ML20042C890

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IPEC Emergency Plan Implementing Procedures
ML20042C890
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 02/06/2020
From: Deborah Gray
Entergy Nuclear Operations
To:
Office of Nuclear Reactor Regulation
References
Download: ML20042C890 (29)
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Text

-====- Entergy Indian Point Energy Center CONTROLLED DOCUMENT Document Control TRANSMITTAL 450 Broadway Buchanan, NY 10511 TO: DISTRIBUTION FROM: IPEC DOCUMENT CONTROL - 3RD FLOOR ADMIN BLDG - JANEENE LEVEQUE X2903 TRANSMITTAL#: EP-20-0006 The Document(s) identified below are forwarded for use. Please review to verify receipt, incorporate the document(s) into your controlled document file, properly disposition superseded, voided, or inactive document(s).

THE FOLLOWING PROCEDURE(S) HAVE BEEN REVISED. PLEASE REMOVE YOUR CURRENT COPY AND REPLACE WITH ATTACHED UPDATED PROCEDURE:

IP-EP-310, REVISION 20 EFFECTIVE 02/07/2020

                      • PLEASE NOTE EFFECTIVE DATE***********

RECEIPT OF THE ABOVE LISTED DOCUMENT(S) IS HEREBY ACKNOWLEDGED. I CERTIFY THAT ALL SUPERSEDED, VOID, OR INACTIVE COPIES OF THE ABOVE LISTED DOCUMENT(S) IN MY POSSESSION HAVE BEEN REMOVED FROM USE AND ALL UPDATES HAVE BEEN PERFORMED IN ACCORDANCE WITH EFFECTIVE DATE(S)

(IF APPLICABLE) AS SHOWN ON THE DOCUMENT(S).

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NAME (PRINT) SIGNATURE DATE COPY LOCATION

IPEC EMERGENCY PLAN DISTRIBUTION LIST Page 1 of 2 IP3 CONTROL ROOM DELIVERED BY DOCUMENTS IP3 53FT. CCR 1 COPY OF ALL EP'S IP3 SHIFT MANAGER DELIVERED BY DOCUMENTS IP3 53FT. ELEVATION 1 COPY OF ALL EP'S IP2 CONTROL ROOM DELIVERED BY DOCUMENTS IP2 53FT. CCR 1 COPY OF ALL EP'S IPECTSC DELIVERED BY DOCUMENTS IP2 53FT. ELEVATION 1 COPY OF ALL EP'S IP2 SIMULATOR DELIVERED BY DOCUMENTS IP2 SIMULATOR BLDG. 1 COPY OF ALL EP'S IP2 SIMULATOR - CLASSROOM 4 DELIVERED BY DOCUMENTS IP2 SIMULATOR BLDG. 1 COPY OF ALL EP'S IP2 SIMULATOR - CLASSROOM 5 DELIVERED BY DOCUMENTS 3 COPIES OF ALL EP'S IP2 SIMULATOR BLDG.

EXCEPT E-PLAN NRG RESIDENT INSPECTOR NRG IP2 88FT. ELEVATION 1 COPY OF ALL EP'S NRG - ROCKVILLE, MD [ 1 COPY10F ALL EP'S AND DOC CONTROL DESK - OFFSITE GENERAL RECORDS ADDRESS EXCEPT IP-EP-115 1 COPY OF ALL EP'S AND NRG JAMES DANNA OFFSITE GENERAL RECORDS EXCEPT IP-EP-115 1 COPY OF ALL EP'S AND NRG DEPUTY DIRECTOR OFFSITE GENERAL RECORDS EXCEPT IP-EP-115 1 COPY OF THE FOLLOWING:

NEW YORK STATE OEM TED FISCH E-PLAN, IP-EP-115, 120, 210,220,230,250,31 0, 320,340,360,410,42 0, 430,620 & IP-1055 WESTCHESTER COUNTY OEM DENNIS DELBORGO 1 COPY OF E-PLAN, OFFSITE IP-EP-310 & 340 & 410 ROCKLAND COUNTY FIRE AND 1 COPY OF E-PLAN, EMERGENCY SERVICES NICHOLAS LONGO OFFSITE IP-EP-310 & 340 & 410 ORANGE COUNTY EMERGENCY 1 COPY OF E-PLAN, SERVICES CENTER SHANNON FISHER OFFSITE IP-EP-310 & 340 & 410 PUTNAM COUNTY BUREAU OF 1 COPY OF E-PLAN, EMERGENCY SERVICES KEN CLAIR OFFSITE IP-EP-310 & 340 & 410

.a. IPEC NON-QUALITY RELATED IP-EP-310 Revision 20

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Dose Assessment Prepared by: Dara Gray Print Name eh.,.<l!fa t2-, l Oat~

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Approval: Frank J. Mitchell Print Name

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Effective Date: February 7, 2020 fu Li-,,1(JfJ

  • IP-EP-310 (Dose) R20.doc

IPEC NON-QUALITY RELATED IP-EP-310 Revision 20 EMERGENCY PLAN PROCEDURE IMPLEMENTING PROCEDURES REFERENCE USE Page g of 22 Table of Contents 1.0 PURPOSE ...................................................................................................................................3

2.0 REFERENCES

............................................................................................................................3 3.0 DEFINITIONS ............................................................................................................................. 3 4.0 RESPONSIBILITIES ....................................................................................................................4 5.0 DETAILS ......................................................................................................................................4 6.0 INTERFACES ............................................................................................................................10 7.0 RECORDS .................................................................................................................................10 8.0 REQUIREMENTS AND COMMITMENT CROSS-REFERENCE. ............................................. 10 9.0 ATTACHMENTS .......................................................................................................................10 9.1 SITE BOUNDARY Xµ/Q (m* 2) BY PASQUILL STABILITY CATEGORY ..................... 11

  • 9.2 9.3 9.4 Xµ/Q VALUES FOR OTHER DISTANCES (m* 2)

REUTER-STOKES LOCATION Xµ/Q VALUES (m*2)

ACCIDENT MONITORING OF NOBLE GAS CONCENTRATION IN THE PLANT VENT

......................................................... 13.

