ML030150621

Transmittal of Latest Revision for Farley Emergency Plan Implementing Procedures 9.0 & 9.5

ML030150621
Person / Time
Site:	Farley
Issue date:	01/06/2003
From:	Hudspeth J Southern Nuclear Operating Co
To:	Mcknight J Document Control Desk, Office of Nuclear Reactor Regulation
References
FNP-177-DC FNP-0-EIP-9.0, Rev 49, FNP-0-EIP-9.5, Rev 7
Download: ML030150621 (97)

Text

53-43 Southern Nuclear Operafing Company, Inc.

Post Office Drawer 470 Ashford, Alabama 36312 Date: January 6, 2003 SOUTH ERI\I E COMPANY Energy to Serve Your World" FNP- 177-DC Director, Office of NRC Alt: Document Control Desk C/O Jim McKnight US Nuclear Regulatory Commission Washington, DC 20555

Dear Sir:

ENCLOSED IS THE LATEST REVISION FOR FARLEY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES 9.0 & 9.5.

FNP-0-EIP-9.0 REVISION 49 EMERGENCY CLASSIFICATION AND ACTIONS FNP-0-EIP-9.5 REVISION 7 EMERGENCY CLASSIFICATION BASED ON ODCM PLEASE REPLACE YOUR COPIES WITH THE ATTACHED REVISED COPIES.

IF YOU HAVE ANY QUESTIONS, PLEASE CALL ME AT 334-899-5156 EXTENSION 3439.

Sincerely, tdspefth Document Control Supervisor CD/001 Rtype:A4.19

- - - -' FNP-0-EIP-9.5 December 5, 2002 I 12/31/02 8:18:58 **

Version 7 FARLEY NUCLEAR PLANT PROCEDURE EMERGENCY PLAN IMPLEMENTING FNP-0-EIP-9.5 S

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S1231/02 8:18:58 FNP-0-EIP-9.5 PROCEDURE CONTAINS Body ............................................................................................................................................... 11 Table I ............................................................................................................................................. 1 Table 2 ............................................................................................................................................. 1 Figure I ............................................................................................................................................ 1 Figure 2 ............................................................................................................................................ 1 Figure 3 ............................................................................................................................................. 1 Figure 4 ............................................................................................................................................ 2 Figure 5 ............................................................................................................................................ 1 Figure 6 ............................................................................................................................................ 1 Figure 7 ............................................................................................................................................ 1 Page 1 of 1

12/31/02 8:18:58 FNP-0-EIP-9.5 I EMERGENCY CLASSIFICATION BASED ON ODCM TABLE OF CONTENTS Section Title Page 1.0 Purpose 1 1

2.0 References 1

3.0 General 4.0 Determining The Methodology for Performing Dose Assessment 1 2

I 5.0 ODCM Dose Assessment for the Plant Vent Stack 5.1 Classification based on RE-29B noble gas or iodine channel values 2 5.2 Classification based on RE-14 count rate (cpm) "3 5.3 Classification based on Plant Vent Stack grab sampling and analyses 4 I I

6.0 ODCM Dose Assessment for Steam Generator Atmospheric Relief 5 and/or Safety Release and/or Turbine Driven Auxiliary Feedwater Release 7.0 ODCM Dose Assessment for Steam Jet Air Ejector Release 6 8.0 ODCM Dose Assessment Using the NRERDS Computer Terminal 7 9.0 Evaluation of ODCM Dose Assessment Using the NRERDS Computer Terminal 11 TABLE 1 REFERENCES TABLE 2 Steam Generator Relief/Safety Valves Open FIGURE 1 Calculations Based On RE-29B Noble Gas Or Iodine Channel Values FIGURE 2 Calculation Based On RE-14 Count Rate FIGURE 3 Calculations Based On Plant Vent Stack Grab Sampling And Analyses FIGURE 4 Calculations Based On SG Atmospheric Reliefs, Safeties and TDAFW Releases FIGURE 5 Calculation Based On Steam Jet Air Ejector Release Page I of 2 Version 7

12/31/02 8:18:58 -. 7 . FNP-O-EIP-9.5 I FIGURE 6 RATIO OF TOTAL IODINES TO 1-131 FIGURE 7 ODCM COMPUTER SCREEN I Page 2 of 2 Version 7

12/31/02 8:18:58 FNP-0-EIP-9.5 I EMERGENCY CLASSIFICATION BASED ON ODCM 1.0 Purpose To provide a method of emergency classification based on exceeding Technical Specification effluent criteria using the annual average mixed mode X/Q value, as defined in the ODCM.

2.0 References See Table 1.

3.0 General 3.1 This procedure is entered to perform dose assessment using the Offsite Dose Calculation Method (ODCM) if Automated Dose Assessment was NOT required to automatically activated OR if a General, or Site Area Emergency is not indicated by FNP-0-EIP-9.1 or FNP-0-EIP-9.3 from the following:

a. EIP-9.0, step 4.2.7

b. EIP-9.0, step 4.2.10 3.2 When this procedure is entered continue to perform dose assessment periodically as required by FNP-0-EIP-9.0, not to exceed 30 minute intervals.

4.0 Determine the Methodology for Performing Dose Assessment 4.1 If the ODCM dose assessment using the NRERDS computer terminal is available and any of the following conditions exist, then dose assessment should be performed using step 8.0, ODCM dose assessment using the NRERDS computer terminal.

"* There is no known tube leak or rupture and R-29B data is available on NRERDS.

"* There is no known tube leak or rupture and R-14 data is available on NRERDS.

"* A steam generator tube leak or rupture is in progress, R- 15 has increased by a factor of 10 or more and R- 15 data is available on NRERDS.

"* A steam generator tube leak or rupture is in progress, R-60A, B, C or D has increased by a factor of 10 or more and R-60 data is available on NRERDS.

4.2 If any of the step 4.1 conditions are not met, then determine the release concentration or release count rate per steps 4.2.1, 4.2.2 or 4.2.3 and use steps 5, 6 or 7 to determine the ODCM Dose assessment.

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12/31/028:18:58 A W E FNP-0-EIP-9.5 I 4.2.1 For a release that takes less than I hour, normalize the release concentration or release count rate to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and add this value to the average background (e.g., if the release lasted 15 minutes, divide by 4; if the release lasted for 10 minutes, divide by 6, etc.). For releases that lasted more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, use the method above to determine the highest average release for any continuous 60-minute period with the highest average release (i.e., comparable to a moving average).

4.2.2 If a single grab sample is the only method of determining release concentration, the value of that grab sample will be the release concentration.

4.2.3 If multiple grab samples are taken within a 60 minute period, they may be averaged to provide the release concentration.

5.0 ODCM Dose Assessment for the Plant Vent Stack Steps 5.1, 5.2, and 5.3 should be used in sequence order any time that a plant vent stack ODCM calculation is performed. This is true even if the alarm that required doing the calculation was a different alarm.

5.1 Classification based on RE-29B noble gas or iodine channel values.

NOTE: Figure 1 may be used as an aid to calculate ODCM off site dose rates based on RE-29B noble gas or iodine channel values.

5.1.1 Obtain noble gas release concentration per step 4.0 from the Non Regulatory Emergency Response Data System (NRERDS), the Radiological and Meteorological Data Acquisition System (RMDA), Plant Computer or directly from the low range gas channel. IF the noble gas channel of RE-29B is INOPERABLE, THEN go to 5.2.

5.1.2 Obtain iodine release concentration per step 4.0 from NRERDS, RMDA, Plant Computer or directly from the iodine channel. IF the iodine channel is inoperable, THEN go to 5.3.

5.1.3 Obtain Plant Vent Stack (PVS) flow rate from NRERDS, RMDA, Plant Computer or from the PVS flowrate recorder in the Control Room.

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12/31/02 8:18:58 T FNP-0-EIP-9.5 I 5.1.4 IF the PVS flow rate is NOT available from these sources, THEN use the following default values: (REA 98-1906)

a. One Auxiliary Building Fan...94,000 scfm

b. Two Auxiliary Building Fans... 136,000 scfm

c. Zero Auxiliary Building Exhaust Fans, one train PRF... 5,000 scfm

d. Zero Auxiliary Building Exhaust Fans, two trains PRF ... 10,000 scfin 5.1.5 Calculate the noble gas and iodine dose rates at the site boundary using the following ODCM equations:

noble gas release PVS flowrate conversion noble gas dose concentration in ;tci/ml X (scfm) X factor i rate (rem/hr) from step 5.1.1 from step 5.1.3/4 8.54E-07 iodine release PVS flowrate conversion Iodine dose concentration in jtci/ml X (scfin) X factor = rate (rem/hr) from step 5.1.2 from step 5.1.3/4 9.41E-04 5.1.6 Go to EIP-9.0, step 4.2.11 for evaluation of emergency classification criteria.

5.2 Classification based on RE-14 count rate (cpm)

NOTE: Figure 2 may be used as an aid to calculate ODCM off site dose rates based on RE-14 count rate.

5.2.1 Obtain release count rate (cpm) per step 4.0 from NRERDS, RMDA, Plant Computer or directly from RE-14.

5.2.2 IF RE-14 count rate is less than 650,000 epm, no emergency classification can be based on effluent noble gas dose rates. Go to step 5.2.7.

5.2.3 IF RE-14 release count rate (epm) is greater than 1,000,000 cpm (full scale) OR NOT operable, THEN go to step 5.3.

5.2.4 Obtain Plant Vent Stack (PVS) flow rate from NRERDS, RMDA, Plant Computer or from the PVS flowrate recorder in the Control Room.

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-- A , w-wu ' P I 12/31/02 8:18: :58 I 5.2.5 IF the PVS flow rate is NOT available from these sources, THEN use the following default values: (REA 98-1906)

a. One Auxiliary Building Fan.. .94,000 scfm

b. Two Auxiliary Building Fans... 136,000 scfin

c. Zero Auxiliary Building Exhaust Fans, one train PRF... 5,000 scfin

d. Zero Auxiliary Building Exhaust Fans, two trains PRF ... 10,000 scfin 5.2.6 Calculate the noble gas dose rate at the site boundary using the following ODCM equation:

RE-14 release count rate PVS flowrate conversion noble gas dose in cpm X (scfim) X factor - rate (rem/hr) from step 5.2.1 from step 5.2.4/5 5.697E-16 5.2.7 Go to step 5.1.2 to perform applicable steps if the iodine dose rate is required or go to EIP-9.0, step 4.2.11 for evaluation of emergency classification criteria.

5.3 Classification based on Plant Vent Stack grab sampling and analyses NOTE: Figure 3 may be used as an aid to calculate ODCM off site dose rates based on Plant Vent Stack grab sampling and analyses.

5.3.1 IF RE- 14 is reading full scale or inoperable AND the low range noble gas channel of RE-29B is NOT operable, THEN request that the Shift Radiochemist obtain a plant vent stack noble gas grab sample AND analyze it for DOSE EQUIVALENT Xe-133.

5.3.2 IF the RE-29B iodine channel is NOT operable, THEN request that the Shift Radiochemist obtain a plant vent stack iodine grab sample AND analyze it for DOSE EQUIVALENT 1-131.

5.3.3 Obtain Plant Vent Stack (PVS) flow rate from NRERDS, RMDA, Plant Computer or from the PVS flowrate recorder in the Control Room.

5.3.4 IF the PVS flow rate is NOT available from these sources, THEN use the following default values: (REA 98-1906)

a. One Auxiliary Building Fan.. .94,000 scfin

b. Two Auxiliary Building Fans... 136,000 scfm

c. Zero Auxiliary Building Exhaust Fans, one train PRF... 5,000 scfin

d. Zero Auxiliary Building Exhaust Fans, two trains PRF ... 10,000 scfm 4 Version 7

12/31/02 8:18:58 T i- T'i FNP-0-EIP-9.5 I 5.3.5 Calculate the dose rates at the site boundary using the following ODCM equations:

DE Xe-133 release PVS flowrate covrinNoble gas dose concentration in pici/ml X (scfin) X factor = rate (rem/hr) from step 5.3.1 from step 5.3.3/4 8.54E-07 DE 1-131 release PVS flowrate conversion Iodine dose concentration in Pci/ml X (scfin) X factor = rate (rem/hr) from step 5.3.2 from step 5.3.3/4 9.41E-04 5.3.6 Go to EIP-9.0, step 4.2.11 for evaluation of emergency classification criteria.

6.0 ODCM Dose Assessment for Steam Generator Atmospheric Relief and/or Safety Release and/or Turbine Driven Auxiliary Feedwater (TDAFW) Release.

SNOTE: Figure 4 may be used as an aid to calculate ODCM off site dose rates based on Steam Generator Atmospheric Reliefs, Safeties and TDAFW.

6.1 Using the values from the R-60 series of instruments, HP surveys or other criteria, determine which steam generators have a radioactive release in progress.

6.2 Obtain the current pressure (psig) for each steam generator of the affected unit that has a radioactive release in progress.

6.3 Determine the number of valves that are open for each steam generator that has a radioactive release in progress by consulting Operations staff. Table 2 may be used as an aid in determining this.

6.4 Determine the total flow in cfm from each generator that has a radioactive release in progress by using the following equation:

6.5 Using the values from the R-60D, HP surveys or other criteria, determine if the TDAFW exhaust has a radioactive release in progress. If the TDAFW is determined to have a radioactive release the flow for that release point is 11175 cfm.

6.6 Add the flows determined in step 6.4 and 6.5 for all steam generators and the TDAFW that have a radioactive release in progress.

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• FNP-0-EIP-9.5 6.7 Obtain noble gas release concentration per FNP-0-CCP-1300, Appendix 0.

