ML030440507

Emergency Plan Implementing Procedure (EPIP) Revisions

ML030440507
Person / Time
Site:	Browns Ferry
Issue date:	02/06/2003
From:	Abney T Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
-RFPFR
Download: ML030440507 (38)

Text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 February 6, 2003 10 CFR Part 50, App E U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop OWFN, P1-35 Washington, D.C. 20555-0001 Gentlemen:

In the Matter of ) Docket Nos. 50-259 Tennessee Valley Authority ) 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - UNITS 1, 2, and 3 EMERGENCY PLAN IMPLEMENTING PROCEDURE (EPIP) REVISIONS TVA is submitting this notification in accordance with the requirements of 10 CFR Part 50, Appendix E, Section V.

Specifically, several EPIPs were revised: (1) EPIP-13, Revision 10; (2) EPIP-15, Revision 7; and (2) EPIP-17, Revision 27. The revisions have an effective date of January 27, 2003. Additionally, EPIP-21 was canceled on January 27, 2003; therefore, please remove EPIP-21, Revision 3.

The enclosed information is being sent by certified mail.

The signed receipt signifies that you have received this information. If you have any questions, please telephone me at (256) 729-2636.

S'ncerely,

.\ E. E. "

Manage -cens hg a Industry Af irs c : See Page 2 Pnted on mcycled pao

U.S. Nuclear Regulatory Commission Page 2 February 6, 2003 cc (Enclosure):

NRC Resident Inspector (Enclosure provided by Browns Ferry Nuclear Plant BFN Document Control Unit) 10833 Shaw Road Athens, Alabama 35611-6970 Mr. Stephen J. Cahill, Branch Chief (2 Enclosures)

U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street S.W., Suite 23T85 Atlanta, Georgia 30303-8931 Mr. Kahtan N. Jabbour, Senior Project Manager (w/o Enclosure)

U.S. Nuclear Regulatory Commission One White Flint, North (MS 08G9)

Office of Nuclear Reactor Regulation 11555 Rockville Pike Rockville, Maryland 20852-2738

ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 EMERGENCY PLAN IMPLEMENTING PROCEDURE (EPIP) REVISION EPIP-13, EPIP-15, EPIP-17, and EPIP-21 SEE ATTACHED

GENERAL REVISIONS FILING INSTRUCTIONS FILE DOCUMENTS AS FOLLOWS:

PAGES TO BE REMOVED PAGES TO BE INSERTED EPIP-13, Revision 9 EPIP-13, Revision 10 EPIP-15, Revision 6 EPIP-15, Revision 7 EPIP-17, Revision 27 EPIP-21, Revision 3 NONE

• • Revision 26 of EPIP-17 deleted the "ORIGINAL" EPIP 17.

Therefore, there is no revision to remove.

Additionally, the "NEW" EPIP-17 (formally EPIP-21) was assigned EPIP-17 revision number 27 to ensure that revisions to the "ORIGINAL" EPIP-17 would be retrievable. This "NEW" revision now makes the EPIP 17 subject matter consistent with TVA's other nuclear EP programs.

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-13 DOSE ASSESSMENT REVISION 10 PREPARED BY A. H FELTMAN PHONE: 3666 RESPONSIBLE ORGANIZATION EMERGENCY PREPAREDNESS APPROVED BY JEFF LEWIS DATE 01/23/2003 EFFECTIVE DATE 01/27/2003 LEVEL OF USE: REFERENCE USE QUALITY-RELATED

REVISION LOG Procedure Number: EPIP-13 Revision Number: 10 Pages Affected: 3, 4, 7, 11, 12, 15 &19 Pagination Pages: ALL Description of Change:

IC-10 The Dose Assessment portion of EPIP-14 Nias removed and placed in EPIP-13 as a part of EP Standardization EPIP-13. "Chemistry Procedure" i~as replaced Nlith the Dose Assessment process Applicable portions of EPIP-13 were placed into EPIP-7. Neither SQN or WBN have a "'Chemistry Procedure". The EP Peer Team recommended reN ising EPIP-13 to become the "Dose Assessment" procedure.

IC-1I This rc isbn is being conducted to incorporate comments made dunng the 2003 Dose Assessment Training. The reN ision mnvoh es the correction of t pograplucal errors on Attachment B. page 1 of 8. and Attachment A & B page 2 of 8. Revise the Noble Gas Section Release Rate concerning SPDS History to more effectively obtain the release history reN mew. Re ise the location for documenting ind speeds to ensure that meters per second is recorded and add a conversion for miles per hour to meters per second.

Human factor Attachment C with larger blanks for recording data and collection/documentatmon arrangement

DOSE BROWNS FERRY ASSESSMENT EPIP-13 NUCLEAR PLANT 1.0 PURPOSE The purpose of this procedure is to describe actions and responsibilities of Radiological Controls (RADCON) personnel during an assessment of environmental radiological conditions at Browns Ferry.

2.0 SCOPE EPIP-13 will be initiated when the RADCON Shift Supervisor or designee is requested or requires information regarding dose assessment.

EPIP-13 contains instructions for RADCON regarding methods for Projecting Total Effective Dose Equivalent (TEDE) and Thyroid Committed Dose Equivalent (CDE) from airborne radioactivity releases The method for projecting TEDE and/or CDE from airborne radioactivity releases may be requested by operations to support emergency classification and/or protective action recommendations The use of this method should only be utilized in the absence of more sophisticated dose models, when the Central Emergency Control Center (CECC) is not activated.

3.0 INSTRUCTIONS 3.1 Method for Proiecting Total Effective Dose Equivalent (TEDE) and Thyroid Committed Dose Equivalent (CDE) from Airborne Radioactivity Releases The method for Projecting TEDE and Thyroid CDE from Airborne Radioactivity Releases is by manual method through the application of matrix tables and calculations.

3.1.1 Manual Method for Projecting TEDE and Thyroid CDE from Airborne Radioactivity Releases 3.1.1.1 The Radcon Shift Supervisor/designee or the TSC Radcon representative is responsible for completing Attachment A of this procedure when releases involves a stack release or Attachment B when the release involves a building or ground level release. The results of the completed attachment "A" and "B" should then be summarized on attachment "C" and forwarded to the Shift Manager /

Site Emergency Director.

PAGE 1 OF 19 REVISION 10

DOSE BROWNS FERRY ASSESSMENT EPIP-13 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.1.1.2 This method for projecting the TEDE and Thyroid CDE from airborne radioactivity releases should only be utilized in the absence of more sophisticated dose models 3.1.1.3 This method may be requested by the Shift Manager prior to any emergency classification declaration. Results of this method may be utilized to classify emergency conditions, make protective action recommendations or by TSC personnel conducting evaluations of current plant conditions.

3.1.1.4 When requested the appropriate attachment of this procedure should be completed immediately and the results reported to the Shift Manager or SED.