.................................................. 14

......................................................................................................................................15 9.5 DETERMINATION OF NOBLE GAS RELEASE RATE - DISCUSSION ...................... 17 9.6 DETERMINATION OF NOBLE GAS TO IODINE CONCENTRATION AND DOSE RATE RATIOS FROM FIELD MONITORING DATA ............................................................. 19 9.7 USE OF CHEMISTRY SAMPLE TO DETERMINE RADIOIODINE RELEASE RATE

& THYROID DOSE CONVERSION FACTOR .............................................................21

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IPEC NON-QUALITY RELATED IP-EP-310 Revision 20

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EMERGENCY PLAN PROCEDURE IMPLEMENTING PROCEDURES REFERENCE USE Page ~ of 22 1.0 PURPOSE To describe the methods of estimating the whole body and thyroid dose to the offsite population in the event of an accidental release of radioactivity to the environm~nt. A manual method of calculation is provided in case the computer method is unavailable.

2.0 REFERENCES

2.1 IP-EP-330, Airborne Sample Analysis 2.2 IP-EP-340, Meteorological Information and Dose Assessment System (MIDAS) 2.3 IP-EP-510, Meteorological, Radiological & Plant Data Acquisition System 2.4 IP-2 Manual Determination of Release Rate (Form EP-17) 2.5 IP-3 Manual Determination of Release Rate (Form EP-18) 2.6 Manual Dose Assessment Worksheet (Form EP-13)

  • 2.7 2.8 IPEC Manual Dose Assessment Worksheet/Back-Calculating Release Rate from Field Data (Form EP-19)

JPEG Manual Dose Assessment Worksheet/Estimating Containment Activity via R-25 / 26 (Form EP-11) 2.9 Determination of Radioactive Airborne Concentrations (Form EP-32) 3.0 DEFINITIONS 3.1 Meteorological Information and Data Acquisition System (MIDAS) - the computer system that collects radiation monitor data, meteorological data, and calculates/displays offsite radiation doses.

3.2 Meteorological, Radiological, and Plant Data Acquisition System (MRP-DAS) - the system which provides meteorological, Reuter Stokes and certain plant parameter data (VC Temperature, VC Pressure, Plant Vent and VC High Radiation Monitors) 3.3 Total Effective Dose Equivalent (TEDE) - The sum of the Deep Dose Equivalent (DOE) and the Committed Effective Dose Equivalent (CEDE).

3.4 Committed Effective Dose Equivalent - The sum of the products of the weighting factors applicable to each of the body organs or tissues that are irradiated and the committed dose equivalent to these organs or tissues .

3.5 Committed Dose Equivalent-Thyroid (COE-Thy) - The committed dose from an intake of radioactive material to a body organ (i.e., thyroid).

.a IPEC NON-QUALITY RELATED IP-EP-310 Revision 20

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EMERGENCY PLAN PROCEDURE IMPLEMENTING '

PROCEDURES REFERENCE USE Page 1 of 22 3.6 Site Boundary - For Dose Assessment and Protective Action Recommendation purposes, the Site Boundary is the closest distance at which members of the public would be exposed to a radioactive release.

When the plume is traveling toward the water, the distance to the nearest point on the opposite side of Hudson River will be considered as the Site Boundary.

3.7 Release - as it is used at IPEC for Emergency Planning is defined as "A release of radioactive materials due to the classified event" (per NYS Radiological Emergency Data Form, Part 1 ).

In accordance with the Part 1 form, "Release" is classified as one of the 4 following descriptions:

A. NO Release B. Release BELOW Federal Limits C. Release ABOVE Federal Limits D. Unmonitored Release Requiring Evaluation 4.0 RESPONSIBILITIES

  • 5.0 Dose Assessment staff in the Control Room (CR) and in the Emergency Operations Facility (EOF) are responsible for assessing actual and potential radioactive releases to the environment in an emergency.

DETAILS NOTE All forms s ecified in Section 5.0 are rovided in IP-EP-115.

5.1 Determine if there is a plant release above Federal Limits based on the following table:

Release Point Unit Rad Monitor Reading that is

>TS U2 or Plant Vent R-27 1.3 E+5 uCi/sec U3 Plant Vent U2 R-44 5. 7 E-3 uCi/cc Plant Vent U3 R-14 4.0 E-3 uCi/cc Main Steam R-28, R-29, U2 Line-SGTR R-30, R-31 SGTR is

  • Main Steam Line-SGTR Hole in Contain men rt U3 U2 or U3 R-62A, R-628, R-62C, R-62D R-25, R-26 considered a release> TS 1A/hr above background

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IPEC NON-QUALITY RELATED IP-EP-310 Revision 20

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EMERGENCY PLAN PROCEDURE IMPLEMENTING PROCEDURES REFERENCE USE Page § of 22 5.2 Upon activation of the IPEC ERO and as the IPEC Plant Conditions require, pertorm dose assessment. When pertorming the Dose Assessment function, use MIDAS (IP-EP-340) as the primary method. If there is no access to a dose assessment software program, dose assessment is to be completed using Hand Calculations (Section 5.4).

5.3 Necessary information to pertorm Dose Assessment is available using MRP-DAS (IP-EP-510).

5.4 Hand calculations for dose assessment are to be pertormed. if the necessary dose assessment software is not available. Pertorm hand calculations as follows:

NOTE:

IF a General Emergency has been declared, THEN use IP-EP-41 O "Protective Action Recommendations" to determine what protective action recommendations should be conveyed to the ED/RAC. Ensure the EPM in the TSC is made aware of any Protective Action Recommendations.

5.4.1 Obtain the* proper release rate calculation form (Form EP-17 for Unit 2 and Form EP-18 for Unit 3) .

5.4.2 Determine radioactive release concentration or rate (µCi/cc,

µCi/sec, OR CPM) and enter onto the appropriate Release Rate calculation form (Form EP-17 for Unit 2 or Form EP-18 for Unit 3).

Values determined from installed radiation monitors OR via a Chemistry sample may be entered directly into the Release Rate calculation form:

a. IF a Chemistry sample is available, THEN use Attachment 9.7 to calculate the radioiodine release rate.
b. IF the plant vent survey is to be used, THEN:
1. Follow guidance provided in Attachment 9.4, Accident Monitoring of Noble Gas Concentration in the Plant Vent.
2. Convert contact field reading on the plant vent to µCi/cc using conversion factor for appropriate time after shutdown, obtained from the appropriate Release Rate calculation form (Form EP-17 for Unit 2 and Form EP-18 for Unit 3).
c. IF back-calculating the Noble Gas release rate (NGRR) from field readings, THEN use Form EP-19.
d. IF using R-25 or R-26 to calculate the Noble Gas release rate (NGRR), THEN use Form EP-11 .
e. IF back-calculating the release rate from airborne samples,
  • THEN refer to IP-EP-330, Airborne Sample Analysis, and Attachment 9.5.