6.8 Obtain total iodine release concentration per FNP-0-CCP-1300, Appendix 0.

6.9 If the reactor is at power, convert from total iodine concentration to 1-131 concentration by dividing the total iodine concentration from step 6.8 by 8.4.

6.10 If the reactor is shutdown, convert from total iodine concentration to 1-131 concentration by dividing the total iodine concentration from step 6.8 by the ratio obtained from Figure 6.

6.11 Calculate the noble gas and iodine dose rates at the site boundary using the following ODCM equations:

noble gas release steam flow rate conversion noble gas dose concentration (Ptci/ml) X (cfm) from step X factor f rate (rem/hr) from step 6.7 6.6 3.85E-05 iodine 131 release steam flow rate conversion iodine dose concentration in p.ci/ml X (cfm) from step X factor = rate (rem/hr) from step 6.9/10 6.6 4.24E-02 6.12 Go to EIP-9.0, step 4.2.11 for evaluation of emergency classification criteria.

7.0 ODCM Dose Assessment for Steam Jet Air Ejector Release SNOTE: Figure 5 may be used as an aid to calculate ODCM off site dose rates based on Steam Jet Air Ejector.

7.1 Obtain noble gas concentration per FNP-0-CCP-1300, Appendix 0.

7.2 Obtain total iodine concentration per FNP-0-CCP-1300, Appendix 0.

7.3 If the reactor is at power, convert from total iodine concentration to 1-131 concentration by dividing the total iodine concentration from step 7.2 by 8.4.

7.4 If the reactor is shutdown, convert from total iodine concentration to 1-131 concentration by dividing the total iodine concentration from step 7.2 by the ratio obtained from Figure 6.

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12/31/02 8:18:58 12/31/-28.8: 8: 8 NP 0- I FNP-0-EIP-9.5 I 7.5 Calculate the noble gas and iodine dose rates at the site boundary using the following ODCM equations:

noble gas release conversion concentration in j+/-Ci/ml X factor, includes from step 7.1. 1050 scfrn flow 4.0425 E-2 iodine 131 release conversion iodine dose concentration in pci/ml X factor, includes = rate (rem/hr) from step 7.3/4 (block 3) 1050 scfm flow 44.52 7.6 Go to EIP-9.0, step 4.2.11 for evaluation of emergency classification criteria.

8.0 ODCM Dose Assessment Using the NRERDS Computer Terminal NOTE hFigure 7 may be used as an aid when performing ODCM Dose Assessment using NOTE the NRERDS Computer Terminal.

8.1 To view the ODCM screen click on the "ODCM Dose Assessment" option on the top menu of the display.

8.2 When it is desired to return to the ERDS / ARDA screens, then click on the "Group Display" option on the top menu of the display.

8.3 Select the desired unit by clicking on the "Unit" option on the top menu of the display, then click on the desired unit.

8.4 To print the ODCM information, click on the "Print Screen" button" when the ODCM page is displayed.

8.5 The peak projected column can NOT be used to classify a radiological release as an Alert or NOUE. The peak projected column can be used by plant personnel to determine what the ODCM dose rate would be if peak release conditions stayed the same for the next hour.

8.6 The instruments used to calculate the total noble gas and the total iodine dose rate are indicated with an "X" in the left hand column (USE IN TOTAL column). If there are any instruments that are not operating properly, they should not have the X in the brackets and a manual dose assessment per steps 5.0 through 7.0 should be performed.

8.7 The default state for instruments used is R29B and all others with no "X" in the brackets.

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12/31/02 8:18:58 r ...T .. FNPOEIP.9.5

- I 8.8 To change the instruments used for the total calculation, click on the "ODCM Options" option on the second menu of the display, then click on the particular unit and instrument to toggle the status of that instrument.

8.9 Overriding the met information, radiation monitors, plant parameters, previous history or inventory will have no effect on ODCM readings.

8.10 Manually selecting R60A, B or C as a release point will cause an ODCM release rate to be calculated for that steam generator even if actual steam pressure is below the PORV setpoint.

8.11 The ODCM dose rate is calculated using a one hour rolling average for its calculation as compared to the EDCM which uses a 15 minute average.

8.12 Plant Vent Stack Release A plant vent stack release is always in progress from the plant as long as there are ventilation fans running. Any ODCM dose assessment should include either R29B or RI4. If neither instrument is operating properly or plant vent stack flow is not indicating properly, the ODCM should be calculated using the appropriate portions of step 5.0 and adding the value to any steam generator dose assessment that is being done.

8.12.1 If plant vent stack flow is not reading correctly on the NRERDS system, then proceed to step 5.0 to calculate the plant vent stack ODCM dose assessment. Add the results to any SG Dose assessment subsequently performed.

8.12.2 If R29 is operating properly, then verify that R29B is selected to be used in the total and R14 is not selected to be used in the total.

8.12.3 If R29B is not operating properly and R-14 is operating properly, then verify that R14 is selected to be used in the total and R29B is not selected to be used in the total.

8.12.4 If R29B and R14 are not operating properly, then proceed to step 5.3 to calculate the plant vent stack ODCM dose assessment using a grab sample.

Add the results to any SG Dose assessment subsequently performed.

8.12.5 If there is an indication of a SG tube leak or rupture, then proceed to step 8.13 to complete ODCM dose assessment.

8.12.6 If there is no indication of a SG tube leak or rupture, then verify that R15 and R60A, B, C, D are not selected for use and print this screen. Proceed to step 9.0 to evaluate the data.

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12/31/02 8:18:58 FNP-0-EIP-9.5 8.13 Steam Jet Air Ejector (SJAE) Release The ODCM calculation will use the instrument that is closest to midscale of R15, R15B, or R15 C to calculate the ODCM release rate from the SJAE. If there is no release from the SJAE then this calculation should not be performed. If there is an indication that the R15 series instruments are not working properly then SJAE ODCM calculation should be done using a manual calculation.

8.13.1 If the SG that has the tube leak or rupture has been isolated from the main steam system by closing the associated MSIVs, then verify that R15 is not selected to be used in the total and proceed to step 8.14.

8.13.2 If the SG that has the tube leak or rupture is not isolated from the main steam system, the SJAE are operating, and the R15 series instrument are working properly then verify that RI 5 is selected to be used in the total and proceed to step 8.14.

8.13.3 If the R15 instruments are not operating properly then proceed to step 7.0 to calculate the SJAE ODCM dose assessment using a grab sample. Add the results to any other dose assessment subsequently performed and proceed to step 8.14.

8.14 Turbine Driven AFW (TDAFW) Release The TDAFW ODCM calculation is not performed unless the dose assessment for ARDA has been started automatically as a result of R-60D going into alarm or ARDA has been started manually for that release point. Once started, TDAFW ODCM is calculated based on an assumed flow from the TDAFW pump. If the TDAFW pump is not actually running using steam from a ruptured SG, the ODCM calculation is meaningless. The R60D instrument is a fairly high range instrument. The actual background reading may be lower than the minimum reading on the instrument. R60D should not be used for the calculation unless it has shown an observable increase.

8.14.1 If the TDAFW pump is not running using steam from the SG with a rupture or tube leak, verify that R60D is not marked for use in the total and proceed to step 8.15.

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• I- F FNP-0-EIP-9.5 I 8.14.2 If the TDAFW pump is running using steam from the SG with a rupture or tube leak and R60D has shown an increase above normal background, verify that ARDA dose assessment has been started for R60D and it is marked for use in the total and proceed to step 8.15.

8.14.3 If the TDAFW pump is running using steam from the SG with a rupture or tube leak and R60D has not shown an increase above normal background, verify that R60D is not marked for use in the total. Calculate TDAFW ODCM using step 6.0. Add the results to any other dose assessment subsequently performed and proceed to step 8.15.

8.15 Steam Generator Atmospheric Relief or Safety Release The R60A, B and C ODCM calculations are not performed unless the dose assessment for ARDA has been started automatically as a result of R60A, B or C going into alarm or ARDA has been started manually for that release point. The ODCM source term will be zero unless there is adequate steam pressure to cause a SG safety or relief to be open providing a flow term. By selecting a specific SG and valve(s) to be open, the operator can force an ODCM source term to be calculated. The R60 instruments are fairly high range instruments. The actual background reading may be lower than the minimum reading on the instrument.

R60s should not be used for the calculation unless it has shown an observable increase.

8.15.1 If there is no flow out of any SG open relief or safety valve in a SG with a tube rupture or leak, then verify that R60A, B and C are not marked for use and print this screen.

8.15.2 If there is flow out of a SG open relief or safety valve due to elevated pressure in a SG with a tube rupture or leak and R60A, B or C for that SG has shown an increase above normal background, then verify that ARDA has started for that that release point. Mark the specific SG for use and proceed to the next step.

8.15.3 If there is flow out of a SG open relief or safety valve due to a failed open valve in a SG with a tube rupture or leak and R60A, B or C for that SG has shown an increase above normal background, then verify an override for the specific valve as a release point, verify ARDA started for the release point, and select the specific R60 for use. Print the screen and proceed to step 9.0 to evaluate the data.

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12/31/02 8:18:58 FNP-0-EIP-9.5 I 8.15.4 If there is flow out of a SG open relief or safety valve in a SG with a tube rupture or leak and R60A, B or C for that SQ have not shown an increase above normal background, then verify that the specific R60 instruments are not selected for use. Calculate relief/safety ODCM using step 6.0.

Add the results to any other dose assessment subsequently performed and proceed to step 9.0 to evaluate the data.

9.0 Evaluation of ODCM Dose Assessment Using the NRERDS Computer Terminal 9.1 After all of the appropriate instruments have been selected for use in the total or removed from the selection as appropriate and any required relief or safety valves have been selected as a release point, then print the ODCM screen.

9.2 The USE IN TOTAL column is selected by the operator to have the program use only those effluent instruments that are appropriate for this particular ODCM calculation.

9.3 There are some ODCM calculations that cannot be performed by the computer. If these are performed manually, the results should be added to the totals for evaluation. For example if plant vent stack has been calculated by using a grab sample add those results to the total for evaluation.

9.4 The total noble gas and total iodine from the PREVIOUS HOUR column plus any manual calculations required should be used to evaluate if the effluent criteria for the Alert or NOUE declarations has been exceeded.

9.5 If the NOUE criteria for noble gas or iodine has been exceeded, the word "EXCEEDED" will be printed next to the value that has exceeded the NOUE criteria.

9.6 The NOUE and ALERT effluent limits have been listed at the bottom of the page for easy reference.

9.7 The PEAK PROJECTED column can be used to evaluate what would happen to the ODCM calculation if the PEAK value from the previous hour is maintained for the next hour. This is a planning tool only and should not be used to make a declaration.

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• A V* FNP-0-EIP-9.5 I TABLE 1 REFERENCES

1. FNP-0-CCP-1300, Chemistry and Environmental Activities During a Radiological Accident

2. FNP-0-EIP-9.0, Emergency Classification and Actions

3. FNP-0-EIP-20.0, Chemistry and Environmental Support to the Emergency Plan

4. NT-86-0014, Gaseous Releases, Emergency Classifications

5. FNP-0-M-01 1, Off-site Dose Calculation Manual I oflI Version 7

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FNP-O-EIP-9.5 FNP-0-EIP-9.5 I TABLE 2 Steam Generator Relief/Safety Valves Open This table may be used to help determine the number of valves that are open for each steam generator assuming there are no failed open or stuck valves.

Steam Generator Total Number Of Valves That Are Open For Each Pressure Range in PSIG Valves Open Per SG SG

<1035 0 NONE 1035-1074 1 1SGPORV 1075-1087 2 1 SG PORV / I SG SAFETY 1088-1101 3 1 SG PORV / 2 SG SAFETIES 1102-1114 4 1 SG PORV / 3 SG SAFETIES 1115-1128 5 1 SG PORV/ 4 SG SAFETIES

>1129 6 1 SG PORV / 5 SG SAFETIES I oflI Version 7

12/31/02 8:18:58 8:18:58 12/31/02 FNP-O-E[P-9.5 FNP-0-EIP-9.5 I FIGURE 1 Calculations Based On RE-29B Noble Gas Or Iodine Channel Values (STEP 5.1)

WORKSHEET

1. Enter the noble gas release concentration in jiCi/mI from step 5.1.1 in block 1.

2. Enter the RE-29B iodine release Concentration in IiCi/ml from step 5.1.2 in block 5.

3. Enter the PVS flowrate in scfm from step 5.1.3 or 5.1.4 in blocks 2 and 6.

4. Obtain the noble gas dose rate by multiplying block I times block 2 times block 3 and enter the results in block 4.

5. Obtain the iodine dose rate by multiplying block 5 times block 6 times block 7 and enter the results in block 8.

6. Return to step 5.1.6.

noble gas release PVS flowrate conversion factor noble gas dose concentration in X (scfm) from X rate (rem/hr) pdci/ml from step 5.1.1 step 5.1.3/4 BLOCK I BLOCK 2 BLOCK 3 BLOCK 4 x x 8.54E-07 I iodine release PVS flowrate conversion factor Iodine dose concentration in X (scfm) from X rate (rem/hr) gci/ml from step 5.1.2 step 5.1.3/4 BLOCK 5 BLOCK 6 BLOCK 7 BLOCK 8 x x 9.41E-04 I oflI Version 7

12/ 31/02 8:18:58 C" * ' A F"-' FNP-0-EIP-9.5 I FIGURE 2 Calculation Based On RE-14 Count Rate (STEP 5.2)