4.0 ATTACHMENTS Attachment A Projecting Total Effective Dose Equivalent (TEDE) and Thyroid Committed Dose Equivalent (CDE) from Stack Airborne Radioactivity Releases Attachment B - Projecting Total Effective Dose Equivalent (TEDE) and Thyroid Committed Dose Equivalent (CDE) from Ground Level Airborne Radioactivity Releases Attachment C - Projected TEDE and Thyroid CDE Assessment Survey Form PAGE 2 OF 19 REVISION 10

DOSE BROWNS FERRY ASSESSMENT EPIP-I NUCLEAR PLANT ATTACHMENT A (Page I-of 8)

PROJECTING TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) FROM STACK AIRBORNE RADIOACTIVITY RELEASES CAUTION: USE THIS ATTACHMENT FOR STACK RELEASES ONLY DETERMINE RELEASE PATHWAY Contact the affected unit, Unit Supervisor to obtain information regarding the release pathway. The two pathway options for a stack release are; (1) stack (filtered) and (2) stack (unfiltered). Remember that when multiple pathways such as, Stack and Ground-Level, are experienced, both pathway calculations should be conducted and the results summed and recorded on Attachment C, the projected TEDE Thyroid CDE assessment survey form.

Record data on page 5 of this attachment.

DETERMINE ESTIMATED RELEASE START TIME AND RELEASE DURATION Contact the affected unit, Unit Supervisor to obtain'information regarding the release start time and duration. Record release duration in hours. If the release duration can not be determined by operations, then a default duration of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> should be utilized.

Record data on page 5 of this attachment.

DETERMINE NOBLE GAS RELEASE RATE IN 4CI/SECOND The Noble Gas Release Rate should be calculated utilizing data obtained from the SPDS terminals under the screen name "MISCRAD". From this screen use the "F5" key to view a tabular form of the instruments utilized by the previous screen. Collect data described as "WIDE RANGE GASEOUS EFFL RAD MON and STACK FLOW".

If the value for the "WIDE RANGE GASEOUS EFFL RAD MON" is equal to or less than 0 00, then discontinue the dose assessment and report that there are no off-site TEDE concerns for the stack release Utilize SPDS history to obtain the highest release concentration for the incident. It is recommended that data be reviewed from history approximately one hour (60 minutes) prior to the estimated start time as referenced in the preceding step. Then step through to the 30 minute period prior to the estimated start time using the F4 key. (It is recommended that data be retrieved at frequency of every 10 minutes or 600 seconds) Place the highest release concentration data in the applicable calculation fields The completed calculation provides the Noble Gas Release Rate Record and utilize this rate for the dose assessment calculations If SPDS is unavailable, notify affected unit, operations personnel, to gain the information utilizing control room instrumentation, or if unavailable notify the Shift Manager/Site Emergency Director that TI 67, "Determination of Stack and Hardened Wetwell Vent Release Rates" (backup mrrethod), procedure must be performed by Radcon and Chemistry personnel.

The following conversion chart can be utilized to convert curies to microcuries.

To CONVERT MULTIPLY BY To OBTAIN 6 ItCI Ci 1.0 X 10 Record data on page 5 of this attachment PAGE 3 OF 19 REVISION 10

DOSE BROWNS FERRY ASSESSMENT EPIPV-13 NUCLEAR PLANT ATTACHMENT A (Page 2 of 8)

DETERMINE RELEASE TYPE Contact the Plant Assessment Team, Core Damage Assessor (5-751-1633) in the CECC to determine the applicable release type. If the Core Damage Group in the CECC can not be contacted, then use the default release type, "Type 2" The four release type options are; (1) "Type 1", Reactor Coolant System Leakage Release, (2) "Type 2" Fuel Cladding GAP Release, (3) "Type 3", Fuel Over Temperature Release, and (4) "Type 4", Fuel Melt.

Some release types have an additional "F" indicator, this implies that the release type has a filtered release pathway.

Record data on page 5 of this attachment.

DETERMINE METEOROLOGICAL DATA Met data should be obtained from the SPDS terminals under screen name "METDATA" or by accessing the "Met Data Terminal" located in the Technical Support Center.

For stack releases record measurements at the 91 meter instrument readings.

If all Met Data Collection Methods are unavailable contact the National Weather Service by dialing 9-1 205-621-5650 The National Weather Service will provide wind speed and wind direction The default value for stability class with no met data available is "D" for stack releases The default value for wind speed with no met data available is 4 0 meters/second for the stack.

Record the following data on page 5 of this attachment.

"* STABILITY CLASS Note: Stability Class may be electronically displayed as 1,2,3. . This corresponds to A,B,C....

"* WIND SPEED IN METERS/SECOND The following conversion chart can be utilized for conversions to meters/second To CONVERT MULTIPLY BY To OBTAIN MILES/H 0.45 METERS/SEC METERSISEC 2.2 MILES/H KNOTS 0.5 METERS/SEC

"* WIND DIRECTION IN DEGREES

"* PLUME DIRECTION IN DEGREES NOTE: To OBTAIN PLUME DIRECTION, ADD 1800 TO WIND DIRECTION IF < 1800 OR SUBTRACT 1800 IF WIND DIRECTION IS> 1800.

PAGE 4 OF 19 REVISION 10

DOSE BROWNS FERRY ASSESSMENT EPIP-13 NUCLEAR PLANT ATTACHMENT A (Page 3 of 8)

DETERMINE THE TEDE FACTOR In determining the TEDE Factor you must know the stability class and the wind speed.

Locate the "TEDE Factor" table that corresponds to the applicable stability class located on page 7 of this attachment.

Locate the column within the table that corresponds to the applicable wind speed If wind speed falls between the two column variables choose the lower value, this is the more conservative factor.

Determine data for the 0.62, 2 and 5 mile distances.

Record data on page 5 of this attachment.

DETERMINE THE TEDE RATIO In determining the TEDE Ratio you must know the release pathway and the release type.

Locate the "TEDE Ratio" table that corresponds to the applicable release pathway located on page 8 of this attachment Locate the column within the table that corresponds to the applicable release type. Recall that the "F" indicator for some release types simply indicate that the release type is filtered.

Determine data for the 0 62, 2 and 5 mile distances Record data on page 5 of this attachment.

DETERMINE THE THYROID CDE RATIO In determining the Thyroid CDE Ratio you must know the release pathway and the release type.

Locate the "Thyroid CDE Ratio" table that corresponds to the applicable release pathway located on page 8 of this attachment Locate the column within the table that corresponds to the applicable release type. Recall that the "F" indicator for some release types simply indicate that the release type is filtered Determine data for the 0.62, 2 and 5 mile distances Record data on page 5 of this attachment PAGE 5 OF 19 RE'VISION 10

DOSE BROWNS FERRY ASSESSMENT EPIP- 13 NUCLEARPLANT ATTACHMENT A (Page 4 of 8)

Complete CALCULATIONS AND ATTACHMENT C Input data into applicable calculation fields and calculate Use caution to input correct factors and ratios for the different mile indications.

Note, to complete the Thyroid CDE calculation, the TEDE calculation must be completed and the TEDE value utilized Also use caution when inserting values into the calculations Use correct terms, i e meters/second verses miles/hour.

COMPLETE ATTACHMENT C, PROJECTED TEDE AND THYROID CDE ASSESSMENT SURVEY FORM, AND FORWARD TO THE SHIFT MANAGER OR THE SITE EMERGENCY DIRECTOR. ENTER TEDE VALUES IN REM/HR ON ARROWS FOR APPLICABLE MILEAGE RINGS. SHOW PLUME DIRECTION ON SURVEY MAP BY THE USE OF AN ARROW.