IPEC NON-QUALITY RELATED IP-EP-310 Revision 20

  • - E,1te,gy~ EMERGENCY PLAN PROCEDURE IMPLEMENTING PROCEDURES REFERENCE Use Page of 22

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5.4.3 If Noble Gas concentrations (µCi/cc) are entered in the Release Rate calculation form (Form EP-17 for Unit 2 or EP-18 for Unit 3),

use the proper equation(s) on the appropriate section of the Release Rate calculation form to calculate the Noble Gas Release Rate (NGRR).

5.4.4 Calculate the radioiodine release rate (Ci/sec) using the default equation (with the assumed NG/I ratio for the release point) on the appropriate Release Rate calculation form (Form EP-17 for Unit 2 and EP-18 for Unit 3).

IF a chemistry sample is available, THEN use Attachment 9.7 to:

a. Calculate the radioiodine release rate, and
b. Determine the sample-specific thyroid dose conversion factor.

5.4.5 Obtain the appropriate Xµ/Qs from Attachment 9.1 or 9.2. Record these values on the Manual Dose Assessment Worksheet (Form EP-13).

5.4.6 Obtain meteorological data in accordance with IP-EP-510 .

5.4.7 Enter the release rates (RR), wind speed (WS) AND appropriate constants on the Manual Dose Assessment Worksheet (Form EP-13).

5.4.8 Determine the TEDE (Whole Body) AND COE-Thy dose rates at the site boundary, 2, 5, AND 10 mile distances. (Form EP-13)

NOTE Use four (4) hours as the default release duration, unless information exists that clearly supports a different release duration.

5.4.9 Determine exposure rates if desired, at other distances utilizing the Xµ/Q values from Attachment 9.2.

5.4.10 Determine required Protective Action Recommendations (Procedure IP-EP-410, Attachment 9.1 ), IF the projected or actual doses at any offsite location exceed the following:

a. 1 Rem Integrated Dose TEDE, or
b. 5 Rem Integrated Dose COE-Thy THEN:
  • If in the CR, inform the Shift Manager (SM)/Emergency Director (ED).
  • If in the Emergency Operations Facility (EOF)/ Alternate Emergency Operations Facility {AEOF), inform the Radiological Assessment Coordinator.

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IPEC NON-QUALITY RELATED IP-EP-310 Revision 20

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EMERGENCY PLAN PROCEDURE IMPLEMENTING PROCEDURES REFERENCE USE Page z of 22 5.4.11 IF there is a radioactive release, THEN contact Chemistry/

Environmental Personnel as time permits to determine if it is above the Reportable Quantities set forth in 40 CFR302, Appendix B. If so, ensure the reportability requirements specified in IP-SMM-Ll-108 are met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

5.4.12 JE there is a radioactive release to the environment above Federal limits (using the table in step 5.1 ), THEN complete Parts I & II of New York State Radiological Data Form (Forms EP-1 and EP-2)

These forms can be filled in by hand or refer to procedure IP-EP-340, "Meteorological Information and Dose Assessment System" to have MIDAS automatically print out these forms.

5.4.13 "New York State Radiological Emergency Data Form-:- Part II" (Form EP-2) SHALL be c9mpleted and transmitted:

a. As soon as possible after it has been determined that a release above Federal Limits exists.
b. If there is a significant change in the radioactive release .
c. With updates approximately every 30 minutes; time interval may be lengthened with concurrence of offsite agencies.

5.4.14 IF electronic emailing and faxing using MIDAS is not operational, THEN process the NYS Radiological Emergency Data Form Parts I & II (Forms EP-1 and EP-2) as follows:

a. Receive form(s) from the Offsite Communicator, verifying that the form(s) are signed by the Emergency Director (ED).
b. Telecopy form(s) to NYS, Counties and JIG.
c. Maintain Fax Report (printed from the fax machine) as record.
d. Make and distribute copies of the form to NRG, FEMA, State and County representatives in the EOF.
e. Return original form and 2 copies to the Offsite Communicator.

5.4.15 To help visualize plume location, MIDAS plume data can be displayed directly from the MIDAS program or a MIDAS shape file can be exported to a Geographical Information System mapping

  • 5.5 software program in the EOF for display. Use IP-EP-410, Attachment 9.4 or the overlay book cover for manual plume visualization on the overlay table.

In the EOF only:

IPEC NON-QUALITY RELATED IP-EP-310 Revision 20

  • 5.5.1 IMPLEMENTING PROCEDURES REFERENCE Use Page Calculate projected doses using MIDAS, or manual methods.

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5.5.2 If available, verify projected doses with actual field radiological of 22 data.

5.5.3 At the earliest time when offsite radioiodine concentration is available, calculate the ratios of noble gas to iodine concentrations and corresponding dose rates using Attachment 9.6. Report the concentration ratio to the stakeholders on the Part II Form, Field Measurement Section.

a. Obtain a closed window gamma reading in the plume (mrem/hr).
b. Obtain iodine concentration in the plume (uCi/cc).

C. Convert gamma dose rate to noble gas concentration.

d. Calculate the ratio of noble gas concentration to iodine concentration.

e . Calculate the ratio of whole body dose rate to thyroid dose rate.

  • 1. IF the dose rate ratio is about 0.2 or higher, THEN noble gas (whole body/TEDE) dose rates will be more limiting than iodine (COE-Thy) dose rates.j Evaluate protective actions for possible changes.
2. IF the dose rate ratio is less than about 0.2, THEN iodine (COE-Thy) dose rates will be more limiting than noble gas (whole body/TEDE) dose rates. Evaluate protective actions for possible changes.

5.5.4 IF offsite gamma dose rates are available, THEN verify release rates determined from plant data using the "IPEC Manual Dose l Assessment Worksheet/Back-Calculating Release Rate from Field Data" (Form EP-19).

5.5.5 Review Site Perimeter surveys.

5.5.6 Review Field Surveys.

5.5.7 Review current and historical Reuter Stokes data, to determine if a release has occurred or is occurring. Attachment 9.3, "Reuter-Stokes Location Xµ/Q Values" provides Xµ/Q values for comparison purp,pses .