WORKSHEET

1. Enter the RE- 14 release count rate in cpm from step 5.2.1 in block 1.

2. Enter the PVS flowrate in scfm from step 5.2.4 or 5.2.5 in block 2.

3. Obtain the noble gas dose rate by multiplying block 1 times block 2 times block 3 and enter the results in block 4.

4. Iodine dose rate must be calculated using step 5.1.2 (figure 1) or step 5.3.2 (figure 3).

5. Return to step 5.2.7.

RE-14 release count PVS flowrate conversion factor noble gas dose rate in cpm X (scfin) X f rate (rem/hr) from step 5.2.1 from step 5.2.3/4 BLOCK I BLOCK 2 BLOCK 3 BLOCK 4 x x I I_ 15.697E-16 I oflI Version 7

12/31/02 8:18:58 .... . . FNPEIP9.5 I FIGURE 3 Calculations Based On Plant Vent Stack Grab Sampling And Analyses (STEP 5.3)

WORKSHEET

1. Enter the dose equivalent Xe-133 release concentration in pci/ml from step 5.3.1 in block 1.

2. Enter the dose equivalent 1-133 release concentration in pxci/ml from step 5.3.2 in block 5.

3. Enter the PVS flowrate in scfm from step 5.3.3 or 5.3.4 in blocks 2 and 6.

4. Obtain the noble gas dose rate by multiplying block I times block 2 times block 3 and enter the results in block 4.

5. Obtain the iodine dose rate by multiplying block 5 times block 6 times block 7 and enter the results in block 8.

6. Return to step 5.3.6.

DE Xe- 133 release PVS flowrate conversion factor Noble gas dose concentration in X (scfin) from X = rate (rem/hr) jxci/ml from step 5.3.1 step 5.3.3/4 BLOCK 3 BLOCK 4 BLOCK 1 BLOCK 2 x x 8.54E-07 DE 1-131 release PVS flowrate conversion factor Iodine dose concentration in X (scfim) from X rate (rem/hr) gci/ml from step 5.3.2 step 5.3.3/4 BLOCK 5 BLOCK 6 BLOCK 7 BLOCK 8 X X 9.41E-04 I oflI Version 7

12/31/02 8:18:58 V~; T_'- FNP-0-EIP-9.5 I FIGURE 4 Calculations Based On SG Atmospheric Reliefs, Safeties and TDAFW Releases (STEP 6.0)

WORKSHEET

1. Enter the steam pressure in psig from step 6.2 for each SG with a radioactive release, determined in step 6.1, in blocks 1, 5 and 9 respectively.

2. Enter the number of valves open from step 6.3 for each SG with a radioactive release, determined in step 6.1, in blocks 2, 6 and 10 respectively.

3. Obtain the steam flow for each SG with a radioactive release by multiplying the steam pressure in blocks 1, 5 and 9 times the number of valves open in blocks 2, 6 and 10 times the conversion factor in blocks 3, 7and 11. Enter the results in blocks 4, 8 and 12.

4. If there is a radioactive release, determined in step 6.5, from the TDAFW then enter a value of 11175 in block 13 otherwise enter a value of ZERO there.

5. Obtain total steam flow by adding the values in blocks 4, 8, 12 and 13. Enter the total steam flow value in block 14 and in blocks 19 and 23 on the following page.

Steam Generator A steam pressure psig # valves open conversion factor steam flow from step 6.2 X from step 6.3 X f cfm BLOCK 1 BLOCK 2 BLOCK 3 BLOCK 4 x x 359.12 Steam Generator B steam pressure psig # valves open conversion factor steam flow from step 6.2 X from step 6.3 X cfmn BLOCK 5 BLOCK 6 BLOCK 7 BLOCK 8 x x 359.12 Steam Generator C steam pressure psig # valves open conversion factor steam flow from step 6.2 X from step 6.3 X = cfmn BLOCK 9 BLOCK 10 BLOCKI 1 BLOCK12 x x 359.12 TDAFW If there is a radioactive release from the TDAFW then enter a value of BLOCK 13 11175 in block 13 otherwise enter a value of ZERO Total Steam Flow Add the Steam flow from all three SGs and the TDAFW and enter the BLOCK 14 value in block 14 and in blocks 19 and 23 on the following page I of 2 Version 7

12/31/028:18:58 f' { / f* F*

, FNP-0-EIP-9.5 I FIGURE 4

6. Enter the total iodine release concentration from step 6.8 in block 15.

7. Enter the ratio of total iodine to 1-131 from step 6.9, step 6.10 or figure 6 in block 16.

8. Determine the Iodine 131 release concentration by dividing block 15 by block 16 enter the value in block 17 and block 22.

9. Enter the noble gas release concentration from step 6.7 in block 18.

10. Enter the steam release flow rate (cfm) from step 6.6 (Block 14 from the previous page).

11. Obtain the noble gas dose rate by multiplying block 18 times block 19 times block 20 and enter the results in block 21.

12. Obtain the iodine dose rate by multiplying block 22 times block 23 times block 24 and enter the results in block 25.

13. Return to step 6.12.

total iodine release concentration in ratio of total iodine to iodine 131 release Aci/ml 1I-131 concentration in from step 6.8 from step 6.9/10 11ci/ml BLOCK 15 BLOCK 16 BLOCK 17 noble gas release steam flow rate conversion factor noble gas dose concentration (tci/ml) X (cfm) from step X - rate (rem/hr) from step 6.7 6.6 (block 14)

BLOCK 18 BLOCK 19 BLOCK 20 BLOCK 21 x x 3.85E-05 =

iodine 131 release steam flow rate conversion factor iodine dose concentration in X (cfmn) from step X = rate (rem/hr) gici/ml from step 6.6 (block 14) 6.9/10 block 17 BLOCK 22 BLOCK 23 BLOCK 24 BLOCK 25 x x 4.24E-02 =

2 of 2 Version 7

12/31/02 8:18:58 FNP-0-EIP-9.5 I FIGURE 5 Calculation Based On Steam Jet Air Ejector Release (STEP 7.0)

WORKSHEET

1. Enter the total iodine release concentration from step 7.2 in block 1.

2. Enter the ratio of total iodine to 1-13 1 from step 7.3, step 7.4 or figure 6 in block 2.

3. Determine the Iodine 131 release concentration by dividing block 1 by block 2. Enter the value in block 3 and block 7.

4. Enter the noble gas release concentration from step 7.1 in block 4.

5. Obtain the noble gas dose rate by multiplying block 4 times block 5 and enter the results in block 6.

6. Obtain the iodine dose rate by multiplying block 7 times block 8 and enter the results in block 9.

7. Return to step 7.6.

total iodine release ratio of total iodine iodine 131 concentration in gci/ml to 1-131 release from step 7.2/ from step 7.3/4 concentration in *ci/ml BLOCK 1 BLOCK 2 BLOCK 3 noble gas release concentration conversion factor, noble gas dose in IiCi/ml X includes 1050 scfm = rate (rem/hr) from step 7.1 flow BLOCK 4 BLOCK 5 BLOCK 6 x 4.0425 E-02 F,=I iodine 131 release concentration conversion factor, iodine dose in pci/ml X includes 1050 scfm - rate (rem/br) from step 7.3/4 (block 3) flow BLOCK 7 BLOCK 8 BLOCK 9 x 44.52S.............................

I oflI Version 7

12/31/02 8:18:58 8:18:58 12/31/02 FNP-O-EIP-9.5 FNP-0-EIP-9.5 I Figure 6 RATIO OF TOTAL IODINES TO IODINE - 131 10 9

8 7

6 5

4 3

2 1

0 0 10 20 30 40 50 60 70 80 90 100 ELAPSED TIME SINCE SHUTDOWN (HOURS)

I oflI Version 7

12/31/02 818:58 FNP-0-EiP-9.5 Figure 7 Unit X ODCM NON REGULATORY ERDS/ARDA Date Time Unit Group Display Print Start Dose Assessment ODCM Dose Assessment Print Screen telease Point Met Information Radiation Monitors Plant Parameters Previous History Inventory QDCM Options USE IN Previous Hour EXCEEDED Peak Projected TOTAL

[X] RE 29B Noble Gas Dose Rate X.XXE-XX X.XXE-XX R/HR Iodine Dose Rate X.XXE-XX X.XXE-XX R/HR

[ ] RE 14 Noble Gas Dose Rate X.XXE-XX X.XXE-XX R/HR

[ ] RE 15 Noble Gas Dose Rate X.XXE-XX X.XXE-XX RIHR Iodine Dose Rate X.XXE-XX X.XXE-XX R/HR

[ ] RE 60A Noble Gas Dose Rate X.XXE-XX X.XXE-XX R/HR Iodine Dose Rate X.XXE-XX X.XXE-XX R/HR

[ ] RE 60B Noble Gas Dose Rate X.XXE-XX X.XXE-XX R/HR Iodine Dose Rate X.XXE-XX X.XXE-XX R/HR

[ ] RE 60C Noble Gas Dose Rate X.XXE-XX X.XXE-XX R/HR Iodine Dose Rate X.XXE-XX X.XXE-XX R/HR RE 60D Noble Gas Dose Rate X.XXE-XX X.XXE-XX R/HR Iodine Dose Rate X.XXE-XX X.XXE-XX R/HR Total Noble Gas X.XXE-XX X.XXE-XX RIHR Iodine X.XXE-XX X.XXE-XX R/HR Noble Gas NOUE Limit = 5.7E-05 R/HR Noble Gas ALERT Limit = 5.7E-04 R/HR Iodine NOUE Limit = 1.7E-04 R/HRI Iodine ALERT Limit = 1.7E-03 R/HR I oflI Version 7

12/31/02 9:41:30 vA r FNP-0-EIP-9.0

-. December 5, 2002 Version 49 FARLEY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE 9.0 FNP-0-EIP-9.0 S

A F

E T

Y EMERGENCY CLASSIFICATION AND ACTIONS R

E L

A T

E D

PROCEDURE USAGE REQUIREMENTS PER FNP-0-AP-6 SECTIONS Continuous Use Reference Use ALL Information Use =_ _

Approved:

Nuclear Plant General Manager Date issued j*XL" UNCONTROLLED COPY CAUTION: wtuwnwrm ewet Do rnut us ina Safety RoPed Act*'4

12/31/02 9:41:30 C FNP-0-EIP-9.0 TABLE OF CONTENTS Procedure Contains Number of Pages Body ............................................................................. 7 Attachment 1..................................................... 5 Guideline 1....................................................... I I Guideline 2 ....................................................... I I Guideline 3 ....................................................... 11 Guideline 4 .................................................... 10 Table 1............................................................ 1 Table 2 ............................................................ 1 Table 3 ............................................................ 1 Table 4 ............................................................ I Figure 1............................................................ 1 Figure 2 ............................................................ 1 Figure 3 ............................................................ 1 Figure 4 ......................................................... 0 Figure 5 ......................................................... 0 Figure 6 ......................................................... 2 Figure 7 ............................................................ 1 Figure 8 ............................................................ 1 Page i of iii Version 49

12/31/02 9:41:30 J. FNP-0-EIP-9.0 EMERGENCY CLASSIFICATION AND ACTIONS TABLE OF CONTENTS Section Title Page 1.0 Purpose 1 2.0 References 1 3.0 General 1 4.0 Classify Emergency 3 5.0 Perform Actions and Initial Notification 6 6.0 Continue Reassessment 6 7.0 Downgrade or Closeout 7 Emergency Notification Form Guidance Guideline 1 General Emergency Guideline 2 Site Area Emergency Guideline 3 Alert Guideline 4 Notification of Unusual Event Table 1 References Table 2 Emergency Facility Activation Table 3 Considerations for Emergency Classifications Based on Security Events Table 4 Information Likely to be Requested by the NRC if an Emergency is Declared Figure 1 10 Mile Emergency Planning Zone Figure 2 Event (Flowpath)

Figure 3 Telecopy Group Dial Numbers Page ii of iii Version 49

12/31/02 9:41:30 1FNP-0-EIP-9.0 EMERGENCY CLASSIFICATION AND ACTIONS TABLE OF CONTENTS Figure 4 Deleted Figure 5 Deleted Figure 6 (Side 1) Emergency Notification Figure 6 (Side 2) Notification Means Figure 7 Emergency Notification Continuation Sheet Figure 8 Dose Equivalent Iodine Estimation Page iii of iii Version 49

12/31/02 9:41:30 - FNP-.-EIP-9.0 EMERGENCY CLASSIFICATION AND ACTIONS 1.0 Purpose The purpose of this procedure is to provide a method for rapid projection of estimated offsite radiation exposures as a result of a release of radioactive material, to provide the basis for classifying emergencies based on plant conditions and automatic dose calculations, to provide guidance for determining protective action recommendations, to provide guidelines for actions, and for notification guidance.

2.0 References See Table 1.

3.0 General

3.1 This procedure provides criteria for the classification of an emergency based on plant status and radiological hazards (i.e., direct radiation and inhalation hazards which may result from the passage of a cloud of radioactive material released from the plant).

3.2 Assessment of radioactive liquid releases will be made using the offsite Dose Calculation Manual.

3.3 Release time is defined as follows:

3.3.1 EDCM Calculations: The period of time from the most recent projection to the estimated time of release termination.

3.3.2 ODCM Calculations: The period of the release in which Technical Specification limits are exceeded.

3.4 Definitions

TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) means the sum of the deep dose equivalent (for external exposures) and the committed effective dose equivalent (for internal exposures).

DEEP DOSE EQUIVALENT (DDE) which applies to external whole body exposure, is the dose equivalent at a tissue depth of I cm.

-I- Version 49

12/31/02 9:41:30 FNP-0-EIP-9.