PAGE 6 OF 19 REVISION 10

DOSE BROWNS FERRY ASSESSMENT EPIP-13 NUCLEAR PLANT ATTACHMENT A-(Page 5 of 8)

Stack Release Data Collection and Calculation Worksheet RELEASE PATHWAY [] STACK (FILTERED) [: STACK (UNFILTERED)

ESTIMATED RELEASE START TIME ESTIMATED RELEASE DURATION NOTE' IF AN ESTIMATED RELEASE DURATION IS UNKNOWN USE 4 HOUJRS AS THE DEFAULT RELEASE DURATION.

NOBLE GAS RELEASE RATE NOBLE GAS CONCENTRATION _ _tCI/CC FLOW RATE SCFM

( __ _ tCI/cC) X( SCFM) X( 472 ) = _I.tCI/SECOND RELEASE CONC FLOW RATE CONVERSION FACTOR RELEASE RATE NOBLE GAS RELEASE RATE I.tCI/SECOND RELEASE TYPE El TYPE 1F (FILTERED) El TYPE 1 (UNFILTERED)

El TYPE 2F (FILTERED) El TYPE 2 (UNFILTERED)

El TYPE 3F (FILTERED) El TYPE 3 (UNFILTERED)

[E TYPE 4F (FILTERED) El TYPE 4 (UNFILTERED)

NOTE: TYPE 2 IS THE DEFAULT RELEASE TYPE ,

STABILITY CLASS. WIND SPEED METERS/SECOND

( _MILES/HOUR X 0.45 = METERS/SECOND)

WIND DIRECTION DEGREES PLUME DIRECTION DEGREES TEDE FACTOR R 62 MILES 0 MILES

.0 MILES TEDE RATIO 0.62 MILES 2.0 MILES 5.0 MILES THYROID CDE RATIO 0 62 MILES 2.0 MILES 5 0 MILES PAGE 7 OF 19R REVISION 10

DOSE BROWNS FERRY ASSESSMENT EPIP-13 NUCLEAR PLANT ATTACHMENT A (Page 6 of 8)

Stack Release Data Collection and Calculation Worksheet TEDE DOSE ASSESSMENT CALCULATIONS 0.62 - 1.99 MILES

( _ ) X ( _ _ cI/S) X ( HOURS) X ( _ ) = TEDE REM TEDE FACTOR RELEASE RATE RELEASE DURATION TEDE RATIO 2.00 - 4.99 MILES

( ) X ( c,/s) X ( HOURS) X( ) =( TEDE REM TEDE FACTOR RELEASE RATE RELEASE DURATION TEDE RATIO 5.00 - 10.00 MILES

( _ _ ) X ( __ CI/S) X ( HOURS) X ( __ ) -_ TEDE REM TEDE FACTOR RELEASE RATE RELEASE DURATION TEDE RATIO THYROID CDE DOSE ASSESSMENT CALCULATIONS 0.62 - 1.99 MILES

( TEDE R x ( THYROID CDE RATIO ) =

T EREM THYROID CDE REM 2.00 - 4.99 MILES

( TEDE TD REM R x ( THYROID CDE RATIO ) = THYROID CDE REM 5.00 - 10.00 MILES THYROID CDE REM TEDE REM THYROID CDE RATIO COMPLETE ATTACHMENT C AND FORWARD TO SM/SED.

PAGE 8 OF 19 REVISION 10

DOSE BROWNS FERRY ASSESSMENT EPIP-13 NUCLEAR PLANT ATTACHMENT A (Page 7 of 8)

TEDE Factor (rem/h per pCi/s) from a BFN Stack Release Stability A wind speed miles 1 M/s 2 m/s 3 m/s 4 m/s 5 m/s 6 m/s 7 m/s 8 Mrs S9m/s 10Dm/s 0 62 mJ 1 1E-09 6 OE-10 4 8E-10 3 6E-10 2 4E-10 2 2E-10 1 9E-10 1 7E-10 1 4E-10 1 2E-10 4.4E-10 2 2E-10 1 8E-10 1 3E-10 8 7E-11 7 8E-11 '7 CE-11 6 1E-11 5 2E-11 4 4E-11 2 mi 4 8E-11 4 4E-11 4 0E-11 3 6E-11 3 2E-11 2 8E-A1 2 4E-11 2 0E-11 Stability B wind speed miles 1 M/s 2 mls 3 m/s 4 mIs 5 m/s 6 m/s 7 m/s 8 m/s 9 mls 10 Mrs 062 2 3E-09 1.1E-09 9 3E-10 7 1E-10 4.9E-10 4 4E-10 3 9E-10 3 4E-10 2 9E-10 2 4E-10 2 6 5E-10 3.3E-10 2 7E-10 2 0E-10 1.3E-10 1 2E-10 1 1E-10 9 4E-11 8 0E-11 6 6E-11 5 9 9E-11 6 8E-11 6.6E-11 6 5E-11 6 4E-11 5.8E-11 5 1E-11 4 5E-11 3 9E-11 3 2E-11 Stability C wind speed miles 1 mIs 2 m/s 3 m/s 4 m/s 5 m/s 6 m/s 7 m/s 8 m/s 9 m/s 10 m/s 062 2 0E-09 1 1E-09 9 2E-10 7 OE-10 4 8E-10 4 4E-10 3 9E-10 3 4E-10 2 9E-10 2 5E-10 2 1 4E-09 8 1E-10 6 5E-10 4 9E-10 3 3E-10 3 0E-10 2 7E-10 2 3E-10 2 GE-10 1 7E-10 5 1 6E-10 1 1E-10 1 IE-10 1 1E-10 1 1E-10 1 OE-10 9 0E-11 7.9E-11 6 7E-11 5 5E-11 Stability D wind speed miles 1 m/s 2 m/s 3 m/s 4 m/s 5 ms 6 m/s 7 mIs 8 ms 9 m/s 10 MI/s 062 1 7E-09 1 1E-09 8 9E-10 6 7E-10 4 6E-10 4 1E-10 3 7E-10 3 2E-10 2 8E-10 2 3E-10 2 1 9E-09 1 2E-09 9 8E-10 7.6E-10 5 3E-10 4 7E-10 4 2E-10 3 7E-10 3 2E-10 2 6E-10 5 4 OE-10 3.OE-10 3.1E-10 3 1E-10 3.2E-10 2 9E-10 2 6E-10 2 2E-10 1 9E-10 1.6E-10 Stability E wind speed miles 1 m/s 2 m/s 3 m/s 4 m/s 5 m/s 6 m/s 7 m/s 8 m/s 9 m/s 10 m/s 062 1.7E-09 1 2E-09 9 7E-10 7 4E-10 5 1E-10 4 6E-10 4 1E-10 3 6E-10 3 1E-10 2 6E-10 2 2 1E-09 1 3E-09 1 1E-0g 8 OE-10 5 5E-10 5 GE-10 4 4E-10 3 9E-10 3 4E-10 2 8E-10 5 6 DE-10 4 3E-10 4 4E-10 4 5E-10 4 6E-10 4 2E-10 3 7E-10 3 2E-10 2 8E-10 2 3E-10 Stability F wind speed miles 1 MI/s 2 m/s 3 m/s 4 m/s 5 m/s 6 m/s 7 m/s 8 mIs 9 m/s 10 MI/s 062 1.5E-09 9 9E-10 8 0E-10 6 1E-10 4 2E-10 3 8E-10 3 4E-10 2 9E-10 2 5E-10 2 1E-10 2 1 8E-09 1 2E-09 9 8E-10 7.6E-10 5 4E-10 4 9E-10 4.4E-10 3 8E-10 3 3E-10 2 8E-10 5 6 7E-10 4 9E-10 5.1E-10 5 2E-10 5 4E-10 4 9E-10 4 4E-10 3 8E-10 3 3E-10 2.8E-10 Stability G wind speed miles 1 MIs 2 m/s 3 m/s 4 m/s 5 m/s 6 m/s 7 m/s 8 m/s 9 m/s 10 m/s 062 1.5E-09 9 OE-10 7 3E-10 5 5E-10 3 8E-10 3 4E-10 3 OE-10 2 7E-10 2 3E-10 1 9E-10 2 1 6E-09 9 8E-10 8 1E-10 6 3E-10 4 6E-10 4 2E-10 3 7E-10 3 3E-10 2 8E-10 2 4E-10 5 5 4E-10 4 OE-10 4 3E-10 4 5E-10 4 8E-10 4 4E-10 3 9E-10 3 5E-10 3 OE-10 2 6E-10 PAGE 9 OF 19 REVISION 10