5.5.8 Exchange offsite monitoring and projected data with State and Counties.

IPEC NON-QUALITY RELATED IP-EP-310 Revision 20 EMERGENCY PLAN PROCEDURE IMPLEMENTING PROCEDURES REFERENCE USE Page 5.5.9 If required, estimate release rates utilizing High Range Vapor Containment radiation monitors R-25/26 (Form EP-11).

5.5.1 O If Core Damage Assessment results are available from the TSC, compare the results with the current dose assessment.

~ IPEC NON-QUALITY RELATED IP-EP-310 Revision 20

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IMPLEMENTING PROCEDURES REFERENCE USE Page 10 of 22 6.0 INTERFACES 6.1 IP-EP-410, Protective Action Recommendations 6.2 IP-EP-340, Meteorological Information and Dose Assessment System (MIDAS) 6.3 IP-EP-510, Meteorological, Radiological & Plant Data Acquisition System 6.4 Westchester, Rockland, Putnam, Orange County Radiological Emergency Response Plans 6.5 2-CY-3940, Plant Vent Sampling During Accident Conditions 6.6 3-CY-3920, Sampling Containment Atmosphere and Plant Vent During Accident Conditions 6.7 IP-SMM-Ll-108, Event Notification and Reporting 7.0 RECORDS

  • 8.0 Forms and reports completed during an actual emergency are permanent records .

.REQUIREMENTS AND COMMITMENT CROSS-REFERENCE IPEC Emergency Plan 9.0 ATTACHMENTS )

9.1 Site Boundary Xµ/Q (m*2) by Pasquill Stability Category 9.2 Xµ/Q (m*2) Values for Other Distances 9.3 Reuter-Stokes Location Xµ/Q (m*2) Values 9.4 Accident Monitoring of Noble Gas Concentration in the Plant Vent 9.5 Determination of Noble Gas Release Rate - Discussion 9.6 Determination of Noble Gas to Iodine Concentration and Dose Rate Ratios from Field Monitoring Data 9.7 Use of Chemistry Sample to Determine Radioiodine Release Rate and Thyroid Dose Conversion Factor

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~E'nLergy NON-QUALITY RELATED PROCEDURE IP-EP-310 Revision 20 EMERGENCY PLAN IMPLEMENTING PROCEDURES REFERENCE USE of Page 11 22 Attachment 9.1 Site Boundary Xµ/Q (m*2) by Pasquill Stability Category Cross Valley (Wind Direction from 210° -348° or Wind Speed> 4 mis)

Sheet 1 of 2 Sector Wind Distance Pasguill Categories From {Meters}

A B C D E F G 1* 168.7° to 191.2° 2977 5.5 E-7 9.0 E-7 5.7 E-6 2.1 E-5 1.1 E-4 4.3 E-5 2.0 E-4 2* 191.2° to 213.7° 3234 5.2 E-7 1.0 E-6 5.0 E-6 1.9 E-5 3.9 E-5 9.6 E-5 1.8 E-4 3 213.7° to 236.2° 716 3.6 E-6 2.0 E-5 5.3 E-5 1.5 E-4 2.7 E-4 4.9 E-4 7.1 E-4 4 236.2° to 258. 7° 701 3.7 E-6 2.0 E-5 5.4 E-5 1.6 E-4 2.7 E-4 5.0 E-4 7.2 E-4 5 258.7° to 281.2° 762 3.2 E-6 1.8 E-5 4.8 E-5 1.4 E-4 4.7 E-4 2.5 E-4 6.8 E-4 6 281.2° to 303. 7° 625 4.7 E-6 2.5 E-5 6.4 E-5 1.8 E-4 3.1 E-4 5.5 E-4 7.9 E-4 7 303.7° to 326.2° 610 4.9 E-6

  • 2.6 E-5 6.6 E-5 1.9 E-4 5.6 E-4 3.2 E-4 8.0 E-4 8 326.2° to 348.7° 701 3.7 E-6 2.0 E-5 5.4 E-5 1.6 E-4 2.7 E-4 5.0 E-4 7.2 E-5 9 348. 7° to 11.2° 1006 2.1 E-6 1.0 E-5 3.2 E-5 9.9 E-5 1.8 E-4 3.6 E-4 5.4 E-4 10 11.2° to 33.7° 1006 2.1-E-6 1.0 E-5 3.2 E-5 9.9 E-5 1.8 E-4 3.6 E-4 5.4 E-4 11 33.7° to 56.2° 488 7.7 E-6 3.6 E-5 8.8 E-5 2.5 E 4.0 E-4 6.7 E-4 9.2 E-4 12* 56.2° to 78.7° 2349 6.6 E-7 1.5 E-6 8.3 E-6 3.0 E-5 6.0 E-5 1.4 E-4 2.6 E-4 13* 78.7° to 101.2° 1802 8.1 E-7 3.2 E-6 1.3 E-5 4.3 E-5 8.5 E-5 1.9 E-4 3.3 E-4 14* 101.2°to 123.7° 1689 9.0 E-7 3.7 E-6 1.4 E-5 4.8 E-5 9.2 E-5 2.0 E-4 3.5 E-4 15* 123. 7° to 146.2° 1432 1.2 E-6 5.1 E-6 1.9 E-5 6.1 E-5 1.2 E-4 2.4 E-4 4.0 E-4 16* 146.2° to 168.7° 1416 1.2 E-6 5.2 E-6 1.9 E-5 6.2 E-5 1.2 E-4 2.5 E-4 4.0 E-4.
  • Plume for these sectors goes over the water before it touches public or private land. Site boundary in these cases is taken to be the landfall point at the sector center.

IPEC NON-QUALITY RELATED PROCEDURE IP-EP-310 Revision 20 EMERGENCY PLAN IMPLEMENTING PROCEDURES REFERENCE USE 12 of 22 Attachment 9.1 Sheet 2 of 2 Site Boundary Xµ/Q {m-2) by Pasquill Stability Category Up Valley Plumes (wind speed ~4 mis) Wind Direction from 102° -209° (1)

Pasguill Categories A B C D E F G 5.2 E-7 1.0 E-6 5.0 E-6 1.9 E-5 3.9 E-5 9.6 E-5 1.8 E-4 Site Boundary Xµ/Q (m*2) by Pasquill Stability Category Down Valley Plumes (wind speed ~4 mis) Wind Direction from 349° - 101 ° (2)

Pasguill Categories A B C D E F G 3.7 E-6 1.0 E-5 3.2 E-5 9.9 E-5 1.8 E-4 3.6 E-4 5.4 E-4 (1) Plume centerline will always cross the site boundary at Sector 2. Therefore, the Sector 2 Xµ/Q values are used.