COMMITTED DOSE EQUIVALENT (CDE) means the dose equivalent to organs or tissues of reference that will be received from an intake of radioactive material by an individual during the 50-year period following the intake.

COMMITTED EFFECTIVE DOSE EQUIVALENT (CEDE) is 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 of tissues.

3.5 Protective action recommendation guidance is provided to aid in establishing protective action recommendations. The Emergency Director will exercise his own judgment in recommending protective actions to offsite agencies.

3.6 If steam generator water level falls below the break point during a steam generator tube rupture, off-site dose rate maybe significantly higher (up to 10 times) due to volatilization of iodine.

3.7 Initial Notification or upgrade should be made from the Control Room or TSC. It is not necessary to transfer the information to the EOF to make the upgrade notification. The EOF, if staffed, should be informed as soon as possible.

3.8 Communication guidance for making the initial verbal notification is on the Emergency Initial Notification Form, in the appropriate guideline.

3.9 Guidance for when the emergency response facilities should be manned and the level of manning required is included in Table 2. It is recommended that the TSC and the EOF be fully staffed initially at the ALERT level. If the full staff is not required, individuals can be released on a case-by-case basis.

3.10 At the NOUE level or below, it may be desirable to partially staff the TSC in order to relieve the Control Room staff of offsite communications and notifications. FNP-0-EIP-6.0 provides a listing of positions that should be considered for partial TSC activation.

3.11 EIP-6, Figure 3, provides a list of information that should be considered when updating plant staff over the public address system.

Version 49

12/31/02 9:41:30 FNP-O-EIP-9.0 4.0 Classify emergency based on the most severe plant conditions OR projected off-site "dose/doserate conditions, WHICHEVER results in the higher emergency classification.

Figure 2 provides a ftowpath for dose assessment methods and plant conditions criteria.

4.1 Plant Conditions While performing the remainder of step 4.1, have the Shift Radio Chemist (SRC) commence performing the calculations for dose assessment per step 4.2. Use the following guidelines to determine the highest indicated emergency classification based on plant conditions:

Guideline 1,Section I, General Emergency Classification Criteria Guideline 2,Section I, Site Area Emergency Classification Criteria Guideline 3,Section I, Alert Criteria Guideline 4,Section I, NOUE Criteria 4.2 Dose Assessment CAUTION: DOSE CALCULATIONS FROM EIP-9.1 OR EEP-9.3 ARE NOT TO BE USED TO DECLARE A NOUE OR ALERT SINCE EIP-9.1 AND EIP-9.3 ARE BASED ON EDCM METHODOLOGY, AND NOUE AND ALERT LIMITS ARE BASED ON ODCM METHODOLOGY.

NOTE: Due to the differences in the met data used for EDCM and ODCM calculations, the following sequence of step 4.2 substeps must be followed. The Top Down approach must be used for dose assessment.

NOTE: EDCM dose assessment can only be done from an ERDS terminal or a MIDAS terminal. The only location in the power block where these terminals are available is in the TSC.

NOTE: All of the step 4.2 substeps will normally be accomplished by the SRC with the exception of steps 4.2.8 and 4.2.11. Steps 4.2.8 and 4.2.11 must be performed by the Shift Supervisor, Operations Shift Superintendent, or Emergency Director.

4.2.1 Initial evaluation of off-site dose.

The shift radio chemist (SRC) when asked to perform dose assessment should initially evaluate effluent monitors (R-14, R-21, R-22, R-29, an R 60 series or an R-15 series) as follows:

Version 49

12/31/02 9:41:30 -

• i F}

• FNP-0-EIP-9.0 4.2.1.1 If there are no effluent radiation monitors that are in alarm or have up-scaled by a factor of 10 or more, and there are no other indications of an off-site radioactive release in progress, then The SRC should report to the ED that there is no indication of a radioactive release based on effluent monitors and NO additional dose assessment per step 4.2 is required. Continue to perform this assessment periodically not to exceed 30 minutes until the requirement is terminated by the ED.

4.2.1.2 If any effluent radiation monitor is in alarm or has up-scaled by a factor of 10 or more, or there are other indications of an off-site radioactive release in progress, then For initial dose assessment from the TSC, proceed to step 4.2.4.

4.2.2 For dose assessment from the EOF or long term dose assessment from the TSC, go to EIP-9.3, PERSONNEL COMPUTER-AUTOMATED DOSE ASSESSMENT and perform dose assessment using the MIDAS program.

Return to step 4.2.8 for evaluation of dose information and continue with step 4.2.9.

4.2.3 If the MIDAS program is inoperable, then for dose assessment from the EOF or from the TSC, go to EIP-9. 1, AUTOMATED DOSE ASSESSMENT and perform dose assessment using the ARDA program to obtain dose information. Return to step 4.2.8 for evaluation of dose information and continue with step 4.2.9.

4.2.4 If the ARDA System is operable and has been automatically activated, then go to EIP-9. 1, AUTOMATED DOSE ASSESSMENT and perform dose assessment using the ARDA program to obtain dose information.

Return to step 4.2.8 for evaluation of dose information and continue with step 4.2.9.

4.2.5 If the ARDA System per EIP 9.1 is operable, has not automatically activated, and one of the following rad monitors has alarmed:

"* R-29

"* R-15C

"* R-60 A, B, C, or D Version 49

12/31/02 9:41:30 FNP-0-EIP-9.0 SHAP,-ED1

• R-14

• R-21

• R-22 Then go to EIP-9.1, AUTOMATED DOSE ASSESSMENT, manually start ARDA and perform dose assessment using the ARDA program to obtain dose information. Return to step 4.2.8 for evaluation of dose information and continue with step 4.2.9.

4.2.6 If the ARDA system per EIP 9.1, AUTOMATED DOSE ASSESSMENT is NOT operable, then go to EIP-9.3, PERSONAL COMPUTER AUTOMATED DOSE ASSESSMENT and perform dose assessment using the MIDAS program. Return to step 4.2.8 for evaluation of dose information and continue with step 4.2.9.

4.2.7 If the ARDA system per EIP 9.1 AUTOMATED DOSE ASSESSMENT is operable, has not automatically activated, and none of the alarms listed in step 4.2.5 have alarmed then go to EIP-9.5, EMERGENCY CLASSIFICATION BASED ON ODCM to perform dose assessment.

Return to step 4.2.11 for evaluation of doserate information.

NOTE: Evaluating the dose assessment information In Step 4.2.8 must be performed by the Shift Supervisor, Operations Shift Superintendent, or Emergency Director in the Control Room or TSC, the DAD or Recovery Manager in the EOF.

4.2.8 Using the dose information obtained from EIP-9.1 or EIP-9.3, determine the highest indicated emergency classification from the "High Effluent" criteria in Guideline 1,Section I, or Guideline 2,Section I.

NOTE: If a General Emergency or site area emergency is indicated in the following step, the Emergency Director should consider directing long term dose assessment be performed from the TSC per step 4.2.2.

4.2.9 If a General Emergency or Site Area Emergency was indicated from step 4.2.8, then go to step 4.3.

4.2.10 If a General Emergency or Site Area Emergency was not indicated in step 4.2.8, then go to EIP-9.5, EMERGENCY CLASSIFICATION BASED ON ODCM. Return to step 4.2.11 for evaluation of doserate information.

Version 49

12/31/02 9:41:30 4 FNP-0-EIP-9.0 NOTE: Evaluating the dose assessment information in Step 4.2.11 must be performed by the Shift Supervisor, Operations Shift Superintendent, or Emergency Director in the Control Room or TSC, the DAD or Recovery Manager in the EOF.

4.2.11 Using the dose rate information obtained from EIP-9.5, determine the highest indicated emergency classification from the "High Effluent" criteria in Guideline 3,Section I, and Guideline 4,Section I.

4.3 Determine the correct emergency classification, declare the emergency at the time the classification was verified in the Guideline, determine PARs and make notifications.

4.3.1 Compare the emergency classifications determined from steps 4.1 and 4.2 to determine the highest required emergency classification and declare the emergency. Do not wait for dose assessment results from step 4.2 to classify the event if plant conditions require an initial classification or an upgrade classification. As soon as a criteria for classification has been met, the event should be classified by the Operations Shift Superintendent or ED and an upgrade can be done later if required.

4.3.2 Using section L of the guideline for the highest emergency classification determined in step 4.3.1, determine the required protective action recommendations.

4.3.3 Complete the initial notification form at the back of the guideline and perform required notifications.

5.0 Perform actions and initial notification to offsite authorities upon initial entry or upgrade into a classification using the applicable guideline:

Guideline 1,Section II - General Emergency Guideline 2,Section II - Site Area Emergency Guideline 3,Section II - Alert Guideline 4,Section II - Notification of Unusual Event 6.0 Continue reassessment of emergency classification per step 4.0 or 7.0, as appropriate, and transmit follow-up message/periodic update message as follows:

6.1 Transmit Follow-up Messages:

Version 49

12/31/02 9:41:30 4. . *: FNP-0-EIP-9.0 6.1.1 Transmit a follow up message as soon as possible following an initial or upgrade verbal notification but no longer than 30 minutes after the verbal notification has been transmitted over the ENN. Refer to step 6.2 for time limits for other follow-up messages.

6.1.2 Use, if desired, Attachment 1, for guidance in completing and transmitting the "Emergency Message" for Follow Up/Periodic Update (Figure 6).

6.1.3 When performing dose assessment, transcribe dose information from the form being printed on a blank Figure 6 or use the form being printed. Fill in the remaining information. Transmit follow up message by telecopy.

NOTE: EFFORTS WILL BE MADE TO TRANSMIT FOLLOW-UP REPORTS EVERY I I NTE:HALF HOUR.

6.2 Transmit subsequent "Follow Up Message/Periodic Update Message" reports per step 6.1.

6.2.1 At a minimum of once per hour. The hourly requirement may be waived while in a NOUE declaration, if this is agreed to by the state and local agencies.

6.2.2 Following a significant change in dose rate that does not require a change in emergency classification.

6.2.3 Following a significant change in plant conditions that does not require a change in emergency classification.

7.0 Downgrade or closeout an emergency classification after determining, through the use of the guidelines, that the current emergency classification is no longer required. FNP-0 EIP-28.0 will be used to downgrade or closeout an emergency class Version 49

12/31/02 9:41:30 r *TT - N FNP-0-EIP-9.0 ATTACHMENT I EMERGENCY NOTIFICATION FORM GUIDANCE 1.0 Emergency Notification Form Guidance is provided below. The guidance is provided for filling out the Emergency Notification Form (FIGURE 6). This attachment can be used as reference guidance when filling out the form or for training.

1.1 A VERBAL NOTIFICATION of a declared emergency or an upgrade to a higher level declared emergency shall be performed in accordance with Guidelines 1 through 4 using the appropriate Verbal Notification Form.

1.2 A FOLLOW-UP MESSAGE will be used to make periodic plant status updates using Figure 6. This attachment is a REFERENCE to use as necessary for completing Figure 6.

NOTE: OR BLACKENING IN.DICATED BY A CHECK, AN "X", OR BY FILLING Line 1

• Check A or B.

• Except for actual emergencies A should be checked in training and for drills/exercises.

• Check D.

• D should be checked for Follow-up Messages described in step 1.2 above. Note the single asterisk associated with box D for Follow-up Messages.

• The Follow-up message numbers are sequential, starting with 001.

Line 2

"* Specify Unit 1, 2, or both. If both is entered consider describing the least affected unit reactor status in line 7.

"* Reported by is the individual who filled out the form.

Page I of 5 Version 49

12/31/02 9:41:30 D T2_7. D"' FNP-0-EIP-9.0 ATTACHMENT I Line 3

"* Fill in the time/date of this message just prior to transmitting.

"* Fill in an extension number that will be staffed so that the state and county agencies have a place to talk to someone that can help them. A Direct inward dial number may be entered. In the TSC, EOF or Control Room (334) 814-4662 and (334) 814-4663are dedicated for call in by the states.

"* Select TSC, EOF or fill in a separate fax number that will be staffed, so that the state and county agencies have a location where they can fax information if necessary Line 4

• This line is not used at FNP. It remains on the form to maintain conformity with other state forms.

Line 5

• Check A, B, C or D (only one) as appropriate. Check no boxes if this is a termination.

Line 6 o Check A or B. Time is for the declaration checked in line 5 or the time of termination..

Termination should only be done after conversation with off-site authority per FNP-0-EIP 28.0. If this is a termination, go to line 16.

Line 7

"* Provide a brief, concise summary of plant conditions that requires the classification and other pertinent information.

"* Enter the classification criteria used in words; the criteria code may also be included.

"* If more space is needed, check box E and use the continuation sheet.

"* If any of the items in block A, B, C or D apply, check them as well.

Line 8

"* Check A, B or C.

"* A should be checked if mitigation efforts appear successful , progressing toward termination/recovery.

"* B should be checked if escalation to a higher classification is unlikely based on current conditions.

"* C should be checked if escalation to a higher emergency classification or PAR change is likely.

"* Check D if RMTs have been dispatched off-site

"* Check E if personnel not needed to support recovery efforts have been released from the site.

This provides the state and county information as to who to expect to see in the 10 mile EPZ Page 2 of 5 Version 49

1,2/31/02 9:41:30 ~ IQ AI'i~ FNP-0-EIP-9.0 ATTACHMENT 1 Line 9

"* Check A or B to provide information about the affected unit.

"* If both units are affected provide the least affected unit information in line 7 and the most affected unit information here

"* If A is checked complete the time that the reactor was shutdown

"* If B is checked, provide the current reactor power from N41, 42, 43 or 44.

Line 10

"* Check A, B, C or D (only one).