DOSE BROWNS FERRY ASSESSMENT EPIP-13 NUCLEAR PLANT ATTACHMENT A (Page 8 of 8)

TEDE RATIOS FOR VARIOUS PATHS AND RELEASE TYPES (STACK Release)

Stack (Filtered) STACK (unfiltered)

I I mii Type If Tp 2F1 1 Fype 3F Type 4F mi Type I Typ 2 T' pe3 Type 4 1.0 19 24 0.62 2

II 10 10 10 1.1 1.0 1.2 11 0 62 2

1.9 24 24 33 5.3 88 5 10 10 1.0 11 5 35 3 5 48 13.5 THYROID CDE RATIOS FOR VARIOUS ACCIDENTS AND RELEASE TYPES (STACK Release)

Stack (Filtered) STICK (unfiltered)

I Type 2 Tvpge 3 IL I 1i11 T)pe 1F Tpe 2F "r~pe 3F TN pe 4F 1111 T peC T) pe 4 0.62 1.6 E-03 1.6 E-037 6 E-03 1.4E-02 0.62 1 IE+0 E01.1E+00 3 6E-01 3.IE-01 4 4 E-02 4 4 E-02 1 7 E-02 2

6.9 E-02 6 9 E-02 2 7E-02 3.0E-02 4 6E-02 2

5 I 1 8E+0 0 2 OE+0 30 1.8E+00 2.OE+00 5.2E-01 5 8E-01 3 7E-01 7E-01 PAGE 10 OF 19 REVISION 10

DOSE BROWNS FERRY ASSESSMENT EPPIP-1 13 NUCLEAR PLANT ATTACHMENT B (Page 1 .of 8)

PROJECTING TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) AND THYROID CDE FROM GROUND-LEVEL RADIOACTIVITY RELEASES CAUTION: USE THIS ATTACHMENT FOR GROUND-LEVEL RELEASES ONLY DETERMINE RELEASE PATHWAY Contact the affected unit, Unit Supervisor to obtain information regarding the release pathway. The two pathway options for a ground level release are; (1) Containment Bypass (CTM) and (2) Main Steam Line Break (MSLB). Remember that when multiple pathways such as, Stack and Ground-Level, are experienced, both pathway calculations should be conducted and the results summed and recorded on Attachment C, the projected TEDE and Thyroid CDE assessment survey form.

Record data on page 5 of this attachment DETERMINE ESTIMATED RELEASE START TIME AND RELEASE DURATION Contact the affected unit, Unit Supervisor to obtain information regarding the release start time and duration. Record release duration in hours If the release duration can not be determined, then a default duration of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> should be utilized.

Record data on page 5 of this attachment.

DETERMINE NOBLE GAS RELEASE RATE IN JCI/SECOND To obtain the Total Noble Gas Release Rate for a building/ground level release the collection of rates from several building exhaust continuous air monitors (CAM) will be required The Noble Gas Release Rate data should be obtained from a SPDS terminal under the screens "U1CAMS, "U2CAMS", and "U3CAMS". When you reach the applicable window press the "F5" key to retrieve a tabular set of CAM data Collect all CAM data as petitioned by page 5 of this attachment. Sum all rates together to obtain a Total Building Noble Gas Release Rate. Record and utilize this rate for the dose assessment calculations. Utilize SPDS history to assist in obtaining the highest release rate for the incident It is recommended that data be reviewed from history approximately one hour (60 minutes) prior to the estimated start time as referenced in the preceding step Then step through to the 30 minute period prior to the estimated start time using the F4 key. (It is recommended that data be retrieved at frequency of every 10 minutes or 600 seconds) Place the highest release concentration data in the applicable calculation fields The completed calculation provides the Noble Gas Release Rate Record and utilize this rate for the dose assessment calculations.

If SPDS is unavailable, notify affected unit operations personnel to gain the information utilizing control room instrumentation, or through the completion of 0-SI-4.B.1 .a.1, Attachment 11.

The following conversion chart can be utilized to convert curies to microcuries.

To CONVERT MULTIPLY BY To OBTAIN Ci 1.0 X 101 I.tCI Record data on page 5 of this attachment PAGEiII OF 19 REVISION 10

DOSE BROWNS FERRY ASSESSMENT IP-13 NUCLEAR PLANT ATTACHMENT B (Page 2 of 8)

DETERMINE RELEASE TYPE Contact the Plant Assessment Team, Core Damage Assessor (5-751-1633) in the CECC to determine the applicable release type. If the Core Damage Group in the CECC can not be contacted, then use the default release type, "Type 2". The four release type options are; (1) "Type 1", Reactor Coolant System Leakage Release, (2) "Type 2" Fuel Cladding GAP Release, (3) "Type 3", Fuel Over Temperature Release, and (4) "Type 4", Fuel Melt Some release types have an additional "F" indicator, this implies that the release type has a filtered release pathway.

Record data on page 5 of this attachment DETERMINE METEOROLOGICAL DATA Met data should be obtained from the SPDS terminals under screen name "METDATA" or by accessing the "Met Data Terminal" located in the Technical Support Center.

For ground-level releases record measurements at the 46 meter instrument readings If all Met Data Collection Methods are unavailable contact the National Weather Service by dialing 9-1 205-621-5650. The National Weather Service will provide wind speed and wind direction The default value for stability class with no met data available is "D"for ground level releases.

The default value for wind speed with no met data available is 2 0 meters/second for ground level releases Record the following data on page 5 of this attachment.

"* STABILITY CLASS Note: Stability Class may be electronically displayed as 1,2,3.. This corresponds to A,B,C....

" WIND SPEED IN METERS/SECOND The following conversion chart can be utilized for conversions to meters/second.

To CONVERT MULTIPLY BY To OBTAIN MILES/H 0.45 METERS/SEC METERS/SEC 2.2 MILES/H KNOTS 0.5 METERS/SEC

"* WIND DIRECTION IN DEGREES

"* PLUME DIRECTION IN DEGREES NOTE: To OBTAIN PLUME DIRECTION, ADD 1800 TO WIND DIRECTION IF < 1800 OR SUBTRACT 1800 IF WIND DIRECTION IS > 180°.