(2) Plume centerline will cross the site boundary at either Sector 8 (Pasquill Category A) or Sector 10 (for Pasquill Category B - G)

IPEC NON-QUALITY RELATED PROCEDURE IP-EP-310 Revision 20 EMERGENCY PLAN IMPLEMENTING PROCEDURES REFERENCE USE Page 13 of 22 Attachment 9.2 Xp/Q Values for other Distances (m-2)

Sheet 1 of 1 Miles Distance Pasguill Categories (Meters)

A B C D E F G 1.0 1608 9.5 E-7 4.0 E-6 1.5 E-5 5.0 E-5 9.0 E-5 2.1 E-4 3.4 E-4 1.5 2412 6.3 E-7 2.1 E-6 1.1 E-5 2.0 E-5 5.4 E-5 1.3 E-4 2.2 E-4 2.0 3216 5.2 E-7 8.3 E-7 5.0 E-6 1.9 E-5 3.9 E-5 9.6 E-5 1.8 E-4 2.5 4020 4.4 E-7 5.8 E-7 3.5 E-6 1.4 E-5 3.7 E-5 7.0 E-5 1.7 E-4 3.0 4824 3.6 E-7 5.0 E-7 2.8 E-6 1.0 E-5 2.2 E-5 5.7 E-5 1.3 E-4 3.5 5628 3.2 E-7 4.2 E-7 2.0 E-6 8.1 E-6 1.8 E-5 4.7 E-5 1.1 E-4 4.0 6432 2.8 E-7 3.7 E-7 1.6 E-6 6.8 E-6 1.5 E-5 4.0 E-5 9.4 E-5 4.5 7236 2.6 E-7 3.5 E-7 1.4 E-6 5.8 E-6 1.3 E-5 3.5 E-5 7.3 E-5 5.0 8040 2.4 E-7 3.2 E-7 1.2 E-6 5.1 E-6 1.1 E-5 3.1 E-5 6.7 E-5 5.5 8844 2.1 E-7 3.1 E-7 9.9 E-7 4.4 E-6 1.0 E-5 2.8 E-5 5.9 E-5 6.0 9648 2.0 E-7 2.7 E-7 8.3 E-7 3.8 E-6 9.1 E-6 2.5 E-5 5.4 E-5 6.5 10452 1.9 E-7 2.5 E-7 7.5 E-7 3.5 E-6 8.2 E-6 2.3 E-5 5.0 E-5 7.0 11256 1.8 E-7 2.4 E-7 6.7 E-7 3.2 E-6 7.5 E-6 2.1 E-5 4.7 E-5 7.5 12060 1.7 E-7 2.3 E-7 6.1 E-7 3.0 E-6 6.9 E-6 1.9 E-6 4.3 E-5 8.0 12864 1.6 E-7 2.2 E-7 5.5 E-7 2.7 E-6 6.3 E-6 1.8 E-5 4.1 E-5 8.5 13668 1.5 E-7 2.1 E-7 5.0 E-7 2.5 E-6 5.8 E-6 1.7 E-5 3.8 E-5 9.0 14472 1.5 E-7 2.0 E-7 4.6 E-7 2.3 E-6 5.5 E-6 1.6 E-5 3.6 E-5 9.5 15276 1.4 E-7 1.9 E-7 4.2 E-7 2.1 E-6 5.4 E-6 1.5 E-5 3.4 E-5 10.0 16080 1.4 E-7 1.8 E-7 4.0 E-7 2.1 E-6 5.3 E-6 1.5 E-5 3.4 E-5

IPECSITE NON-QUALITY RELATED IP-EP-310 Revision 20 EMERGENCY PLAN PROCEDURE

  • IMPLEMENTING PROCEDURE REFERENCE USE Attachment 9.3 Page 14 Of 22 Reuter-Stokes Location Xµ/Q Values (m*2)

Sheet 1 of 1 Stability Class Sector Monitor A B C D E F G Distance (m) 1 3226 5.3E-7 8.4E-7 5.lE-6 l.9E-5 4.0E-5 9.8E-5 l.8E-4 2 3379 5.2E-7 8.3E-7 5.0E-6 l.8E-5 3.9E-5 9.7E-5 l.7E-4 3 2574 6.3E-7 l.2E-'-6 7.3E-6 2.6E-5 5.3E-5 l.2E-4 2.4E-4.

4 1448 1.2E-6 4.6E-6 l.8E-5 6.lE-5 l.lE-4 2.4E-4 3.9E-4

  • 5 6

7 8

1287 643 643 804 l.4E-6 4.3E-6 4.3E-6 2.9E-6 6.4E-6 2.2E-5 2.2E-5 l.7E-5 2.3E-5 6.0E-5 6.0E-5 4.5E-5 7.3E-5 l.8E-4 l.8E-4 l.3E-4 l.4E-4 3.0E-4 3.0E-4 2.4E-4 2.8E-4 5.5E-4 5.5E-4 4.5E-4 4.4E-4 7.7E-4 7.7E-4 6.6E-4 9 1126 l.8E-6 8.5E-6 2.6E-5 8.lE-5 l.5E-4 3.2E-4 4.9E-4 10 1287 l.4E-6 6.4E-6 2.3E-5 7.3E-5 1.4E-4 2.8E-4 4.4E-4 11 1287 l.4E-6 6.4E-6 2.3E-5 7.3E-5 1.4E-4 2.8E-4 4.4E-4 12 2494 6.4E-7 l.3E-6 7.5E-6 2.7E-5 5.6E-5 l.2E-4 2.4E-4 13 1870 8.0E-7 2.7E-6 l.2E-5 4.2E-5 8.lE-5 l.8E-4 3.2E-4 14 1870 8.0E-7 2.7E-6 l.2E-5 4.2E-5 8.lE-5 l.8E-4 3.2E-4 15 1648 9.4E-7 3.9E-6 l.5E-5 5.0E-5 9.7E-5 2.lE-4 3.6E-4 16 1770 8.4E-7 3.3E-6 l.3E-5 4.5E-5 8.8E-5 l.9E-4 3.4E-4

IPECSITE NON-QUALITY RELATED IP-EP-310 Revision 20 EMERGENCY PLAN PROCEDURE IMPLEMENTING PROCEDURE Page 15 Of 22 REFERENCE USE Attachment 9.4 Accident Monitoring of Noble Gas Concentrations in the Plant Vent Sheet 1 of 2 NOTE

1. The Operations Support Center (OSC) Rad/Chem Coordinator will determine which reading to obtain first; plant vent or back-up plant vent monitoring.
2. Locations and equipment may be different from Unit 2 or Unit 3 Radiation readings may be, obtained on the plant vent by the following:
a. Follow the provisions used by the OSC to plan and track team assignments.
b. Use a telescoping radiation monitoring instrument (e.g. teletector or equivalent) to perform this function.