"* Check A if the criteria for a (B) Potential Release, (C) Is Occurring or (D) Has Occurred has not been met

"* If A is checked, go to line 14 to provide meteorological data. Off-site agencies still want line 14 information in order to know what zones might be affected. No information should be filled in for lines 11, 12 or 13.

"* Check B for potential failures of the final barrier to the release of fission fragments.

Examples of potential releases are the RCS and clad barriers that are known to be failed and containment pressure is above design value, or the clad and containment barriers are failed and a pressurizer safety valve is stuck with PRT pressure rising. For potential releases, do not put estimated or potential values for the release information inr lines 11, 12, or 13, because there is no release in progress.

"* If B is checked, go to line 14 to provide meteorological data. Off-site agencies still want line 14 information in order to know what zones might be affected. No information should be filled in for lines 11, 12 or 13.

"* Check box C If an emergency release is occurring. An emergency release should be considered to exist if an abnormal increase in radiological release rate by a factor of 10 over and above normal operating levels has occurred. Normal operating levels are average release levels for steady-state operations (may be obtained from ERDS, RMDA, control room recording, or plant computer).

• If A Site Area Emergency or General Emergency has been declared and a release is in progress, complete the information in lines 11, 12 and 13 based on the values obtained from an EDCM calculation (MIDAS or ARDA)

• If a NOUE or an ALERT has been or can be declared based on the release in progress then provide the release information in line 7 as directed by step D of Guideline 3 or 4. Do not provide any information in lines 11, 12 or 13 except for checking 12D to indicate that the release is above Technical Specification limits

• Check Box D-if arelease that-was large enough to require an emergency classification of NOUE or above to be declared had occurred but is now stopped.

"* If EDCM dose assessment information has already been provided in lines 11, 12 and 13 in previous messages continue to provide this information.

"* If a new estimate of projected off site dose is not available then do not provide data in lines I through 13, go directly to line 14.

Page 3 of 5 Version 49

ATTACHMENT 1 Line I1

"* For actual releases only, normally check A

"* Mixed mode calculations are normally not done at FNP

"* Fill in actual start/stop times for C, D, E and F as appropriate. It is not necessary to check the boxes when data is being entered into the blanks.

Line 12

"* The ARDA and MIDAS programs provide release rate in ptCuries/Sec. Check box A.

"* For all emergency releases check C or D to indicate if release is above or below Technical Specification limits. Any release that can be used to declare a NOUE or above is above Technical Specification Limits and if no emergency can be declared it is below Technical Specification limits

"* The data for completing blanks E, F, G and H on this line is available from the MIDAS or the ARDA printout.

"* It not necessary to check the boxes when data is being entered into the blanks.

Line 13

"* For all new dose assessment calculations that are to be reported, then check new and fill in Blanks C through K. Note that line 14 meteorological data must be the same data that was used in performing the new dose assessment calculation.

"* If there has been no new dose assessment calculation performed since the last message, then check box B and leave all other line 13 blanks empty.

"* Box B can also be checked to if the intent of the message is to report rapid changes in emergency status, plant conditions, meteorological conditions or changes in PARS without performing a new dose projection.

"* In blank C fill in the length of time in hours that the release is expected to continue from the current time. Four hours should always be assumed if the actual time is unknown.

"* The data for completing blanks D through K on this line is available from the MIDAS or the ARDA printout.

"* It not necessary to check the boxes when data is being entered into the blanks.

"* For ODCM calculations (for NOUE or Alert), do not enter dose information here. Place the dose information in the comments at line 7, along with the notes that are specified in the NOUE and Alert Guidelines if declaration is based on the ODCM.

Line 14

"* Fill in the meteorological data required in A through D. Note that line 14 meteorological data must be the same data that was used in performing the dose assessment calculation information provided on line 12 and 13.

"* When possible use 15 minute average data, available from the NR ERDS MIDAS page Page 4 of 5 Version 49

12/31/02 9:41:30 Q  !* \ *. , FNP-0-EIP-9.0 ATTACHMENT I Line 15

"* Refer to Step L of the appropriate FNP-0-EIP-9.0 Guideline to determine appropriate Protective action Recommendations (PARs).

"* If there are no protective action recommendations, check box A and proceed to step 16.

"* Specific protective actions must be made for a general emergency.

Line 16

"* "Approved by" should be the Emergency Director or Recovery Manager, with the current date and time.

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12/31/02 9:41:30 Q P . FNP-0-EIP-9.0 J--i-

' '7"`ýGUIDELINE 1 GUIDELINE I GENERAL EMERGENCY I. Criteria for Classification The classification of General Emergency applies to those events which are in progress or have occurred which involve actual or imminent substantial core degradation or melting with potential loss of containment integrity. The potential for release of radioactive material for the General Emergency classification is more than 1000 Ci of 1-131 equivalent or more than 106 Ci of Xe-133 equivalent.

The purpose of the declaration of a General Emergency is to:

(a) Initiate predetermined protective actions for the public.

(b) Provide continuous assessment of information from licensee and offsite measurement.

(c) Initiate additional measures as indicated by event releases or potential releases and, (d) Provide current information for and consultation with offsite authorities and the public.

A General Emergency would be declared for any of the following:

1.0 HIGH EFFLUENT Projected exposure at site boundary or for projected peak dose location within the plume for EDCM calculation:

G1.1 Greater than or equal to 1.0 REM (1000 MREM) TEDE exposure OR G1.2 Greater than or equal to 5.0 REM (5000 MREM) thyroid CDE exposure Page I of 11 Version 49

12/31/02 9:41:30

• NP-_-E**, .0 KL -GUIDELINE 1 GUIDELINE 1 GENERAL EMERGENCY 2.0 FISSION PRODUCT BARRIERS G2.1 Loss of two of three fission product barriers with a potential loss of the third. The following describe indication of loss of these boundaries:

(a) Fuel cladding damage indicated by:.

1. RCS activity > 300 jtCi/gram dose equivalent 1-131.

Figure 8 may be used to help evaluate if Dose Equivalent 1-131 (DEI) is> 300 ttCi/gram.

OR

2. Loss of core geometry is indicated by AT between RCS wide range hot leg and cold leg temperature of > 640 F and core exit temperature (incore thermocouples) reading greater than 12000 F.

(b) Loss of primary coolant boundary as indicated by:

1. Containment pressure reaching 27 psig AND

2. High containment radiation (R-2, R-22 and R-12, reaching their alarm setpoint) AND,

3. High containment humidity.

(c) Loss or potential loss of containment integrity is indicated by:

1. Containment pressure greater than 54 psig, OR

2. A rapid decrease in containment pressure, OR

3. Failure of the containment isolation system resulting in a direct path from containment to the environment.

(d) Other plant conditions exist, from whatever source, that make release of large amounts of radioactivity in a short time period possible, such as any core melt situation.

Page 2 of 11 Version 49

12/31/02 9:41:30 IA-R ED FNP-0-EIP-9.0 GUIDELINE 1 GUIDELINE 1 GENERAL EMERGENCY 3.0 SECURITY/EVACUATION G3.1 Loss of physical control of the facility. If the basis for declaring this emergency classification is based on security concerns then refer to table 3 prior to taking actions that will cause people to report to the site or change locations on site Page 3 of 11 Version 49

12/31/02 9:41:30 QL T J-z*U *.-

~ TFNP-0-EIP-9.O GUIDELINE 1 GUIDELINE 1 GENERAL EMERGENCY II. Emergency Director Actions NOTE: THE OPERATIONS SHIFT SUPERINTENDENT SHALL PERFORM THE DUTIES OF THE EMERGENCY DIRECTOR UNTIL HIS ARRIVAL AND ASSUMPTION OF DUTIES.

NOTE: ACTIVATION OF THE TSC AND EOF STAFFS, PER STEPS El AND E2, SHOULD BE DONE IN PARALLEL WITH NOTIFICATION OF THE STATE AND LOCAL AGENCIES.

Initials A. If the Plant Emergency alarm has not already been activated, then announce over the public address system "All Plant Personnel Report to Designated Assembly Area," activate the PEA for 30 seconds and repeat the announcement.

B. Announce the condition, request setup of the TSC and EOF and give needed evacuation instructions over plant public address system.

I NOTE: IF POSSIBLE AND TIME PERMITTING, DISCUSS WITH ALABAMA RADIATION CONTROL AND GEORGIA EMERGENCY MANAGEMENT AGENCY ABOUT THE PARs PRIOR TO ANNOUNCING THEM OVER THE ENN.

C. Fill in the General Emergency Initial Notification Form (last two pages of this guideline), including developing protective action recommendations per step L.

Take into account the zones and evacuation time estimates shown in Figure 1.

Page 4 of 11 Version 49

12/31/02 9:41:30 FNP-0-EIP-9.0 L)1.*. .. . L,.-.-.-.* GUIDELINE I GUIDELINE 1 GENERAL EMERGENCY NOTE: INITIAL NOTIFICATIONS WILL NORMALLY BE MADE BY THE SHIFT CLERK, BUT MAY BE MADE BY OPERATIONS STAFF, TSC STAFF OR OTHER QUALIFIED PERSON USING THE INITIAL NOTIFICATION FORM (LAST TWO PAGES OF THIS GUIDELINE).

NOTE: INITIAL AND UPGRADE CLASSIFICATIONS AND NOTIFICATIONS SHOULD BE PERFORMED BY THE CONTROL ROOM OR THE TSC STAFF, WITH THE EOF INFORMED AS SOON AS POSSIBLE.

D. Initial Notifications

1. Within 15 minutes of declaration, verbally notify the state and local agencies using the General Emergency Initial Notification Form (last two pages of this guideline).

2. Verify notifications complete and documented on the General Emergency Initial Notification Form (last two pages of this guideline).

E. Emergency Organization Notifications NOTE: STEPS El AND E2, NOTIFYING THE TSC AND EOF STAFF, WILL NORMALLY BE ACCOMPLISHED BY HAVING THE SHIFT CLERK COORDINATE ACTIVATION OF THE ERO CALLOUT SYSTEM PER FNP

.0-EIP-8.3, TABLE 2 AND STEP 11.

2. TSC Staff (full activation required)

2. EOF Staff (full activation required)

3. On-call Emergency Director

4. On-call Recovery Manager

5. Emergency Support Manager

6. Notify Security of Emergency, incoming personnel, access restrictions and to setup the EOF (pax 4611).

Page 5 of 11 Version 49

12/3102 9:1:30FNP-0-EIP-9.0 121029413 GUIDELINE 1 GUIDELINE 1 GENERAL EMERGENCY F. Other Notifications

1. NRC (Perform immediately after state notification and within one hour of declaration per Figure 6, side 2).

2. Have Regulatory ERDS activated to transmit data to the NRC within one hour of the declaration of the emergency (EIP-8-3, step 10).

3. If personnel injury or fire is involved, refer to FNP-0-EIP- 11.0 and 13.0 respectively for additional actions and EIP-8.0 steps 5.0 and 6.0 for additional notification requirements.

4. U.S. Army EOD group at Fort Benning, GA, if necessary.

5. Savannah River Operations Office, if necessary.

6. If there is a security event involved ensure appropriate notifications and actions of FNP-0-AOP-49 and FNP-0-SP 37.0 are performed G. In Plant Protective Actions S1. Ensure personnel accountability per EIP- 10.0.

2. Plan and initiate reentry's per EIP-14.0.

3. Ensure proper Control Room response.

4. Assign an individual to provide periodic plant status updates.

5. Assign an individual to maintain a log of important Emergency Director activities.

6. Assign an individual to keep a record of all off-site communications.

7. Determine what should be done with a unit that is not affected by the declared emergency. Consider the effect on the emergency unit, manpower utilization, plant and grid stability, and other relevant factors.

Page 6 of 11 Version 49

12/31/02 9:41 :30 Q IFNP-EI9.

1* *.-

• Di* GUIDELINE 1 GUIDELINE 1 GENERAL EMERGENCY H. Off-Site Support

1. Ensure Radiation Monitoring teams have been dispatched per EIP-4.0.

2. Provide information to the Recovery Manager for use in press releases and recovery planning.

I. Information to Off Site Authorities I. Provide periodic plant status updates, meteorological and dose estimates and release projections based on plant conditions and foreseeable contingencies.

J. Re-Assess plant conditions S1. Continue to assess plant and radiological conditions to ensure the correct emergency classification is declared.

2. If plant and radiological conditions no longer require the current emergency K. classification downgrade or close out the emergency class using FNP-0-EIP-28.0.

K. Long term concerns S1. Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, provide for full TSC and OSC reliefs.

2. Within 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />, provide for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TSC and OSC coverage.

3. If an LOSP has occurred evaluate the event to ensure that an adequate supply of fuel oil is available for the Diesel Generators for 7 days. Refer to REA 00-2337 and FNP-0-SOP-42.0 Figure 1.

Page 7 of 11 Version 49

12/31/02 9:41:30 C A P 1 F FNP-0-EIP-9.0 GUIDELINE I GUIDELINE 1 GENERAL EMERGENCY NOTE: Only the technically based protective actions specified below should be recommended unless there are obvious relevant factors (e.g., severe natural phenomena) that probably were not anticipated when the PARs were developed and that would make the standard PAR recommendations Impractical or obviously non-conservative. In such events, the emergency director should use his own judgment as appropriate.

L. Protective action recommendation guidance

a. EVACUATE AND CONTROL ACCESS IN DOWNWIND ZONES Recommend immediate evacuation for all of the general population and controlling access within a two mile radius of FNP (Zone A) and 5 miles downwind of FNP (Zones B-5, C-5,...K-5).

