
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PMP 2081-EPP.010 EXHIBIT A
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RADIATION PROTECTION DIRECTOR ACTIVATION PRIORITIES (1)
Priority Task EPP(s) Th'at Implement 1
Search and Rescue and First Aid-Life PMP 2081 EPP.006 Saving Only 2
Initial Dose Projections and PMP 2080 EPP.001, Comparison with EAL's
.006,.007 3
In-Plant Surveys to Calculate Initial PMP 2081 EPP.011, Source Team
.012,.014 4
Dose Confirmation (Off-site PMP 2081 EPP.012, Monitoring) 5 Monitoring at Access Control Points PMP 2081 EPP.011 at RadiationTContaminated Areas 6
Emergency Fftst Aid and PMP 2081 EPP.008, Decontamination - not Life Saving
.009 7
Acccmpany Follow-up Re-entry and PMP 2081 EPP.010 Rescue Teams
()
8 Personnel Exposure Control (Routine PMP 2081 EPP.009 1
Dosintetry Assurance and Completion of Radiation Work Permits) 9 Follow-up Radiation Monitoring for PMP 2081 EPP.012, Effects
.013,.014,.015 10 Liaison with Off-site Agencies PMP 2081 EPP.013 11 Follow-up Dose Projections and EAL PMP 2081 EPP.012, Modifications
.013,.014,.015 12 Follow-up In-plant /On-site Monitoring PMP 2081 EPP.011, and Sample Collection
.016 13 Sample Analysis and Interpretation PMP 2081 EPP.016,
.017
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14 Minor First Aid Decontamination PMP 2081 EPP.008,
.009 (1)
This list of activity priorities is sequenced in a "likely order" for a fast breaking radiological emergency when personnel resources may be limited.
Personnel assignments should be made as needed by the specific plant and personnel requirements.
j Page 4 of 5 Rev. 1
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e PMP 2091 EPP.010 EXHIBIT B RADIATION MONITORING TEAM MISSION DIRECTIVE TYPE MISSION: On-Site Off-Site Airborne Waterborne Sampling Monitoring ASSIGNED TO TEAM LEADER:
TEAM MEMBERS:
DATE/ TIME ASSIGNED:
/
AREA INVOLVED:
Date Time MISSION DETAILS:
4 RADIATION / DAMAGE CONDITIONS / ROUTE:
O BRIEFING AND RECEIPT ACKNOWLEDGED Team Leader TIME MISSION INITIATED:
TIME MISSION COMPLETED:
RESULTS OF MISSION (USE REFERENCES AS CONVENIENT):
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INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT O
Instruction or Procedure Temporary Sheet This temporary sheet applies to 0FF-SITE RADIOLOGICAL MONITORING TEMPORARY Instruction or Procedure No. PMP 2081.EPP.012 Revision No.
1 TP-1 I
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The fol!owing change ( X )
new requirement (
)
shall be instituted effective (Date) 25 January. 1983 4
Replace the following pages as indicated:
List of Effective Pages, Page 1 of 1, Revision 1 with Revision 1, TP-1 Page 1 of 11, Revision 1 with Revision 1, TP-1 Page 2 of 11, Revision 0 with Revision 0, TP-1 Page 3 of 11, Revision 1 with Revision 1, TP-1 Page 4 of 11, Revision 1 with Revision 1, TP-1 DCR FEB 0 21983 0
i REASON FOR CHANGE:
Changes were made in response to NRC - Identified Weaknesses in the Emergency Plan involving obtaining representative samples of the plume atmosphere using a thin window detector l
to enable differentiation between beta / gamma and gamma measurements.