C. As requested by OSC Rad/Chem Coordinator or Control Room (CR},

REPORT radiation levels.

d. Proceed to the Containment Airlock area.
e. Using the fan-building wall for shielding, obtain radiation readings by Vapor Containment purge and exhaust ducts.
f. CAUTION The door leading out to the plant vent area may lock when closed. To prevent being trapped in the plant vent area, BLOCK OPEN THE DOOR prior to going to the plant vent area.
g. Proceed through the door to the plant vent area.
h. Obtain radiation readings at the following locations:
i. 6 feet from the plant vent 10 feet above the floor.
j. Contact with the plant vent 10 feet above the floor.
k. Notify the OSC or CR that radiation readings have been obtained and follow instructions as directed .

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IPECSITE NON-QUALITY RELATED PROCEDURE IP-EP-310 Revision 20 EMERGENCY PLAN

  • IMPLEMENTING PROCEDURE REFERENCE Attachment 9.4 Use Page Accident Monitoring of Noble Gas Concentrations in the Plant Vent 16 Of 22 Sheet 2 of 2 Backup plant vent monitoring readings may be obtained by the following:
a. Request a team be dispatched to obtain and analyze Plant Vent Sample.
b. IF a sample from the plant vent is required from Unit 2 THEN follow chemistry procedure 2-CY-3940 "Plant Vent Sampling During Accident Conditions"
c. IF a sample from the plant vent is required from Unit 3 THEN follow Chemistry procedure 3-CY-3920 "Sampling Containment Atmosphere and Plant Vent During Accident Conditions"
d. Report the results to the OSC or CR and FOLLOW INSTRUCTIONS as directed .

IPECSITE NON-QUALITY RELATED IP-EP-310 Revision 20 EMERGENCY PLAN PROCEDURE IMPLEMENTING PROCEDURE 22 REFERENCE USE Page 17 Of Attachment 9.5 Determination of Noble Gas Release Rate - Discussion Sheet 1 of 2 The following instrumentation/methodology can be used to determine the noble gas release rate.

  • Plant vent monitor-low range (Direct Readout)
  • Plant vent monitor-high range (Direct Readout)
  • Plant vent survey-hand neld instrument or remote readout
  • Isotopic analysis of sample taken from release point
  • Condenser air ejector monitor (Direct Readout).
  • . Back-calculating a release rate based on actual field radiological data .

Containment radiation monitors R-25 and R-26 to measure the source term within containment and to estimate potential releases from containment.

Potential exposure to the population if a future release of the existing containment source term occurs, utilizing the following information:

1. Containment pressure relief line contains three isolation valves (one in containment and two outside).
2. Containment purge system contains two isolation valves on the Inlet Duct (one in containment and one outside).
3. Containment purge system contains two isolation valves on the Exhaust Duct (one in containment and one outside).
4. Weld Channel (WC) and Isolation Valve Seal Water System (IVSWS) are pressurized to ensure that during accident conditions, a pressure build up to AT LEAST 50 psi in containment would NOT cause a leak of radioactive material to the environment as long as the isolation valves remained in the closed position .

ta IPECSITE NON-QUALITY RELATED IP-EP-310 Revision 20

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EMERGENCY PLAN PROCEDURE IMPLEMENTING PROCEDURE REFERENCE USE 18 Of 22 Page Attachment 9.5 Determination of Noble Gas Release Rate - Discussion Sheet 2 of 2 *

5. WITHOUT WC AND IVSWS, BUT with isolation valves closed, the containment leak rate is expected to be LESS THAN 0.1 % of the containment volume per day (Tech Spec) WITH a pressure buildup to 50 psi inside containment. At lower pressures the leak rate would be smaller, approaching zero as the pressure differential approaches zero.
6. Containment Volume = 2.6 x 106 ft 3 = 7.4 x 1010 cc
7. For Post-Steam Generator Tube Rupture (SGTR) cool-down using blow-down situations, the determination of the gaseous release rate from the blowdown flash tank SHALL be accomplished by determining the noble gas concentration in the faulted SG blowdown (Chem sample µCi/cc) AND the blowdown rate (GPM).
8. Complete Form EP-32, Determination of Radioactive Airborne Concentrations by using the following general formula when applying Airborne Sample Data to determine concentration or release rnte. This is for a 10 cubic foot sample.
a. NG Release Concentration, µCi/cc =

mR/hr in field DCF, mR/hr per µCi/cc

b. NG Release Rate, Ci/sec =

Concentration(Ci/m 3)

  • Wind Speed (m/sec)

Xµ/Q (m- 2)

Note That µCi/cc = Ci/m 3

IPECSITE NON*QUALITY RELATED IP-EP-310 Revision 20 EMERGENCY PLAN PROCEDURE IMPLEMENTING PROCEDURE Of 22 REFERENCE USE Page 19 Attachment 9.6 Determination of Noble Gas to Iodine Concentration and Dose Rate Ratios from -

Field Monitoring Data Sheet 1 of 2 Part 1 - Flow Chart - Gamma Dose Rates, and NG and Iodine Air Sample Concentrations Obtain Gamma Reading at a = mremlhr location in the plume (mrem/hr)

(G) (Time after S!Jutdown, Hrs)

NGDCF Determine Noble = (G) mremlhr I DCF (mrem/hr per ucilcc)

Gas Activity (uCi/cc) = uCi/cc (NG Cone.)

l Obtain Iodine Sample at same location as = II 1-1 IJ 14.6 E-9 II X j 10 cu ft gamma reading the plume

= [ I (cpm) - 8kg (cpm) J x 4.6 E-9 I Sample Vol (ff3) *

= uCi/cc (I Cone.)