PAGE 12 OF 19 REVISION 10

DOSE BROWNS FERRY ASSESSMENT EPIP-13 NUCLEAR PLANT ATTACHMENT B (Page 3 of 8)

DETERMINE THE TEDE FACTOR In determining the TEDE Factor you must know the stability class and the wind speed.

Locate the "TEDE Factor" table that corresponds to the applicable stability class located on page 7 of this attachment.

Locate the column within the table that corresponds to the applicable wind speed If wind speed falls between the two column variables choose the lower value, ,this is the more conservative factor.

Determine data for the 0.62, 2 and 5 mile distances Record data on page 6 of this attachment.

DETERMINE THE TEDE RATIO In determining the TEDE Ratio you must know the release pathway and the release type.

Locate the "TEDE Ratio" table that corresponds to the applicable release pathway located on page 8 of this attachment.

Locate the column within the table that corresponds to the applicable release type. Recall that the "F" indicator for some release types simply indicate that the release type is filtered.

Determine data for the 0.62, 2 and 5 mile distances.

Record data on page 6 of this attachment.

DETERMINE THE THYROID CDE RATIO In determining the Thyroid CDE Ratio you must know the release pathway and the release type.

Locate the "Thyroid CDE Ratio" table that corresponds to the applicable release pathway located on page 8 of this attachment.

Locate the column within the table that corresponds to the applicable release type. Recall that the "F" indicator for some release types simply indicate that the release type is filtered Determine data for the 0.62, 2 and 5 mile distances Record data on page 6 of this attachment.

PAGE 13 OF 19 REVISION 10

DOSE 1 BROWNS FERRY ASSESSMENT EPrIP-1i NUCLEAR PLANT ATTACHMENT B (Page 4 of 8)

Complete CALCULATIONS AND ATTACHMENT C Input data into applicable calculation fields and calculate. Use caution to input correct factors and ratios for the different mile indications.

Note, to complete the Thyroid CDE calculation, the TEDE calculation must be completed and the TEDE value utilized Also use caution when inserting values into the calculations. Use correct terms, I e. meters/second verses miles/hour COMPLETE ATTACHMENT C, PROJECTED TEDE AND THYROID CDE ASSESSMENT SURVEY FORM, AND FORWARD TO THE SHIFT MANAGER OR THE SITE EMERGENCY DIRECTOR. ENTER TEDE VALUES IN REM/HR ON ARROWS FOR APPLICABLE MILEAGE RINGS. SHOW PLUME DIRECTION ON SURVEY MAP BY THE USE OF AN ARROW.

PAGE 14 OF 19 REVISION 10

DOSE BROWNS FERRY ASSESSMENT EPIP-13 NUCLEAR PLANT ATTACHMENT B-(Page 5 of 8)

Ground-Level Release Data Collection and Calculation Worksheet RELEASE PATHWAY [1 CTM BYPASS Ml MAIN STEAM LINE BREAK ESTIMATED RELEASE START TIME ESTIMATED RELEASE DURATION NOTE: IF AN ESTIMATED RELEASE DURATION IS UNKNOWN USE 4 HOURS AS THE DEFAULT RELEASE DURATION NOBLE GAS RELEASE RATE _CI/SECOND POINT ID DESCRITPTION CURRENT VALUE SPDS 90-252c0 U0 CAM-RB VENT EXH BETA GAS _CI/SEC "Ul CAMS" 90-250Cl Ul CAM-RB VENT EXH BETA GAS pCI/SEC "FE"90-251 cl Ul CAM-TB VENT EXH BETA GAS _LCI/SEC "HISTORY" 90-249cl Ul CAM-TB VENT EXH BETA GAS GLCI/SEC POINT ID DESCRITPTION CURRENT VALUE SPDS 90-250c2 U2 CAM-RB VENT EXH BETA GAS ptCI/SEC "U2CAMS" 90-251c2 U2 CAM-TB VENT EXH BETA GAS ptCl/SEC "F5" 90-249c2 U2 CAM-TB VENT EXH BETA GAS I.tCI/SEC "HISTORY" POINT ID DESCRITPTION CURRENT VALUE SPDS 90-250c3 U3 CAM-RB VENT EXH BETA GAS CI/SEC "U3CAMS"90-251 c3 U3 CAM-TB VENT EXH BETA GAS _tCI/SEC "FH" 90-249c3 U3 CAM-TB VENT EXH BETA GAS pCI/SEC "HISTORY" TOTAL NOBLE GAS RELEASE RATE _CI/SEC RELEASE TYPE TYPE 1 (UNFILTERED)

TYPE 2 (UNFILTERED)

TYPE 3 (UNFILTERED)

TYPE 4 (UNFILTERED)

NOTE: TYPE 2 IS THE DEFAULT RELEASE TYPE STABILITY CLASS WIND SPEED METERS/SECOND

( _MILES/HOUR X 0.45 = METERS/SECOND)

WIND DIRECTION DEGREES PLUME DIRECTION DEGREES PAGE 15 OF 19 R O 10 REVISION

DOSE BROWNS FERRY ASSESSMENT EPIP-13 NUCLEAR PLANT ATTACHMENT B (Page 6 of 8)

TEDE FACTOR 0 62 MILES 2 0 MILES 5 0 MILES TEDE RATIO 0 62 MILES 2 0 MILES 5 0 MILES THYROID CDE RATIO 0 62 MILES 2 0 MILES 5 0 MILES TEDE DOSE ASSESSMENT CALCULATIONS 0.62 - 1.99 MILES

( )X(

) tCI/s)X( _ HOURS) X( ) = _ TEDE REM TEDE FACTOR RELEASE RATE RELEASE DURATION TEDE RATIO 2.00 - 4.99 MILES

( _ _ ) X ( _ ,ICI/s) X ( HOURS) X ( __) = _ TEDE REM TEDE FACTOR RELEASE RATE RELEASE DURATION TEDE RATIO 5.00 - 10.00 MILES

( __ ) X ( _ p.CI/S) X ( HOURS)X(

X _ TEDE REM TEDE FACTOR RELEASE RATE RELEASE DURATION TEDE RATIO THYROID CDE DOSE ASSESSMENT CALCULATIONS 0.62 - 1.99 MILES THYROID CDE REM TEDE REM THYROID CDE RATIO 2.00 - 4.99 MILES

( TEDE R x ( THYROID CDE RATIO ) =

TD REM THYROID CDE REM 5.00 - 10.00 MILES

( )_X_( ) = _ THYROID CDE REM TEDE REM THYROID CDE RATIO COMPLETE ATTACHMENT C AND FORWARD TO SM/SED.