This change should be made a permanent revision to the Instruction or Procedure:
X3YES ONO a NOT KNOWN, additional review required Expiration Date:
PROCEDl$EPEVISION Standard Dist. List No.:
1 Originator: T/lut V
/Ll MW ^
Distribution:
Management Staff:
[ MA744t/8L -_
Senior Reactor Ope.ator: /ddnMEj PNSRC RWTimrnt& Date 5-- ]/. gs (/
LO 2 '*** -' - ' - #3 ~
Forrn No. 4330 REVISED 7/78 WHITE
- ORIGINAL CANARY - ORIGINATOR COPY FINK
- WORKING COPY FORM NO. PMI 201M REV.2
s-PMP 2081.EP?.012 h
LIST OF EFFECTIVE PAGES PAGE NUMBER REVISION NUMBER AND DATE Page 1 of 11 Revision 1,TP-1 Page 2 of 11 Revision 0, TP-1 Page 3 of 11 Revision 1,TP-1 Page 4 of 11 Revision 1 TP-1 Page 5 of 11 (EXHIBIT A)
Revision 0, 04-01-81 Page 6 of 11 (EXHIBIT B)
Revision 0, 04-01-81 Page 7 of 11 (EXHIBIT B).,
Revision 0, 04-01-81 Page 8 of 11 (EXHIFIT C)
Revision 0, 04-01-81 Page 9 of 11 (EXHIBIT D)
Revision 0, 04-01-81 Page 10 of 11 (SAMPLE ENVELOPE Revision 0, 04-01-81 DATA)
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Page 11 of 11 (EXHIBIT F)
Revision 0, 04-01-81
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s Page 1 of 1 Rev. 1,IP-1
V INDIANA & MICHIGAN ELECTRIC CCNPANY
' DCNAID C. COOK NUCLEAR PIAlff OFF-SITE RADIOIOGICIL FONITORING 1.0 OBJECITJES This procedure includes requirements for off-site radiation monitoring and data acquisition necessary for the TSC Plant Evaluation Team and RAD to verify the extent and nature of off-site gaseous releases per PMP 2081.EPP.014, Off-Site Dose Assessments, and to r+> -nd protective actions to the public. This procedure does not address determination of radiological effects on the environment (contained in Ptf 2081.EPP.013).
2.0 RESPONSIBILITIES The Radiation Monitoring Team (RbE) are responsible to the Radiation Protection Director (RPD)/ to:
2.1 Survey and record off-site radiological data at mlected locations.
2.2 Report all survey results to the RPD.
2.3 Assist in surveys from helicopters (if necessary).
2.4 Pecxmend survey locations for continums plume dispersion monitoring.
lTD-1 3.0 INSTRUCTIONS OFFIONAL CHECKLIST ENTRIES PROVIDED 1 DIE:
INITIAL DOSE ESTIMATES MAY BE MADE BY VISUAL AIDS OR BY THE USE OF THE AEPSC COMPUTER PROGRAM CPM 002 OR MIDAS OR BY HAND AS PER PMP 2081.EPP.014.
FIEID MEASURDE2 TIS ARE TO VERIFY AND/OR ESTA3LISH (DRRELATINS.
IKEE:
IF THE RBE IS TO USE A HELICOPTER, THDI PPN DIRECTLY 10 STEP 3.6.
3.1 Peceive briefing frcm the RPD or RAD on-site lTP-1 mnditions and off-site locations to be monitored.
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PfP 2081.EPP.012 O
No1E:
uSE ExHI81TS A Orr-S1TE SURVEY rap, AND 8, ESTABLISHED SURVEY PODES, 'IO IDCATE THE SURVEY POItES. ALSO, SEE PMP 2082.EPP.008,IRPS AND OVERIAYS.
3.2 When directed by the RAD to perform off-site i
radiological surveys, obtain a radio telephone, lTP-1 R=diation Protection Dnergency Kit, and a 12 volt Air Sagler, (Mobile), while another IDE mernber locates and prepares the survey vehicle.
7 NOTE:
KEYS EOR I&M VHIICLES ARE MADEAINED IN 'IHE i
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OPERATICES STAGING AREA ENE%ENCY EQUIPME2C ROCM.
3.3 Perform an equipment and instrument check prior to lg leaving the site.
3.4 Establish ctzmunications with the TSC using the radio telephone and proceed to the survey points.
3.5 Ask the RPD if the points to be surveyed remain the same and document the changed instructions, on EXHIBIT C, RADIATICN PONI'IORING TEAM MISSION DIRIITIVE.
3.6 If reauested to assist in off-site agency surveys frcm a helicooter, proceed as follows:
J 3.6.1 Request a briefing on the helicopter landing location, estimated tire of arrival, and cn present plant conditions frcm the RPD.
3.6.2 Obtain a Radiation Prctection Emergency Kit and a portable rir sagler.
NOI'E:
THE OFF-SITE IDNI'IORING KIT (bOBILE) CAN EE CBTAINED AT 'IHE OSA EMERGENCY EQUINEtE RCOM OR AS SPECIFIED IN PMP 2082.El9.007.