"* When evacuating 5 mile downwind zones, disregard portions of the 10 mile zones, D-10 through GIO and 1-10 through K-10, which fall within 5 miles of FNP.

"* Recommendation of a partial evacuation of a zone is not allowed.

"* Consider wind direction variability for inclusion of zones adjacent to the plume.

"* Recommendation should include zones that fall within approximately 45 degrees (22.5 degrees on either side) of the down wind direction.

"* Evacuation time estimates indicated on Figure 1 for the effected zones should be considered when making evacuation recommendations.

b. SHELTER AND CONTROL ACCESS IN DOWNWIND ZONES Recommend immediate sheltering of the general population and controlling access in the 10 mile downwind zones (B-10, C-I0,...K-10), unless more extensive protective actions are known to be required.

"* Recommend locating and evacuating hot spots.

"* Recommend implementing control of food and water supplies pending.

"* Sampling and analysis and possible confiscation in certain areas.

"* Recommend monitoring of environmental radiation levels.

"* Recommend to consider evacuation of children and pregnant women.

"* Recommendation of partial sheltering of a zone is not allowed.

"* Consider wind direction variability.

"* Consideration should be given to zones adjacent to the plume.

"* Recommendation should include zones that fall within approximately 45 degree (22.5 degrees on either side) of the down wind direction.

(PARs continued on next page)

Page 8 of I Version 49

J_. T7}  : FNP-0-EIP-9.0 12/31/02 9:41:30 *]

A X , . GUIDELINE I GUIDELINE 1 GENERAL EMERGENCY

c. If dose projections or measured values indicate that General Emergency TEDE or Thyroid CDE limits are exceeded beyond the 5 miles that would normally be evacuated, then consider making the following additional recommendations (Do not delay sending the initial pre determined PARs to do this step.):

"* The ED should use best judgement when making these recommendations.

"* Many assumptions exist in dose assessment calculations involving both source term and meteorological factors which make computer predictions over long distances highly conservative and subject to scrutiny.

"* RMTs should normally be dispatched to verify radiation levels prior to making PARs beyond the above pre-determined PARs.

"* If GE TEDE or CDE limits are exceeded between 5 and 10 miles, consider recommending evacuation of downwind zones out to 10 miles and sheltering downwind areas to 15 miles.

"* If GE TEDE or CDE limits are exceeded beyond 10 miles, consider recommending evacuation of downwind areas out to a distance where the GE TEDE or CDE limits are no longer exceeded and sheltering downwind to 5 miles beyond the recommended evacuation area.

"* When making recommendations for evacuation or sheltering areas outside the 10 mile EPZ simply identify the distance and direction to the states without specifying specific areas.

d. PAR CONTINUING ACTIONS

"* Continue to assess conditions such as wind direction shifts, changes in release status, changes in source term, or changes in stability class and upgrade PARs as necessary.

"* PARs should be upgraded within 15 minutes of discovery of the status change that required the upgrade.

"* Changes in PARs should be transmitted verbally to the state and local agencies within 15 minutes of the PAR upgrade.

"* Verbal notification can be done using any convenient communication method.

No specific form is required for the verbal notification. Document the notification times on Figure 6.

"* Follow the initial verbal notification as soon as possible with a follow-up message on Figure 6 that is sent to the states and counties as hardcopy.

Page 9 of 11 Version 49

"12/31/02 9:41:30 FNP-0-EIP-9.0 GUIDELINE 1 GENERAL EMERGENCY RED VERBAL NOTIFICATION FORM

1. rA-[This is a Drill [-]Actual Emergency jInitial

2. Site: Farley Nuclear Plant

3. Confirmation Phone Numbers: (334)899-5156 or (334)794-0800

5. 1 Emergency Classification:

Ext. 4662 or 4663 I j jGeneral Emergency 01 1%

6. Emergency Declaration At: Time/Date _______ / /___

(central) MM DD YY

7. Emergency Classification criteria: [" Gl.l GI.2 0 G2.1 [: G3.1 Failed Barriers: F]RCS O]Containment []Fuel Clad []none OHeat Removal Sys Inadequate 10 Emergency Releases: [A]None

14. Meteorological Data [EWind Direction (from)_

K]Is

[Speed(mph)

Occurring E['AT I

15. Recommended Actions:

Evacuate and control access in down wind zones X] A-2 [:] B-5 [] C-5 W-1 D5 W-IE-5 [IF-5 ]1i-5 r-J-5 W-K-5 Dl Shelter and control access in down wind zones OR -2"Evacuate and control access in down wind zones EWB-1o WiC-10 WD-lo WE-o [IF-IO W]G-1o WH-lO WI-O Wi-io [IK-1o AND In all affected areas: Monitor environmental radiation levels, locate and evacuate hot spots-and implement control and possible confiscation of food and water supplies and consider evacuation of children and pregnant women.

rE1Other

16. Approved By: Emergency Director (Name) (Title)

A. Line I check box A or B.

B. Line 6 fill in the declaration time/date (time that you evaluated the condition in procedure).

C 1. Line 7 check the box(es) for the criteria requiring this emergency classification (only one required).

C2. Check all failed barriers or none, check heat removal inadequate if appropriate.

C3. If more information is required, list it on a separate page, read it over the ENN when line 7 is read.

D. Line 10 if an Emergency Radioactive release is in progress, check box C otherwise check box A.

E. Line 14 enter the current met data (35 foot elevation preferred) from PPC (ERDS) or the BOP F. Line 15 indicated the PARs required for this declaration, by selecting the down wind zones in lines C and DI or D2. Use line E as appropriate. For example list PARs beyond 10 miles.

G. Line 16 the Emergency Director must sign this form.

H. Within 15 minutes of declaration time, using the ENN (instructions on following page), contact the state and local agencies listed below. Enter below the time of the attempted initial ENN contact (transmission time). Enter below the name of the person contacted once obtained. Check the acknowledged box when receipt of message is acknowledged. The table on the next page lists methods of contact.

Alabama Radiation Control (ARC) (Do not use abbreviation over ENN)/

Troopers/Houston Co. Time Name Acknowledged[O GEMA/Early County Time Name AcknowledgedEI If ARC is at the FEOC in Houston County then Houston County is not required to be notified.

Houston County Time Name Acknowledged[]

If GEMA is at the FEOC in Early County then Early County is not required to be notified.

Early County Time Name AcknowledgedEI If AEMA is not on the ENN, they are not required to be notified.

AEMA Time Name AcknowledgedE]

I. Proceed to the following page for the REMAINING NOTIFICATIONS at step J.

Page 10 of I Version V 49

12/31/02 9:41:30 QT1ý.ATRiU FNP-0-EIP-9.0 GUIDELINE 1 GENERAL EMERGENCY RED VERBAL NOTIFICATION FORM ENN INSTRUCTIONS FOR INITIAL NOTIFICATION

1. Pickup handset, Dial CC9907 to open all speakers, DIAL ** on the ENN, wait 10 seconds, press to talk and announce "This Is name/title at Farley Nuclear Plant. Please obtain a GENERAL EMERGENCY RED initial notification form and monitor the ENN."

2. Request a state level agency for Alabama and Georgia, a county level agency for Houston County (not required IF Alabama Radiation Control is at the FEOC) and Early County (not required if GEMA at the FEOC), and AEMA acknowledge manning of the ENN per step H on the previous page. Example "Alabama Radiation Control at Montgomery EOC are you on the line?"

3 Pickup handset, DIAL ** on the ENN, wait 10 seconds, press to talk and announce on the ENN "Please prepare to receive a GENERAL EMERGENCY, RED initial notification message with acknowledgment", then slowly read the GE initial notification form over the ENN.

4. Have the agencies contacted above, acknowledge receipt of the message.

5. Pickup handset, Dial CC9900 to close all speakers opened in step 1.

6. If any required agency could not be contacted on the ENN, then use numbers listed below or in FNP-0-EIP-8.3 to contact them by any available means.

NOTIFICATION MEANS (underlined nmnbers are available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> aa day)

(underlined munbers are available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> day)

ALABAMA State MEANS NOTIFICATION Agencies In preferred order GEORGIA State Agencies In preferred order Alabama Radiation Control at Montgomery EOC GEMA at Atlanta EOC ENN (11), OPX (6628), phone (334-242-4378) ENN (2 1). OPX (6629). Phone (404-635-7200)

FAX (334-264-4396) FAX (404-627-4850)

State Troopers in Montgomery GEMA at Georgia Forward EOC ENN 0(2). phone (334-242-4378.,4379) ENN (22) OPX (6626) phone (229-723-4826)

Alabama Radiation Control at Alabama Forward FAX (8-257-2455)

EOC EARLY COUNTY ENN (13), OPX 662 1), phone (334-793-1565) ENN(42) ENN(41) OPX (6622)FAX(8-257-2455)

FAX (8-257-1535) phone(229-723-3577. 3578, 4826)

HOUSTON COUNTY ENN(3 1) ENN(13), OPX (6621), FLORIDA State Agency FAX(8-257-1535) Florida Department of Emergency Management phone (334-794-9720, 793-9655, 334-677-4807, 4808! phone (800-320-0519) (850-413- 9911)

AEMA COURTESY NOTIFICATION FAX (850-488-7841)

ENN (51) I REMAINING NOTIFICATIONS (continued from previous page)

J. Fax a copy of the previous page GENERAL EMERGENCY RED VERBAL NOTIFICATION FORM to the State of Florida, EOF and EOC using speed dial #10 or an alternative method of contact that is listed in the table above.

K. Verify the state of Florida has received the FAX using the numbers listed in the table above.

L. Complete Figure 6, side 1, follow-up message as soon as possible.

M. Fax Figure 6, side 1, to state and local agencies as soon as possible, but within 30 minutes of the verbal notification per the instructions on Figure 6, side 2.

N. Provide the information on Figure 6, side 1, to the NRC as soon as possible, but within one hour of the declaration per the instructions on Figure 6, side 2.

Page 11 of 11 Version 49

12/31/02 9:41:30 Sn-t xizmu FNP-0-EIP-9.

GUIDELINE 2 GUIDELINE 2 SITE AREA EMERGENCY I. Criteria for Classification The classification of Site Area Emergency applies to those events which are in progress or have occurred involving actual or likely major failures of plant functions needed for protection of the public from radiation or contamination. The potential for release of radioactive material for the Site Area Emergency classification is up to 1000 Ci of 1-131 equivalent, or 104 to 106 Ci of Xe-133 equivalent. The purpose of the declaration of a Site Area Emergency is to:

(a) Assure that response centers are manned, (b) Assure that monitoring teams are dispatched, (c) Assure that personnel involved in an evacuation effort of near site areas are at their duty stations if the situation worsens, and, (d) Provide current information for and consultation with offsite authorities and the public.

(e) A Site Area Emergency would be declared for plant conditions that warrant activation of emergency centers and monitoring teams.

A Site Area Emergency would be declared for any of the following:

1.0 RCS FAULT SI.I A major loss of primary coolant as indicated by:

(a) Decreasing pressurizer pressure and possible level, AND (b) Near normal steam pressure in all steam generators accompanied by, (1) Containment pressure reaching 27 psig, AND (2) High containment radiation (R-2, R-l1, and R- 12 reaching their alarm setpoint), AND (3) High containment sump (recirculation) level AND (4) High containment humidity.

Page I of 11 Version 49

12/31/4

)2 9:41:30 ýsI-ARED FNP-O-EIP-9.0 GUIDELINE 2 GUIDELINE 2 SITE AREA EMERGENCY S1.2 Rupture of a control rod mechanism housing as indicated by the following:

(a) Rod position indication, AND (b) High RCS pressure surge, AND (c) Momentary nuclear power surge, AND (d) Subsequent behavior indicating a loss of primary coolant.

2.0 SG FAULT OR RUPTURE S2.1 A loss of offsite power (an unplanned loss of power to the emergency 4160 volt busses F and G from off site sources that are not part of a pre planned test sequence) (LER #2000-005-00 Unit 1) and a steam generator tube rupture as indicated by.

(a) ECCS actuation, AND (b) High secondary coolant activity (R- 15 or R- 19 reach full scale)

S2.2 Greater than 50 gpm primary to secondary leak, fuel damage as evidenced by a reactor coolant activity greater than Technical Specification 3.4.16 requiring shutdown or Dose Equivalent Iodine greater than T.S. Figure 3.4.16-1 20% limit, and a steam line break outside containment as indicated by:

(a) Abnormally low steam pressure on one or all steam generators with one or more of the following:

(1) Steam line high flow, (2) Steam line high differential pressure, (3) Steam flow greater than feed flow AND (b) No abnormal temperature or humidity increase in containment I Page 2 of 11 Version 49

12/31/(

)2 9:41:30 SHARED

..--- *.GUIDELINE FNP-0-EIP-9.02 GUIDELINE 2 SITE AREA EMERGENCY 3.0 DEGRADED CORE/FUEL FAULT S3.1 RCS activity > 300 tCi/gram dose equivalent 1-131 with potential excessive RCS leakage or potential loss of containment. Figure 8 may be used to help evaluate if Dose Equivalent 1-131 (DEI) is > 300 .tCi/gram.

S3.2 Degraded core conditions with possible loss of core geometry as indicated by:

(a) AT between RCS wide range hot leg and cold leg temperature

> 64 0F and core exit temperature (in core thermocouples) reading greater than 800°F and increasing, OR (b) Core exit temperature (incore thermocouples) > 1200 0F.

