ML17320A344

Public Version of Procedure Temporary Sheet 2 to Rev 3 to Emergency Plan Implementing Procedure PMP 2080 EPP.006, Initial Dose Assessments (Gaseous). Revised Index Encl

ML17320A344
Person / Time
Site:	Cook
Issue date:	01/12/1983
From:	Murphy C, Townley E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17320A343	List: ML17320A342 ML17320A344
References
PMP-2080-EPP., PMP-2080-EPP.00, NUDOCS 8302080042
Download: ML17320A344 (7)

Text

rnIAIJIA e mceAe DONALD C. COOK NUCLEAR PLANT

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instruction or Procedure Temporary Sheet This temporary sheet applies to /~~~~~ EMPORARY Instruction or Procedure No. ~P ~~B'gp ~~nod HEET NO.

Revision No. +

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USmg JAN 1 21983 This change should be made a permanent revision to the instruction or Procedure:

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Senior Reactor Operata".

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PMP 2080 EPP.006

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Pg.~ 2of 3 INDIANA & MICHIGAN EIZCTRIC CCM?ANY DCMID C. COOK NEXZAR PLANT INITIALDOSE ASSESSMENTS (GASKKJS) 1.0 OB319CTVGX This procedure provides the Shift Supervisor/On-Site Emergency Coordinator (SS/OSEC) with a method to initially assess potential off-site does effects or unplanned radioactive gaseous releases.

2.0 RESPONSIBILITIES 2.1 Upon a projected or prior to activation of a~ the unplanned, Technical radioactive gaseous release, Support Center, it and is the SS/OSEC's responsibility to make off-site does projections. The SS/OSEC shall also verify the projected values by organizing a Radiation Monitoring Team and sending them to appropriate off-site area.

2.2 Technical Support Center (TSC) personnel assum the responsibilities of 2.1 upon TSC activation.

This procedure is applicable prior to activation of the Technical Support Center whenever there is a significant projected or unplanned release of gaseous radioactl.v3.ty e 3 0 APPLICAB3ZZTY This procedure is applicable prior to activation af the Technical Support Center whenever there is a significant projected or unplanned, release of gaseous zadl.oact3.v3.ty +

4.0 INSTRUCTIONS 4.1 Obtain data necessary to make off-site dose projections.

4.1.1 R-15, R-26, and/or R-33 ~tion nanitor readings.

4.1.1.1 If R-26 is off-scale high, obtain a radiation reading at 6" fran the unit vent, sample line.

4.1.1.2 If R-15 or R-33 is off-scale high, obtain a radiation reading at 6" fran the GSLD or 83AE exhaust line.

4.1.2 Appropriate vent flew rate (Unit Vent, GSID, or S3AE) .

4.1.3 Wind velocity and direction fzcm the 150 foot elevation.

.Page 1 of 17 Rev. 3 TP 2

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t PMP Pg. 3 2080 EPP.006 of 3 4.1.4 Determine PASCALL Category as per the table below:

'DT=(T9180ft.T930Ft ) oC PASCALL CATEGORY

.9 A

-.9 to .8 B

-'.8 to ~

7 C

-.7 to ~ 2 D

.2 to + .7 E

+.7 to +1.8 F

+1.8

'f G

4.2 meteorological instrumentation is inoperable use Exhibit G to estimate wind speed and PASTEL Category. Obtain wind direction frcm the Visitors Center or State Police.

4.3 Select appropriate graph(s) to use and fillin data blanks.

4.3.1 R-26 On-Scale; Exhibit A 4.3.2 R-26 Off-Scale; Exhibit B

, 4.3.3 R-33 On-Scale; Ehchibit C 4.3.4 R-15 On-Scale; Exhibit D 4.3.5 R-15, R-33 Off-Scale; Exhibit E 4.3.6 Waste Gas Decay Tank Release; Exhibit F KlZE R-15 On-Scale will always result. in less than 1 mR/hr off-site.

With steam generator tube ruptures, readings would be expected also on R-33. The dose associated with the release fran a steam generator tube rupture will be the sum of +~ doses calculated fmxn R-15 and R-33.

NOZE: The ability to predict dose rate in the event of a steam generatar tube rupture is dependent upon the release being via R-33 and R-15. If relearns are being made via the safeties ar steam generator PR3V's because of the loss of condenser vacuum ar equipment failure, there is not quick method to calculate dose rate.'ose rate should then be neasured at the site boundary as soon as possible by dispatching a aanitoring team to monitor downwind at the site boundary.

P 4.4 Complete the appropriate graph(s) to estimate off-site dose rate as follows:

4.4.1 Draw a straight line connecting the data points on scales (1) and (2).

4.4.2 Draw a straight.,line connecting the intersection of scale (3),

faun step 4.4.1, with the data point an scale (4) .

4.4.3 Connect the intersection of scale (5), frcm step 4.4.2, with the data point on scale (6).

4 4 ' Read the 610 aeter site boundary dose rate fnxn the intersection of scale (7), caused by Step 4.4.3.

I Page 2 of 17 Rev. 3 T,P-2 ~

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PMP EPP INDEX

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INDIANA 5 MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT P ANT MANAGE Index Identi fi cati on Title Revision iNo.

Comments Number And Date PMP 2080 EPP.001 Emergency Plan Activation Revision 3 and Condition Classification 10-12;..82 EPP.002 Unusual Event CANCELLED 10-29-81 EPP.OO Alert CANCELLED 10-29-81 EPP.OO Site Emergency CANCELLED 10-29-81 N

EPP;00 General Emergency CANCELLED 10-29-81 EPP.OO Initial Dose Assessment Revilion 3 TP-1, 1-4-83 EXP NA (Gaseous) 8-27-82 TP-2,1-.10-83 Exp NA EPP.007 Initial Release Assessments Revision 0 TP-1,2-23-82 Exp NA (Liquid) 4-1-81 EPP.008 Initiating Manning of Emer- Revision 3 gency Response Facilities 10-12-82 8 Calling Off-Duty Personnel EPP.009 Fire Emergency Guidelines Revision 1.

6-15-82 EPP.010 Toxic Gas Release Guidelines Revision.l

.6-'2-82 EPP.011 Natural Emergency Guidelines Revisioil 1 11-15-82 t

EPP.012 Initial Off-Site Notificatio Revision 2

'\ 10-19-82 Page ~

Rev. Data l i2 i'