3.6.3 Perform a quick equignent eneck prior to lg pMW-3.6.4 tieet the heliccpter.
NCTIE:
RECORD ALL SURVEY INSTRUCI' IONS AND IDCATIONS OF SUFVEY PODES (DISTA!K'E IN MTTE FROI THE SITE AND ELEVATICN, OR FEET ABOVE GROUND LEVEL) ON EXHIBIT C, RADIATION BDNI'IORING TEAll MISSION DIRECTIVE.
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- n 3.7 Survey to determine the apprn.imate location of the pltne and U
the presence or absence ~of ground deposition of beta activity.-
3.7.1
'Ihe Eberline E-5'30G is the instrument of choice for deter-mining p1tne locaticn. Operational details for this in-strument may be found in 12 THE 6010. RAD.517.
-3.7.1.1 Using the E-530G, obtain readings of count rate using the side or end window of the probe. Cb-tain readings with the window open and with it closed. The open window result minus the closed window result yields _an estimate of beta presence.
i 3.7.1.1-1 If there is an indicaticn of beta frca all directions, this indicates that the probe is within the plume and that it is a good locaticm for ab+=ining air sanples.
TP-1 3.7.1.1-2 If high ganma readings are found with low or no beta, this indicates that the probe is under the plume.
3.7.1.1-3 If beta results are obtained when the open window is directed at the
.A ground,-but not when directed into V
the air above ground, ground deposi-ticn is indicated.
3.7.1.2 Use the directional capability of the E-530G prtbe to detarmina the team's approx 2 mate loca-tion-in relation to the plume.
3.7.1.3 Once the plume's locaticn is established, obtain dose rates and begin surveying a traverse of the plume using the PIC-6.
If the plume is l
too low in radioactivity for the PIC-6, obtain,
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raadings with the E-530G.
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3.8 Continuously at:nitor the general area. Record all survey data 1
and results of the analyses on EXHIBITS D, DOSE RATE EURM: AND L
2, SAMPLE ENVEEOPE DATA, as specified. Mditional acticms/ccaments l
can be entered on EXHIBIT D.
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3.8.1 Using equignent shielded against beta radiaticm, traverse the plume in the crosswind direction, deter-ine the maxi-num mrem /hr, and record that reading, time ~ the reading was taken, and the locaticm on EXHIBIT E.
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3.8.2 Place a particulate filter and a silver zeolite cartridge l-in the air sampler and collect a sample of 5 to 10 cubic O
feet voltm at the location where the mrem /hr reading ws the hi@ est (found during traverse).
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PW 2081.EPP.012 3.8.3-While collec ting the sanple, report. the specific survey v
location and results of the gama dose rate survey to the RPD.
3.8.4
_ After collecting the air sanple, record (cn the sanple
-container - EXHIBIT E) and place the silver zeolite cart-ridge and the particulate filter in separate sanple enve-
' lopes and mark them for later identificaticn.
t 3.8.5 Contact the RPD (by radio) to locate a low background area to be used for counting and pra to the area specified.
3.8.6 Determine the activities per 12 'IHP 6010. RAD.517.
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USE CURVES IN KIT AS NECESSARY.
3.8.7 Ccxtplete the information regtuxed on EXHIBIT E.
3.9 ' Perform aMitional surveys as follows:
NOTE:
BASED W FIELD DOSE RATE MEASUREMENTS, TAKE THE AIR SAMPLES STARTING AS NEAR 'IO THE CENTER OF THE PIDC AS POSSIBLE.
3.9.1 Repeat Step 3.7 or 3.8 ac directed by the RPD (3 or 4 pasms across the plume would be optinum). and record data cn EXHIBITS D, DOSE RA'IE FORM, and E, SAMPLE ENVEIOPE DATA.
3.9.2 Ccstpute the average dose rate for all pasms made in or near the same location and record on EXHIBIT E.
3.9.3 Report the Average Dose Rate and specific location to RPD.
3,10 Assist in coordination and augmentation of the State and local effort, as directed by the RPD/ RAD.
3.11 Request further instr.2ctions frcm the RPD/ RAD.
CAUTIG : IF RELIEVED BY A NEN RMI MEMBER, FULLY BRIEF THE MEMBER CN THE SIA'IUS OF 'IEE SURVEYS.
3.12 Exhibit F in a Checklist for Off-Site Radiological Monitoring.
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