Spent fuel handling accident for which sampling or radiation monitors indicate a projected lower limit of offsite individual exposure to be:

S3.3 100 mrem (.1 rem) TEDE OR

$3.4 500 mrem (.5 rem) thyroid CDE As a result of one of the following:

(a) Dropped spent fuel assembly, OR (b) An object is dropped onto a spent fuel assembly, OR (c) A cask containing a spent fuel assembly is dropped exposing the assembly, OR (d) A spent fuel assembly is deformed as a result of any manipulation, OR (e) Spent fuel pool water level below top of assemblies.

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12/31/029:41:30  ! , A - FNP-0-EIP-9.0

.- -GUIDELINE 2 GUIDELINE 2 SITE AREA EMERGENCY 4.0 HIGH EFFLUENT Projected exposure at site boundary or projected peak dose location within the plume for EDCM calculation:

S4.1 Greater than or equal to 100 nirem (.1 rem) TEDE exposure OR S4.2 Greater than or equal to 500 rnrem (.5 rem) thyroid CDE exposure 5.0 EQUIPMENT/STRUCTURE FAILURE

$5.1 Loss of functions for achieving hot standby.

S5.2 Transients requiring operation of shutdown systems with failure to trip (continued power generation but no core damage immediately evident).

6.0 ELECTRICAL/INSTRUMENTATION FAULT S6.1 Loss of offsite power (an unplanned loss of power to the emergency 4160 volt busses F and G from off site sources that are not part of a pre-planned test sequence) (LER #2000-005-00 Unit 1) with a failure of all emergency AC power for more than 15 minutes.

S6.2 Loss of both trains of auxiliary building DC power for more than 15 minutes.

S6.3 Loss of all main control board annunciator capability for more than 15 minutes while:

(a) Plant is not in cold shutdown, OR (b) Significant plant transient is initiated while all alarms lost.

Page 4 of 11 Version 49

12/3,1/02 9:41,:30 H A RED FNP-0-EP-9.0 GUIDELINE 2 GUIDELINE 2 SITE AREA EMERGENCY 7.0 SITE HAZARDS NOTE: A fire affecting ECCS Is one that has directly affected the to ability of both trains of ECCS (high head, low head or accumulators specifically) perform their intended function. This does not Include attendant equipment if alternate means of performing the attendant equipment functions are available.

S7.1 A fire affecting ECCS.

Severe natural phenomena being experienced or projected with plant not in cold shutdown:

S7.2 Earthquake greater than SSE levels S7.3 Flood, low river water, or hurricane surge greater than design levels.

S7.4 Winds in excess of 115 mph.

Other hazards being experienced with the plant not in cold shutdown as follows:

S7.5 Aircraft crash affecting vital structures by fire or impact, OR S7.6 Severe damage to safe shutdown equipment from missiles or explosion, OR S7.7 Entry of toxic or flammable gases into vital areas(s) 8.0 SECURITY/EVACUATION S8.1 Imminent loss of physical control of the plant (i.e., takeover by terrorists, anti-nuclear factions, etc.). If the basis for declaring this emergency classification is based on security concerns, then refer to table 3 prior to taking actions that will cause people to report to the site or change locations on site.

S8.2 Evacuation of the control room and control of shutdown systems not established from local stations in 15 minutes.

Page 5 of 11 Version 49

12/31/02 9:41:30 SHAFRED GUIDELINE 2 FNP-0-EIP-9.0 GUIDELINE 2 SITE AREA EMERGENCY II. Emergency Director Actions NOTE: THE OPERATIONS SHIFT SUPERINTENDENT SHALL PERFORM THE DUTIES OF THE EMERGENCY DIRECTOR UNTIL HIS ARRIVAL AND ASSUMPTION OF DUTIES.

NOTE: ACTIVATION OF THE TSC AND EOF STAFFS, PER STEPS El AND E2, SHOULD BE DONE IN PARALLEL WITH NOTIFICATION OF THE STATE AND LOCAL AGENCIES.

Initials A. If the plant emergency alarm has not already been activated, then announce over the public address system, "All plant personnel report to designated assembly areas", activate the PEA for 30 seconds, then repeat announcement.

B. Announce the condition, request setup of the TSC and EOF, and give needed I evacuation instructions over plant public address system.

C. Fill in the SITE AREA Emergency Initial Notification Form (last two pages of this guideline), including developing protective action recommendations per step L.

Take into account the zones and evacuation time estimates shown in Figure 1.

NOTE: INITIAL NOTIFICATIONS WILL NORMALLY BE MADE BY THE SHIFT CLERK, BUT MAY BE MADE BY OPERATIONS STAFF, TSC STAFF OR OTHER QUALIFIED PERSON USING THE INITIAL NOTIFICATION FORM (LAST TWO PAGES OF THIS GUIDELINE).

NOTE: INITIAL AND UPGRADE CLASSIFICATIONS AND NOTIFICATIONS SHOULD BE DONE FROM THE CONTROL ROOM OR THE TSC, WITH THE EOF INFORMED AS SOON AS POSSIBLE.

D. Initial Notifications

1. Within 15 minutes of declaration verbally notify the state agencies using the Site Area Emergency Initial Notification Form (last two pages of this guideline).

2. Verify notifications complete and documented on the Site Area Emergency Initial Notification Form (last two pages of this guideline).

Page 6 of 11 Version 49

12/31/02 9:41:30 SIHARED GUIDELINE 2 FNP-0-EIP-9.0 GUIDELINE 2 SITE AREA EMERGENCY E. Emergency Organization Notifications NOTE: STEPS El AND E2, NOTIFYING THE TSC AND EOF STAFF WILL NORMALLY BE ACCOMPLISHED BY HAVING THE SHIFT CLERK COORDINATE ACTIVATION OF THE ERO NOTIFICATION SYSTEN PER FNP-0-EIP-8.3, TABLE 2 AND STEP 11).

1. TSC Staff (full activation required initially and then downsize if appropriate per table 2)

2. EOF Staff (full activation required initially and then downsize if appropriate per table 2)

3. On-call Emergency Director

4. On-call Recovery Manager

5. Emergency Support Manager

6. Notify Security of Emergency, incoming personnel, access restrictions and to setup the EOF (pax 4611).

F. Other Notifications

1. NRC (Perform immediately after state notification and within one hour of declaration per Figure 6, side 2.)

2. Have Regulatory ERDS activated to transmit data to the NRC within one hour of the declaration of the emergency (EIP 8.3, step 10).

3. If personnel injury or fire is involved, refer to FNP-0-EIP- 11.0 and 13.0 respectively for additional actions and EIP-8.0 steps 5.0 and 6.0 for additional notifications.

4. U.S. Army EOD group at Fort Benning, GA, if necessary.

5. Savannah River Operations Office, if necessary.

6. If there is a security event involved, ensure appropriate notifications and actions of FNP-0-AOP-49 and FNP-0-SP 37.0 are performed.

Page 7 of 11 Version 49

12/31/02 9:41:30 FNP-0-ELP-9.0 SM-AREDGUIDELINE 2 GUIDELINE 2 SITE AREA EMERGENCY G. In Plant Protective Actions

1. Ensure personnel accountability per EIP-10.0.

2. Plan and initiate reentries per EIP-14.0.

3. Ensure proper Control Room response.

4. Assign an individual to provide periodic plant status updates.

5. Assign an individual to maintain a log of important Emergency Director activities.

6. Assign an individual to keep a record of all off site communications.

7. Determine what should be done with a unit that is not affected by the declared emergency. Consider the effect on the emergency unit, manpower utilization, plant and grid stability and other relevant factors.

H. Off Site Support I. Ensure Radiation Monitoring teams have been dispatched per EIP-4.0.

2. Provide information to the Recovery Manager for use in press releases and recovery planning.

I. Information to Off Site Authorities I. Provide periodic plant status updates, meteorological and dose estimates and release projections based on plant conditions and foreseeable contingencies.

J. Re-Assess plant conditions I. Continue to assess plant and radiological conditions to ensure the correct emergency classification is declared.

2. If a higher emergency classification is required immediately go to the appropriate guideline.

3. If plant and radiological conditions no longer require the current emergency classification downgrade or close out the emergency class using FNP-0-EIP-28.0.

Page 8 of 11 Version 49

12/31/02 9:41:30 ,Li-

• FNP-0-EIP-9.0

- +/-. **-* ' . *--'--* -- GUIDELINE 2 GUIDELINE 2 SITE AREA EMERGENCY K. Long term concerns

1. Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, provide for full TSC and OSC reliefs.

2. Within 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />, provide for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TSC and OSC coverage.

3. If an LOSP has occurred evaluate the event to ensure that an adequate supply of fuel oil is available for the Diesel Generators for 7 days. Refer to REA 00-2337 and FNP-0-SOP-42.0 Figure 1.

L. Protective action recommendation guidance NOTE Only the technically based protective actions specified below should be recommended unless there are obvious relevant factors (e.g., severe natural phenomena) that probably were not anticipated when the PARs were developed, and that would make the standard PAR recommendations Impractical or obviously non-conservative. In such events, the emergency director should use his own judgment as appropriate.

a. Protective Action Recommendations are not required; however, they may (at the discretion of the Emergency Director) be made as a precautionary measure, depending on the severity of the plant condition or if the site boundary dose is approaching the General Emergency limit. Refer to the note above.

b. If it is determined that PARs are required, then use the guidance of Guideline 1, Section L when making the recommendations

c. Continue to assess plant and radiological conditions such as wind direction shifts, changes in release status, changes in source term, or changes in stability class and upgrade PARs as necessary. PARs should be upgraded within 15 minutes of discovery of the status change that required the upgrade. Changes in PARs should be transmitted verbally to the state and local agencies within 15 minutes of the PAR upgrade. Verbal notification can be done using any convenient communication method, no specific form is required. Follow the initial verbal notification as soon as possible with a follow-up message on Figure 6 that is sent to the states and counties as hardcopy.

Page 9 of 11 Version 49

12/31/02 9:41:30 SZH}f RED FNP-0-EIP-9.0 GUIDELINE 2 SITE AREA EMERGENCY ORANGE VERBAL NOTIFICATION FORM

1. j-]This is a Drill 'F]Actual Emergency XInitial

2. Site: Farley Nuclear Plant

3. Confirmation Phone Numbers: (334)899-5156 or (334)794-0800 Ext. 4662 or 4663

5. 1 Emergency Classification:

WSite Area Emergency 6.XEmergency Declaration At: Time/Date D /

(central) MM DD YY

7. Emergency Classification criteria: [3 SL.1 OS51.2 El 52.1 [I S2.2 [I S3.1 $3.2 Sl

["S3.3 0I'3.4 " S4.1 El S4.2 [I S5.1 [I S5.2 [I S6.1 [I S6.2 [: S6.3

[o S7.1 [I S7.2 05$7.3 0I"7.4 0-1S7.5 05$7.6 -S7.7 [I S8.1 [I S8.2 Failed Barriers: QIRCS [Orntainment []Fuel Clad []none []Heat Removal Sys Inadequate 10 Emergency Releases: AA.None [I]is occurring

14. Meteorological Data [A ind Direction (from) [Speed(mph) _ EAT 15 Recommended Actions:

[]mThere are no recommended protective actions.

FC] Evacuate and control access in down wind zones E] A-2

• B-5 '- C-5 [] D5 FW]E-5 WJF-5 W-I-5 WIJ-5 WIK-5 Dl Shelter and control access in down wind zones OR D2 Evacuate and control access in down wind zones W]B-10 D]C-10. -]D-10 W]E-10 [F-10 W]G-10 [WH-10 [-]I-10 []J-10 -- K-10 AND In all affected areas: Monitor environmental radiation levels, located and evacuate hot spots and implement control and possible confiscation of food and water supplies and consider evacuation of children and pregnant women.

[FE]other

16. Approved By: Emergency Director (Name) (Title)

A. Line l check box A or B.

B. Line 6 fill in the declaration time/date (time that you evaluated the condition in procedure).

Cl._Line 7 check the box(es) for the criteria requiring this emergency classification (only one required).

C2. Check all failed barriers or none, check heat removal inadequate if appropriate.

C3. _If more information is required, list it on a separate page, read it over the ENN when line 7 is read.

D. Line 10 if an Emergency Radioactive release is in progress, check box C otherwise check box A.

E. Line 14-enter the current met data (35 foot elevation preferred) from PPC (ERDS) or the BOP.

F. Line 15 indicated the PARs required for this declaration, (normally 15A, none for SAE). If PARs are required, indicate by selecting the down wind zones in lines C and DI or D2. Use line E if necessary.

G. Line 16, the Emergency Director must sign this form.

H.____Within 15 minutes of declaration time, using the ENN (instructions on following page), contact the state agencies listed below. Enter below the time of the attempted initial ENN contact (transmission time). Enter below the name of the person contacted once obtained. Check the acknowledged box when receipt of message is acknowledged. The table on the next page lists methods of contact.

Alabama Radiation Control!

Troopers/Houston Co. Time Name Acknowledged[']

GEMA/Early County Time Name AcknowledgedEl If AEMA is not on the ENN, they are not required to be notified.

AEMA Time Name Acknowledged[I I. Proceed to the following page for the REMAINING NOTIFICATIONS at step J.

Page 10 of Version s 49 4

12/31/02 9:41:30 HIARED GUIDELINE 2 FNP-0-EIP-9.0 SITE AREA EMERGENCY ORANGE VERBAL NOTIFICATION FORM ENN INSTRUCTIONS FOR INITIAL NOTIFICATION

1. Pickup handset, dial CC9907 to open all speakers, DIAL ** on the ENN, wait 10 seconds, press to talk and announce "This Is namettitle at Farley Nuclear Plant. Please obtain an SITE AREA EMERGENCY, ORANGE Initial notification form and monitor the ENN."