  • Equation based on frisker efficiency (of about 0.0034 cpmldpm) and the conversions of dpm to uCi and cu. ft. to cc. * ,,

frost.f GAS 005E tOOVIER5IDtJ FACTORS K1 NIOle 1BooJ at Time After~ for i-ioblle Gas Dose f.JobleGas OCF Time a iW.down ~GB OCf (mRemlbr pe1" peii'<<) (boors) mRie-ml'hr ~ ~'cc) 1.21E+.5, 2:.5-3.5 tbJm 3.5-4.5 liotlB

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IPECSITE EMERGENCY PLAN NON-QUALITY RELATED PROCEDURE IP-EP-310 Revision 20 IMPLEMENTING PROCEDURE REFERENCE USE Page 20 Of 22 Attachment 9.6 Determination of Noble Gas to Iodine Concentration and Dose Rate Ratios from Field Monitoring Data Sheet 2 of 2 Part 2 - Flow Chart - Ratio Determinations Concentration Dose Conversion Dose Rate (uCi/cc) Factor (mrem/hr (mrem/hour) per uCi/cc)

Noble Gas (Whole Body)

Iodines* 8.0 E+S I (CDE-Thy)

Ratio NG/ Iodine (Whole Body/ CDE-Thy)

N/A (1) (2)

  • Note: if time is > 24 hr, then use an iodine dose conversion factor of 2.6 E+9.

(1) NG / Iodine Concentration Ratio:

Use NG/I concentration ratio for future release rates for dose projection calculations.

(2) Dose Rate Ratio:

  • IF the dose rate ratio is about 0.2 or higher, THEN noble gas (whole body/TEOE) dose rates will be more limiting than iodine (COE-Thy) dose rates. (i.e., Whole Body/TEOE will reach PAG limit before iodine/ COE-Thy).
  • IF the dose rate ratio is less than about 0.2, THEN iodine (COE-Thy) dose rates will be more limiting than noble gas (whole body/TEDE) dose rates. (i.e., COE-Thy dose will reach PAG limit before Whole Body/TEDE) .
  • Note: The above calculation is for one location at one time a few hours after plant shutdown. If practical, 3 or more such determinations of NG/I ratios from multiple locations should be performed.

~

IPECSITE NON-QUALITY RELATED IP-EP-310 Revision 20

'@ f.}1/e,gy!J, EMERGENCY PLAN PROCEDURE IMPLEMENTING PROCEDURE REFERENCE USE Page 21 Of 22 Attachment 9.7 Use of Chemistry Sample to Determine Radioiodine Release Rate and Thyroid Dose Conversion Factor Sheet 1 of 2 Part 1 - Determine Radioiodine Release Rate Based on Chem. Sample Multiply [iodine uCi/cc] x [volume or mass release rate] x [constant]= iodine Ci/sec For plant vent or air ejector:

uCi/cc iodine Cfm Constant (1) Iodine Ci/sec 4.?0E-04 For main steam line release uCi/cc iodine lbm/hr Constant (2) Iodine Ci/sec 3.2 E-6 For steam generator blow down release uCi/cc iodine Gpm Constant (3) Iodine Ci/sec 6.30E-05 (1) constant converts uCi/cc x cfm to Ci/sec, using Ci/uCi, cc/cu ft, and min/sec (2) constant converts uCi/cc x lbm/hr to Ci/sec, using Ci/uCi, expected steam density, and hr/sec (3) constant converts uCi/cc x gpm to Ci/sec, using Ci/uCi, cc/gal, and min/sec

~ IP-EP-310 Revision 20 IPECSITE NON-QUALITY RELATED

~Ertlerg}f; $, EMERGENCY PLAN PROCEDURE i IMPLEMENTING PROCEDURE REFERENCE USE 22 Of 22 Page Attachment 9. 7 Use of Chemistry Sample to Determine Radioiodine Release Rate and Thyroid Dose Conversion Factor Sheet 2 of 2 Determination of Iodine Dose Factor Based on Chem. Sample Sample Date Sample Time Sample Description and Unit of Measurement (e.g.,

uCi/cc)

  • Col.1 Iodine lsoto es Col. 2 Thyroid Dose Conv. Factor K2 Col.3 Concentration of Iodine lsoto es .

Col. 4 = Col 2 x 3 Weighted Conversion Factor 1-131 2.60E+09 1-132 1.50E+07 1-133 4.40E+08 1-134 2.60E+06 1-135 7.60E+07 Total NIA Wtd, K2 = sum of K2 = mrad/hr per uCi/cc Iodine (mrad Col. 4 divided by COE-Thy per hour breathed) sum of Col. 3

ATTACHMENT 9.1 10 CFR 50,54(a)(2) REVIEW SHEET20F2 Procedure/Document Number: IP*EP-31 O Revision:20 Equipment/Facility/Other: Indian Point Energy Center

Title:

Dose Assessment Part IV. Maintaining the Emergency Plan Conclusion The questions In Part II do not represent the sum total of all conditions that may cause a change to or impact the ability to maintain the emergency plan. Originator and reviewer signatures in Part IV document that a review of all elements of the proposed change have been considered for their impact on the ability to maintain the emergency plan and their potential to change the emergency plan.

1. Provide a brief conclusion that describes how the conditions as described in the emergency plan are maintained with this activity.
2. Check the box below when the 10 CFR 50.54(q)(2) review completes all actions for all elements of the activity- no 10 CFR 50.54(q)(3) screening or evaluation is required for any element. Otherwise, leave the checkbox blank.

181 t have completed a review of this activity in accordance with 10 CFR 50.54(q)(2) and determined that the effectiveness of the emergency plan Is maintained. This activity does not make any changes to the emergency plan.

No further actions are required to screen or evaluate this activity under 10 CFR 50.54(q)(3).

A review of this activity in accordance with 10CFR 50.54(q)(2) has been completed and determined that the effectiveness of the emergency plan is maintained. This* revision on the Dose Assessment procedure updates the procedure revision number, since the last revision (Rev 19) had some pages mistakenly identifying it as Rev 18. There are no changes being made to the content of the procedure. The change made to IP-EP-31 Odo not require a change to the Emergency Action Level scheme, On shift staffing study, or the IPEC Emergency Plan. No further actions are required to screen or evaluate this activity under 10 CFR 50.54(q)(3) .

  • Part V. Signatures:

Preparer Name (Print)

Craig Delamater (Optional) Reviewer Name (Print) ignature Reviewer Signature Date:

Reviewer Name (Print) Date:

Timothy F. Garvey ..--,~Reviewefos gnature Nuclear EP Project Manager  : VV'- '\/I.A,,--"\ '2- Y: l-i..o Reviewer Name (Print) R viewer Signature Date:

Frank J. Mitchell Manager, Emergency Planning or designee #!dc:D ~Ii/po!Jt7

Change Page/Section IP-EP-310, ~e Assessment (Revision 20 in eB) Revision Matrix Previous Version (19) New Version (20) Editorial Effect on 10 CFR 50.47(b)

No. Change Planning Standards or NUREG-0654 program elements? Justify if NO.