PAGE 16 OF 19 REVISION 10

DOSE BROWNS FERRY ASSESSMENT EPIP-13 NUCLEAR PLANT ATTACHMENT B (Page 7 of 8)

TEDE FACTOR (rem/hr per pCils) FROM A GROUND-LEVEL RELEASE wind s peed I

Stability A . 4 MIS1 5 MIS1 7 MIS

-- o 9 M/S 10m/S ilmes 1 M/S 2 MsI 3 MIS1s 6 MsI 8 m/s k

0 62 mi I 6E-09 8 E-1 0 6 4E-101 4 8E-101 3 2E-101 2 9E-1 0 2 5E-10 2 2E-10 19E-10 16E-1 0 2 mi 28E-1 0 2 2E-101 1 7E-101 11.11E-1101 1 OE-10 90E-111 7 8E-11 67E-11 55E-11 5 mI 7 5E-1 1 - 5 2E-1 1 52E-111 - 51E-111 5 1E-111 4 6E-1 1 4 0E-111 3 5E-1 1 30E-11 25E-11

• t.*hllltv B wind s )eed Stabilit 4 m/s 5 rMIS 6 MIS 7 MIS 8 MEs 9 MIS 10 MIS miles 2 m8I 3 MIS 0 62 I7MIS5E-09 3 7E-09 3 OE-09 2 2E-09 1 4E-09 1 3E-09 I 2E-09 1 OE-09 8 9E-10 7 5E-10 3 6E-10 2 9E-1 0 1.3E-1 0 1 2E-101 1.0E-10 87E-11 72E-11 2 2E-10 1 4E-10 I- 2 9 9E-1 1 6 8E-1 1 6 7E-1 1 6-7E-111 6 6E-1 1 6 0E-1 1 5 3E-111 4 6E-1 1 "40E-11 3 3E-1 1 I 5 5

Stablety C wind s eed miles 1 M/S 4 m/s 5 M/s 10 MES 2 mIs 3 rnsI 6 MIS 7 m/s1 8 MIS j 9 MIS 0 62 1 1E-08 9 OE-09 6 7E-09 4 3E-09 3 9E-109 3 5E-091 3 OE-091 2 6E-09 22E-09 2.2E-08 2 I 4E-09 1 2E-09 8 8E-10 5 9E-1 0 5 3E-10 4 7E_10T 4 1E-101 3 5E-1 0 2 9E-1 0 2 9E-09 1 9E-10 I 3E-1 0 1 3E-10 13E-10 1 3E-10 1 2E-i10 1.1E-101 9 3E-111 7_9E-1 1 6 5E-11I 5

Stability wind sp)eed mles 4 MIS 5 MIS 7 mIs 9 MIS 10 rn/s 1 MIS 2 MES 3 MsI 6 MsI 8 MsI 3 2E-08 2 6E-0181 1 9E-08 1 2E-08 1 1E-08! I OE-08 8 8E-09 7 5E-09 6.3E-09 0 62 6 3E-08 2 1 OE-08 5 4E-091 4 3E-091 1 9E-09 I 7E-091 1 5E-09 1 3E-09 1.0E-09 3 2E-091 2 2E-09 5 8 3E-10 5 8E-101 5 7E-101 5 6E-101 5 6E-10 5 0E-1 0 4 5E-101 3 9E-10 3 4E-10 2 8E-10 1

Stablity E wid seed miles 2 m2-s 3 rnS/ 4 MIS 5 m/s 6 rn-S 7 rnIS 8 MEI jpJ 9 M/S 10 MIS 5 5E-081 4 4E-08 3 3E-08 2 2E-08 2 OE-08 1 8E-081 1 6E-08 1 3E-08 1 1E-08 S1 E-07 I- 062 2 1 E-08 1 OE-081 8 3E-09 6 3E-01 4 2E-09 3 8E-09 3 4E-091 2 9E-09 2 5E-09 2 1E-09 I 2 5 I- 12E0 1 2E-0S I1.2E-09 1 1E-09 9 8E-101 8 6E-1 0 7 3=-10n 6 0E-101 5 1.8E-09 Stability 1ind m/s8 eed 4 rMIS 5 10 M/S 1 MIS 2 rnIS 3 MIS 6 MIS 7 MISEj 8 MIS 9 MIS 062 Li 2 2E-07 1.0E-07 2 5E-O08 8 3E-08 2 OE-O8 6 3E-08 1 5E-08 4 2E-08 9 7E-09 3 8E-08 8 8E-09 3 4E-08 7.8E-091 3 OE-08 6 8E-09 2 6E-08 5 8E-09 2 2E-08 4 9E-09 5 4 6E-09 3 2E-09 3 1 E-09 3 1E-09 3 OE-09 2 7E-09 2 4E-09 2 1E-09 I BE-09 1 5E-09 Stability G wind speed miles 1 Mis 2 m/s 3 m/s 4 m/s 5 m/s 6 m/s 7 m/s IM/s 9m/s 10 m/s 062 4 8E-07 2 3E-07 1 BE-07 1 4E-071 9 OE-08 8 1E-08 7 2E-08 6 3E-08 5 4E-08 4 6E-08 2 1 E-07 5 1 E-08 4 OE-08 3 OE-08 2 OE-08 1.8E-08 1 6E-08 1.4E-08 1 2E-08 1 OE-08 5 1.1 E-08 7 5E-09 7.3E-09 7.2E-09 7 OE-09 6 3E-09 5 6E-09 4 9E-09 4 1 E-09 3 4E-0S PAGE 17 OF 19 REVISION 10

DOSE BROWNS FERRY ASSESSMENT EPIP-13 NUCLEAR PLANT ATTACHMENT B (Page 8 of 8)

TEDE RATIOS FO! I VARIOUS PATHS AND RELEASE TYPES CT.I Bipas.s .\ ISLB I Type 1 Type 2 Tye 3 Type 4 mi T~pc 1 T;pe 2 Type 3 Type 4 062 2

23 23 59 60 7.6 7.6 22 21 0 62 2

21 10 i 11 10 21 8.9 i~ 24 11 9.2 25 5 55 13 17 52 5 23 23 21 59 THYROID CDE RATIOS FOR VARIOUS ACCIDENTS AND RELEASE TYPES CT.I B*pas.% .%S&LB Typc I Tvpc 2 T)pe 3 Tpe 4 ni Type I T3pe 2 T;pe 3 Tpc 4 0 62 1 IE-01 6.2E+00 2 OE+00 1.4E+00 062 I1.IE+01 I1 IE+01 4 8E+00 3 3E+00 2 I IE-01 6.2E+00 2 OE+00 1.4E+00 2 I.IE+01 1.1E+01 4 8E+00 3 3E+00 5 I IE-01 6.2E+00 2 OE+00 1.4E+00 5 I1.1E+01 I IE+01 4 8E+00 3 3E+00 PAGE 18 OF 19 REVISION 10

DOSE BROWNS FERRY ASSESSMENT EPIP-13 NUCLEAR PLANT ATTACHMENT C (Page 1 of 1)

PROJECTED TEDE and Thyroid CDE ASSESSMENT SURVEY FORM

[-- STACK RELEASE L-GROUND-LEVEL RELEASE TIME OF ASSESSMENT RELEASE RATE _tCl/s WIND SPEED MILES/HR STABILITY CLASS WIND DIRECTION PLUME DIRECTION PREPARED BY DATE Site Boundarn Rein TEDE 00 Rein Th roid CDE 2 Miles Rein TEDE Rein ThIxoid CDE 270o 900 5 KMIle, Rem TEDE Rein Th3 rotd CDE 1860 LAST PAGE PAGE 19 OF 19 REVISION 10