1. Cover Page Rev 19 Rev20 Yes No- This is an editorial change to

' the Revision number and effective date.

The meaning or intent of description in the emergency plan, facilities or equipment described in the Emergency Plan or a process described in the Emergency Plan are not affected by this change. No further evaluation is required for this change.

2. Page 1-10 Header Revision 19 Revision 20 Yes No- This is an editorial change to the Revision number and effective date.

The meaning or intent of description in the emergency plan, facilities or equipment described in the Emergency Plan or a process described in the Emergency Plan are not affected by this change. No further evaluation is required for this change.

IP-EP-310, Dose Assessment *

(Revision 20 in eB) Revision Matrix Change Page/Section Previous Version (19) New Version (20) Editorial Effect on 10 CFR 50.47(b)

No. Change Planning Standards or NUREG-0654 program elements? Justify if NO.

3. Page 11 - 22 Header Revision 18 Revision 20 Yes No- This is an editorial change to the Revision number and effective date.

The meaning or intent of

- description in the emergency plan, facilities or equipment described in the Emergency Plan or a process described in the Emergency Plan are not affected by this change. No further evaluation is required for this change.

IPEC IMPLEMENTING PROCEDURE IP-SMM-AD-102 Rev: 16 PREPARATION, REVIEW, AND APPROVAL Page 35 of 43 ATTACHMENT 10.2 IPEC PROCEDURE REVIEW AND APPROVAL (Page 1 of 1)

Procedure

Title:

Dose Assessment Procedure No. IP-EP-310 Existing Rev: 19 New Rev: 20 ORN/EC No: 20-00063 Procedure Activit!l D Converted To IPEC, Replaces: TemE!orar!Jl Procedure Change (MARK Applicable) (MARK Applicable)

D NEW PROCEDURE Unit 1 Procedure No. EDITORIAL Temporary Procedure Change D

D GENERAL REVISION D ADVANCE Temporary Procedure Change D PARTIAL REVISION IX! EDITORIAL REVISION Unit2 Procedure No: D CONDITIONAL Temporary Procedure Change D VOID PROCEDURE Terminating Condition:

D SUPERSEDED Unit 3 Procedure No:

D RAPID REVISION Document in Microsoft Word:

D Yes D No D VOID DRN/TPC No(s):

Revision Summary x N/A - see Revision Summary Matrix.

Implementation Reguirements Implementation Plan? D Yes IX! No Formal Training? D Yes OONo Special Handling? D Yes IX!No RPO Dept: Emergency Planning Writer: (Print Name/ExVSign):-=D=-=a""-ra:::....;::G:..:..:ra::ay""'/8"-4;....:1c.....:4,_/- - - - ~ - - - -

Review and AE!E!roval (Per Attachment 10.1, IPEC Review And Approval Requirements)

  • J//.;'i,bo :u,
1. IX! Technical Reviewer: Craig Delamater/

' (Print Name/ Signature/ Date)

2. D Cross-Disciplinary Reviewers:

Dept: Reviewer:

Print Name/ Signature/ Date)

Dept: Reviewer:

_ / , / Print Name/ Signature/ Date) *

3. 00 RPO- Responsibilities/Checklist: FrankJMitchell/ ~V 11/'~

(Print Name/ Signature/ Date)

,J!t/Jtj;JO D PAD required and is complete (PAD Approver and Reviewer qualifications have been verified) 00 Previous exclusion from further Ll-100 Review is still valid 00 PAD not required due to type of change as defined in 4.6 4 . ~ Non-Intent Determination Complete: Dara Gray

~,A.1..,...~..,,... ...=,,"-\'=z;..<<-+--l ---'-........:=-=---'== ==c.==------

t--'2-~-'2 zO (P. int me Si nature/ Date)

NO change of purpose or scope NO change o ess restrictive acceptance criteria NO reduction in the level of nuclear safety NO change to steps previously identified as commitment steps

  • No voiding or canceling of a procedure, unless NO deviation from the Quality Assurance Program Manual requirements are incorporated into another procedure NO change that may result in deviations from Technical or the need for the procepure was eliminated Specifications, FSAR, plant design requirements,
5. D On-Shift Shift Manager/CRS:

(Print Name/ Signature/ Date)

6. D User Validation: User:
7. D Special Handling Requirements Understood:

(Print Name/ Signature/ Date)

a~Entergy IPEC NON-QUALITY RELATED IP-EP-AD2 Revision 12 EMERGENCY PLAN PROCEDURE ADMINISTRATIVE PROCEDURES REFERENCE USE Page  ! of 1 Attachment 9.1 Emergency Planning Document Change Checklist Form (All sections must be completed, N/A or place a check on the line where applicable)

Section 1 Doc/Procedure Type:

AdministrativeD lmplementinq IXI EPLAN n N/An Doc/Procedure No: IP-EP-310 Doc/Procedure

Title:

Dose Assessment New revision number: 20 Corrective Action: YesD No IZJ Effective date:

Section 2

  • 1.

Change Description Ensure the following are completed, or are not applicable and are so marked:

a. 50.54q
b. EN-FAP-OM-023 181 N/AO D N/A 181
c. IP-SMM-AD-10 2 181 N/AO

.d. OSRC D N/A 181

e. NRC Transmittal
  • D N/A181 (within 30 days)
2. List any other documents affected by this change: _ _
3. Transmittals are completed: D N/A I&! Date:-1f#-/).P l.D
4. Ensure the proper revision is active in eB Ref. Lib.:~ N/A D
5. Approved doc/procedure delivered to Doc. Control for distribution: D N/A ~ Date: ;;Jd2v2.D
6. Position Binders updated: D N/A D Date: :i I 1o /~o;)..D
7. Copy of EPDCC placed in EP file: D N/A D Date: _ _
8. Supporting documentation is submitted as a general record in eB Ref. Lib.: D N/A ~ Date: ,)./ s-/,)..o;;,..o
9. Word files are moved//°;m working drafts folder to current revision folder in the EP drive:

D NIA D Date: ~ 10 .;w~o

  • Sheet 1 of 1
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