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-15 EMERGENCY EXPOSURE REVISION 7 PREPARED BY" A H FELTMAN PHONE 3666 RESPONSIBLE ORGANIZATION. EMERGENCY PREPAREDNESS APPROVED BY JEFF LEWIS DATE" 01/23/2003 EFFECTIVE DATE- 01/27/2003 LEVEL OF USE: REFERENCE USE QUALITY-RELATED

REVISION LOG Procedure Number: EPIP-15 Revision Number: 7 Pages Affected: 1,5,7 Pagination Pages: NONE Description of Change:

EC-08 This change is being conducted to human factor the Revision Log. Description of Change and added clarification to revision log effecting rev. 6. EPIP 15 w~as revised to change a procedural reference The revision Nxas considered as a non-intent change EPIP 15 (rev log) N\as changed to reflect the current revision level Pages 2. revised Radiological Control Instruction 3 1 procedure title to Standard Programs and Processes (SPP) 5 10 IC-09 This procedure is being revised to add a authorization sign-off for the SED N~hen emergencx exposures are required. BFN utilized logs to document SED authorization of Emergency Exposures. WBN & SQN utilized forns EP Peer team recommended the use of forns to document authorization The procedure is also being revised to correct a page reference

t. pographical error

EMERGENCY BROWNS FERRY EXPOSURE 15 NUCLEAR PLANT 1.0 PURPOSE This procedure provides guidance for authorizations of personnel dose limits under emergency conditions, consistent with EPA-400, "Manual of Protection Action Guides and Protective Actions for Nuclear Incidents".

2.0 SCOPE These limits apply only to emergency exposure authorizations and not to spontaneous reactions by individuals attempting to mitigate an emergency situation This procedure provides guidance for the approval and administration of radiation exposures received during emergencies in excess of 10 CFR 20.1201 entitled "Occupational Dose Limits for Adults."

This procedure does not provide direction for the approval and administration for exposures received during other activities involving radiation dose to individuals Note: For the purposes of this implementing procedure, radiation exposure as expressed in units of R/hr and submits, thereof, are equivalent to dose (rad) and dose equivalent (rem) based on ANSI N 13.11 development and terminology. Any acute dose greater that 10 rem is generally denoted in units of rad, since that level is considered as the accident range of personnel exposure. Any dose less than that level is considered as the protective range of personnel exposure. For purposes of this procedure the assumptions of 1 rad = 1 rem is assumed for all levels of exposure 3.0 INSTRUCTIONS 3.1 RADCON Group The Radiological Control group is responsible for performing radiological surveys or other assessments to estimate the radiation doses 3.2 SITE EMERGENCY DIRECTOR 3.2.1 The Site Emergency Director (SED), shall provide authorization for all emergency radiation doses that may exceed 10 CFR 20 1201 entitled "Occupational Dose Limits for Adults" 3 2 2 The documentation of authorization shall be accomplished by SED signature on Attachment B of this procedure PAGE 1 OF 7 REVISION 7

EMERGENCY BROWNS FERRY EXPOSURE EPIP- 15 NUCLEAR PLANT 3.3 GUIDANCE FOR ALL EMERGENCY DOSE LIMITS 3.3.1 The exposure of personnel during emergency operations shall be maintained As Low As Reasonably Achievable (ALARA).

3.3.2 Internal exposure should be minimized by the use of respiratory protection equipment Respiratory Protection Factors are provided Standard Programs and Processes (SPP) 5 10 If a projected dose to the thyroid is expected to exceed 10 rem during emergency conditions, Potassium Iodine (KI) should be issued EPIP 14 contains information regarding issuance and precautions for the use of KI.

3.3.3 Protective clothing should be used to minimize personnel contamination 3.3 4 Personnel undertaking an emergency operation in which the dose will exceed 10 CFR 20 1201 entitled "Occupational Dose Limits for Adults" limits shall do so on a voluntary basis and with full awareness of the risks involved, including the numerical levels of dose at which acute effects of radiation will be incurred and numerical estimates of the risk of delayed effects as depicted on Attachment A.

Acknowledgment of this decision shall be documented on Attachment B of this procedure by the individual involved in this activity 3.3 6 Other factors being equal, older volunteers should be selected first 3 3 7 Other factors being equal, selection of female volunteers capable of reproduction should be avoided.

3 3 8 Exposures under these conditions shall be limited to a once in a lifetime Personnel who have received previous accident or emergency exposures in excess of 25 rem TEDE shall not participate in further emergency exposure assignments 3 3 9 Personnel shall not enter any area where dose rates are unknown or not measurable with instruments and dosimetry immediately available PAGE 2 OF 7 REVISION 7

EMERGENCY BROWNS FERRY EXPOSURE EPIP-15 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.3 9 Until isotopic assessments of airborne radioactivity are available, and administrative correction factor of 2 should be used to estimate TEDE exposures in airborne activity areas Estimated TEDE = Dosimeter Reading X 2 Note: The above value corresponds to the ratio of external (measured) dose rate to estimate TEDE dose, in accordance with default values in TVA's Dose Assessment model. When accident specific nuclide assessment are available, more definitive dose assessments should be performed to adjust the correction factors.

3.4 DOSE LIMITS FOR WORKERS DURING EMERGENCIES 3.4 1 Doses to all workers during emergencies should, to the extent practicable be limited to 10 CFR 20 1201 limits There are however, some emergency situations for which higher emergency exposures may be justified Whenever these situations are justified and ALARA considerations have been evaluated the following limits can be administered.

3.4 2 Dose Limits for the Protection of Valuable Property DOSE RECEPTOR LIMIT (REM)

WHOLE BODY (TEDE) 10 LENS OF THE EYE, 30 ALL OTHER ORGANS 100 PAGE 3 OF 7 REVISION 7

EMERGENCY BROWNS FERRY EXPOSURE EPIP-15 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.4 DOSE LIMITS FOR WORKERS DURING EMERGENCIES (CONTINUED) 3.4 3 Dose Limits for Lifesaving Activities and the Protection of Large Populations DOSE RECEPTOR LIMIT (REM)

WHOLE BODY (TEDE) 25 LENS OF THE EYE 75 ALL OTHER ORGANS 250 3 4.4 Dose Limits Greater Than 25 Rem for Lifesaving Activities or to Avoid Extensive Exposures to Large Populations.

3 4.4 1 Situations may occur in which a dose in excess of 25 rem would be required in order to carry out lifesaving operations or to avoid extensive exposures to large populations. It is not possible to prejudge the risk that one person should be allowed to take to save the life of others 3 4 4.2 Personnel made knowledgeable of the risks involved with radiation exposures through training or briefings utilizing the information contained within Attachment A and selected on a voluntary basis may be allowed to exceed the 25 rem emergency dose exposure limit for the purpose of lifesaving activities or to avoid extensive exposures to large populations 3 4 4 3 Acknowledgment of this decision shall be documented on Attachment B of this procedure by the individual involved in this activity PAGE 4 OF 7 REVISION 7

EMERGENCY - BROWNS FERRY EXPOSURE IP-15 NUCLEAR PLANT 3.0 INSTRUCTIONS (CONTINUED) 3.5 POST-EXPOSURE ACTIVITIES 3 5.1 Personnel receiving emergency doses should be restricted from further occupational exposures pending the outcome of exposure evaluations, and if necessary, medical surveillance 3.5 2 Radcon shall conduct post exposure dose assessments for exposed individuals, with particular attention to determining the adequacy of administrative dosimeter correction factors for TEDE doses resulting from internal and external exposures 3.5.3 Any exposures above 5 rem TEDE shall be reported to a TVA physician It is the responsibility of the physician to determine appropriate medical evaluations and required care. Cross reference guidance in EPIP-10.

3.5 4 Any emergency exposures shall be reported to the Radcon Manager as soon as possible PAGE 5 OF 7 REVISION 7

EMERGENCY BROWNS FERRY EXPOSURE EPIP- 15 NUCLEAR PLANT ATTACHMENT A (Page 1 of 1)

EPA EMERGENCY EXPOSURE RISK INFORMATION I Health Effects Associated with Whole Body Adsorbed Doses Received Within A Few Hours.

2 Whole Body Early Fatalities Whole Body Prodromal Effects3 Absorbed Dose (rad) (Percent) Adsorbed Dose (rad) (Percent) 140 5 50 2 200 15 100 15 300 50 150 50 400 85 200 85 460 95 250 98 SRisks will be lower for protracted exposure periods 2 Supportive medical treatment may increase the dose at which these frequencies occur by approximately 50 percent Forewarning symptoms of more serious health effects associated with large doses of radiation.

II Approximate Cancer Risk to Average Individuals from 25 rem Effective Dose Equivalent Delivered Promptly Age at Exposure (years) Risk of Premature Death Average years of life lost if (deaths per 1,000 persons premature death occurs i

exposed) i (Years) 20 to 30 91 24 30 to 40 72 19 40 to 50 53 15 50 to 60 35 11 Note: Tables referenced from the Environmental Protection Agency's "manual of Protective Action Guides and Protective Actions for Nuclear Incidents", (EPA-400), October 15, 1991, page 2-12 PAGE 6 OF 7 REVISION 7

EMERGENCY BROWNS FERRY EXPOSURE EPIP- 15 NUCLEAR PLANT ATTACHMENT B (Page 1 of 1)

ACKNOWLEDGMENT AND AUTHORIZATION TO EXCEED OCCUPATIONAL DOSE LIMITS READ THE FOLLOWING STATEMENT BEFORE SIGNING THIS FORM:

I acknowledge by signature on this form that I am volunteering for exposures in excess 10 CFR 20 1201 limits and that I have been made aware through training or a briefing of the risks involved. Briefing material presented on Attachment A of the procedure.

The persons listed belmo have acknowledged and volunteered to recei e Dose Limits in excess of 10 CFR 20 1201 himits Authorization is required by the Site Emergency Director to administer any emergency exposure limit. Authorization is acknowNledged by SED signature on the bottom of this form Name SSN Signature Dose Limit (Please print 1*a,4. Frst N1) (REM) 1.

2.

3.

4 5

6 7

8 9.

10.

11.

12.

13.

14.

15 Brief Description of Task Authorized by.

Site Emergency Director Time/Date LAST PAGE PAGE 7 OF 7 REVISION 7

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-17 FIRE EMERGENCY PROCEDURE REVISION 27 PREPARED BY: A H FELTMAN PHONE 3666 RESPONSIBLE ORGANIZATION: EMERGENCY PREPAREDNESS APPROVED BY. JEFF LEWIS DATE 01/23/2003 EFFECTIVE DATE 01/27/2003 LEVEL OF USE: REFERENCE USE QUALITY-RELATED

REVISION LOG PROCEDURE NUMBER EPIP-17 REVISION NUMBER 27 PAGES AFFECTED ALL DESCRIPTION OF CHANGES IC-30 This rcision is being conducted to cancel EPIP-17. EPIP-17 is being renumbered for standardization issues. EPIP-12 wiill manage Emcrgency Equipment and Supplies (Inmenton and Operabiltv Procedure) The Cancellation of EPIP-17 and acti ation of EPIP-12 Nill be accomplished as a parallel change IC-31 This re, ision is being conducted as a recommendation of the EP Peer Team. standardization process EPIP-21 -Fire Emergency Procedure" is being moed to EPIP-17 As noted in IC-30 EPIP-17 wias canceled and the contents of EPIP-17 placed into EPIP-12. This rex ision rcactivates EPIP-17 as the "Fire EmergencN Procedure" There has been no material re ision to the existing Fire Emergency Procedure. this reN ision only mno es the content of the procedure to EPIP-17

FIRE EMERGENCY PROCEDURE TBROWNS FERRY EPIP-17 NUCLEAR PLANT 1.0 PURPOSE To provide timely response to fire emergencies at Browns Ferry and a mechanism to notify additionally emergency personnel or resources as needed 2.0 SCOPE This procedure applies to all fire emergencies at Browns Ferry.

3.0 INSTRUCTIONS 3.1 General 3 1.1 All members of the fire response team will proceed to the scene upon hearing the announcement 3.2 Initial Notification bv Unit Operator' 3.2.1 Upon receiving a fire emergency call, the Unit I Control Room Unit Operator will

"* Obtain name of caller.

"* Obtain location of fire.

"* Obtain nature of fire.

"* Obtain telephone number from caller 3.2 2 Initiate the "Fire Alarm Bell".

3.2 3 Announce fire location over the plant public address (PA) system, repeating at regular intervals until instructed otherwise by Shift Manager or Unit Supervisor.

3.2.4 Notify the Fire Protection Personnel using the Operations/Fire Protection Radio.

3 2.5 Notify the Shift Manager of the fire 3.3 Shift Manager Responsibilities 3 3.1 The Shift Manager will

"* Dispatch Unit Supervisor or designee to the scene to act as Incident Commander.

"* Establish and maintain communications with the Incident Commander

"* Refer to SSI-00 I for applicability based on the severity of the fire 3 3.2 When requested by the Incident Commander notify the off-duty BFN fire protection personnel Notify the off-duty BFN fire protection personnel from list in the Shift Manager office This list will be maintained by the Fire Protection Organization PAGE I OF 2 REVISION 27

FIRE EMERGENCY PROCEDURE BROWNS FERRY EPIP-17 NUCLEAR PLANT 3.3 Shift Manaeer Responsibilities (Continued) 3 3.3 When requested by the Incident Commander notify of the Clements Volunteer Fire Department Notify the Clements Volunteer Fire Department by calling the Limestone County Sheriffs Dispatcher (233-3473) 3.3.4 Following an "Appendix R Fire" - direct the Operations Support Center (OSC) to provide ventilation of Shutdown Board Rooms by MSI-0-000-PROO05, Electrical Equipment Room Emergency Ventilation 3.4 Incident Commander Responsibilities 3 4 1 The Incident Commander will

"* Establish radio communication with the Shift Manager.

• Keep Shift Manager advised of situation.

"* Request Shift Manager to call in off-site support as needed 3.5 RADCON Representative Responsibilities 3 5 1 The RADCON Representative will:

• Advise the Incident Commander of radiological hazards

• Ensure the Incident Commander is aware of areas of significant radiation exposure and airborne radioactivity that may affect stay time for team members

• Notify the Incident Commander of any team members limitations in regards to stay time 4.0 ATTACHMENTS None LAST PAGE PAGE 2 OF 2 REVISION 27