2. Request a state level agency for Alabama and Georgia and the AEMA acknowledge manning of the ENN per step H on the previous page. Example "Alabama Radiation Control at Montgomery EOC are you on the line?"

3 Pickup handset, DIAL ** on the ENN, wait 10 seconds, press to talk and announce on the ENN "Please prepare to receive a SITE AREA EMERGENCY, ORANGE initial notification message with acknowledgment", then slowly read the SAE initial notification form over the ENN.

4. Have the agencies contacted above, acknowledge receipt of the message.

5. Pickup handset, dial CC9900 to close all speakers opened in step 1.

6. If any required agency could not be contacted on the ENN, then use numbers listed below or in FNP-0-EIP-8.3 to contact them by any available means.

NOTIFICATION MEANS (underlined numbers are available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day)

ALABAMA State Agencies In preferred order GEORGIA State Agencies In preferred order Alabama Radiation Control at Montgomery EOC GEMA at Atlanta EOC ENN (11), OPX (6628), phone (334-242-4378) ENN (21). OPX (b629). Phone (404-635-7200)

FAX (334-264-4396) FAX (404-627-4850)

State Troopers in Montgomery GEMA at Georgia Forward EOC ENN (12). phone (334-242-4378.4379) ENN (22) OPX (6626) phone (229-723-4826)

Alabama Radiation Control at Alabama Forward FAX (8-257-2455)

EOC EARLY COUNTY ENN (13), OPX 6621), phone (334-793-1565) ENN(42) ENN(41) OPX (6622)FAX(8-257-2455)

FAX (8-257-1535) phone(229-723-3577. 3578, 4826)

HOUSTON COUNTY ENN 31). ENN(13), OPX (6621), FLORIDA State Agency FAX(8-257-1535) Florida Department of Emergency Management phone (334-794-9720, 793-9655, 334-677-4807,48081 phone (800-320-0519) (850-413- 9911)

AEMA COURTESY NOTIFICATION FAX (850-488-7841)

ENN (51)

REMAINING NOTIFICATIONS (continued from previous page) 3 _Fax a copy of the previous page SITE AREA EMERGENCY, ORANGE VERBAL NOTIFICATION FORM to the State of Florida, EOF and EOC using speed dial #10 or an alternative method of contact that is listed in the table above.

K Verify the State of Florida has received the FAX using the numbers listed in the table above.

L Complete Figure 6, side 1, follow-up message as soon as possible.

M Fax Figure 6, side 1, to state and local agencies as soon as possible, but within 30 minutes of the verbal notification per the instructions on Figure 6, side 2.

N Provide the information on Figure 6, side I to the NRC as soon as possible but within one hour of the declaration per the instructions on Figure 6, side 2.

Page 11 of 11 Version 49

12/31/029:41:30 ' /I:DG DEN FNP-0-EIP-9.03 S) I -I iAl- LE f GUIDELINE 3 GUIDELINE 3 ALERT I. Criteria for Classification The classification of Alert applies to situations in which events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. The potential for release of radioactive material for the Alert classification is up to 10 curies of 1-131 equivalent, or up to 104 curies of Xe-133 equivalent. The purpose of offsite alert is to assure that emergency personnel are readily available to respond if the situation becomes more serious or to perform confirmatory radiation monitoring, if required, and to provide offsite authorities current status information for possible further action.

(a) An Alert would be declared for plant conditions that warrant precautionary activation of the technical support center, operations support centers, and the emergency operations facility (at the discretion of the Recovery Manager).

An Alert would be declared for any of the following:

1.0 RCS FAULT AU.I A primary coolant leak greater than 50 gpm. Indications of such a leak will include high charging flow AND (a) High containment radiation (R 2, R 22, and R 12) AND (b) High containment humidity OR (c) Pressurizer relief or safety valve discharge line temperature high AND (d) Pressurizer relief tank level, pressure or temperature increasing or above normal.

A1.2 Single rod cluster control assembly withdrawal at power as detected by:

(a) Rod position indicator, AND (b) Increasing core power, AND (c) Increasing Tavg.

Page I of 11 Version 49

12/31/029:41:30 FNP-0-EIP-9.0 D

SGUIDELINE 3 GUIDELINE 3 ALERT 2.0 SG FAULT OR RUPTURE A2.1 Steam generator tube rupture indicated by, (a) ECCS actuation, AND (b) High secondary coolant activity (R-15, R-19, R-23A, or R-23B reach full scale).

A2.2 Greater than 10 gpm primary to secondary leak as indicated by high secondary coolant activity (R-15, R-19, R-23A, or R-23B alarming)

WITH a steam line break outside containment indicated by:

(a) Abnormally low steam pressure on one or all steam generators with one or more of the following:

(1) Steam line high flow, OR (2) Steam line high differential pressure, OR (3) Steam flow greater than feedwater flow AND (b) No abnormal temperature, or humidity increase in containment.

A2.3 A steam or feed line break inside containment as indicated by abnormally low pressure on one steam generator with the following:

(a) Steam line high differential pressure, OR (b) Steam flow greater than feed flow, OR (c) Steam line high flow, AND (d) Containment high temperature Page 2 of 11 Version 49

12/31/02 9:41:30 FNP-0-EIP-9.0 123ii/29130*** GUIDELINE 3 GUIDELINE 3 ALERT 3.0 DEGRADED CORE/FUEL FAULT A3.1 Severe loss of fuel cladding as indicated by a reactor coolant activity equal to or greater than 300 ItCi/gram equivalent 1-131. Figure 8 may be used to help evaluate if Dose Equivalent 1-131 (DEI) is > 300 jJCi/gram.

A3.2 Spent fuel handling accident in which an increase in radiation level (i.e.,

alarm condition or off scale reading) is observed on R-2, R-l 1, R-12, R-5, OR R-25 as a result of one of the following:

(a) Dropped spent fuel assembly, OR (b) An object is dropped onto a spent fuel assembly, .R (c) A cask containing a spent fuel assembly is dropped, OR (d) A spent fuel assembly is deformed as a result of any manipulation, OR (e) Low spent fuel pool water level.

4.0 HIGH EFFLUENT Radiological effluent at the site boundary (combined effect from both units) greater than 10 times the radiological technical specification instantaneous limits (based on ODCM) as follows, per EIP-9.5:

A4.1 Liquids: 10 times 10CFR20 Appendix B, Table 2, Column 2 A4.2 Liquids: Dissolved or entrained noble gases: 0.001 mCi/ml A4.3 Noble gases (whole body) 5.7E-4 Rem/hr (5.7E- Imrem/hr)

A4.4 Noble gases (skin): 3.4E-3 Rem/hr (3.4 mrem/hr)

A4.5 Airborne radioiodine and particulates other than noble gases:

1.7E-3 Rern/hr.(1.7 mrem/hr)

Page 3 of 11 Version 49

12/31/02 9:41:30 FNP-0-EIP-9.0 GUIDELINE 3 GUIDELINE 3 ALERT A4.6 High radiation levels or high airborne contamination indicative of a severe degradation in the control of radioactive materials as indicated by:

(a) Readings on R-14 (stack gas monitor), R-21 (stack particulate monitor) QR R-22 (stack gas monitor) reading off scale, AND (b) Sampling or R-27 high range containment monitor confirms direct readings.

5.0 EQUIPMENT/STRUCTURE FAILURE A5.1 Loss of all auxiliary feedwater (Modes 1-3), OR A5.2 Loss of both trains of RHR (All modes), OR A5.3 Loss of both trains of CCW (Modes 1-4), OR A5.4 Loss of both trains of Service Water (Modes 1-4)

A5.5 Failure of the reactor protection system to initiate and complete a trip which brings the reactor subcritical.

6.0 ELECTRICAL/INSTRUMENTATION FAULT A6.1 Loss of offsite power (an unplanned loss of power to the emergency 4160 volt busses F and G from off site sources that are not part of a pre-planned test sequence) (LER #2000-005-00 Unit 1) with a failure of all emergency AC power for less than 15 minutes.

A6.2 Loss of both trains of auxiliary building DC power for less than 15 minutes.

A6.3 Loss of all main control board annunciator capability.

Page 4 of 11 Version 49

12/31/02 9:41:30 FNP-0-EIP-9.0 GIADED GUIDELINE 3 GUIDELINE 3 ALERT 7.0 SITE HAZARDS Severe natural phenomena being experienced or projected as follows:

A7.1 Earthquake greater than OBE levels. (ARP-I.12 LOC MK5)

A7.2 Flood, low river water or hurricane surge near design levels that could impact plant operations.

A7.3 Any tornado striking facility A7.4 Hurricane winds near design basis level (115 mph)

Hazards experienced onsite which affect plant operation such as:

A7.5 Aircraft crash A7.6 Release of toxic gas A7.7 Release of flammable gas NOTE: A fire or explosion potentially affecting ECCS is one that has directly affected the ability of one train of ECCS (high head, low head or accumulators specifically) to perform its intended function. This does not include attendant equipment if alternate means of performing the attendant equipment functions are available.

A7.8 Fire or explosion potentially affecting ECCS 8.0 SECURITY/EVACUATION A8.1 A security emergency involving the occurrence or credible imminent threat of sabotage. If the basis for declaring this emergency classification is based on security concerns, then refer to Table 3 prior to taking actions that will cause people to report to the site or change locations on site.

A8.2 Evacuation of control room anticipated or required with control of shutdown systems established from local stations.

Page 5 of 11 Version 49

12/31/02 9:41:30 HA'RE D T

GUIDELINE 3 FNP-0-EIP-9.0 GUIDELINE 3 ALERT H. Emergency Director Actions NOTE: THE OPERATIONS SHIFT SUPERINTENDENT SHALL PERFORM THE DUTIES OF THE EMERGENCY DIRECTOR UNTIL HIS ARRIVAL AND ASSUMPTION OF DUTIES.

NOTE: ACTIVATION OF THE TSC AND EOF STAFFS, PER STEPS El AND E2, SHOULD BE DONE IN PARALLEL WITH NOTIFICATION OF THE STATE AND LOCAL AGENCIES.

A. Announce the condition, request setup of the TSC and EOF, and give needed evacuation instructions over plant public address system.

I B. Evacuate affected areas of the plant as appropriate.

C. Fill in the ALERT Initial Notification Form (last two pages of this guideline).

NOTE: INITIAL NOTIFICATIONS WILL NORMALLY BE MADE BY THE SHIFT CLERK, BUT MAY BE MADE BY OPERATIONS STAFF, TSC STAFF OR OTHER QUALIFIED PERSON USING THE INITIAL NOTIFICATION FORM (LAST TWO PAGES OF THIS GUIDELINE).

NOTE: INITIAL AND UPGRADE CLASSIFICATIONS AND NOTIFICATIONS SHOULD BE DONE FROM THE CONTROL ROOM OR THE TSC, WITH THE EOF INFORMED AS SOON AS POSSIBLE.

D. Initial Notifications

1. Within 15 minutes of declaration, verbally notify the state and local agencies using the Alert Initial Notification Form (last two pages of this guideline).

2. Verify notifications complete and documented on the Alert Initial Notification Form (last two pages of this guideline).

Page 6 of 11 Version 49

12/31/02 9:41:30 FNP-0-EIP-9.0 GUIDELINE 3 GUIDELINE 3 ALERT IF an ALERT was declared due to radiological effluents greater than or equal to ALERT limits which are 10 times Technical Specification limits, THEN enter the following information on the Emergency Notification form (Figure 6, line 7) when making the initial hardcopy notification of the Alert:

a. ODCM site boundary dose rates from EIP-9.5.

and

b. The following note:

"Dose rate at site boundary has been calculated using the ODCM as required by the FNP Technical Specification.

EDCM calculation is not appropriate."

E. Emergency Organization Notifications NOTE: STEPS E.1 AND E.2, NOTIFYING THE TSC AND EOF STAFF WILL NORMALLY BE ACCOMPLISHED BY HAVING THE SHIFT CLERK COORDINATE ACTIVATION OF ERO NOTIFICATION SYSTEM PER I FNP-0-EIP-8.3, TABLE 2 AND STEP 11.

1. TSC Staff (full activation required initially and then downsize if appropriate per table 2)

2. EOF Staff (full staffing required initially and then activate the EOF or downsize staff as appropriate per table 2)

3. On-call Emergency Director

4. On-call Recovery Manager

5. Emergency Support Manager

6. Notify Security of Emergency, incoming personnel, access restrictions and to setup the EOF (PAX 4611)

Page 7 of 11 Version 49

12/31/02 9:41:30 FNP-0-EIP-9.0 GUIDELINE 3 GUIDELINE 3 ALERT F. Other Notifications

1. NRC (Perform immediately after state notification and within one hour of declaration per Figure 6, side 2)

2. Have Regulatory ERDS activated to transmit data to the NRC within one hour of the declaration of the emergency (EIP-8.3, step 10)

3. If personnel injury or fire is involved, refer to FNP-0-EIP- 11.0 and 13.0 respectively for additional actions and EIP-8.0 steps 5.0 and 6.0 for additional notifications

4. U.S. Army EOD group at Fort Benning, GA, if necessary

5. Savannah River Operations Office, if necessary

6. If there is a security event involved, ensure appropriate notifications and actions of FNP-0-AOP-49 and FNP-0-SP 37.0 are performed G. In Plant Protective Actions S1. Ensure personnel accountability per EIP-10.0, if any areas of the plant were evacuated due to hazardous conditions

2. Plan and initiate re-entries per EIP-14.0, if any areas of the plant were evacuated due to hazardous conditions

3. Ensure proper Control Room response

4. Assign an individual to provide periodic plant status updates

5. Assign an individual to maintain a log of important Emergency Director activities

6. Assign an individual to keep a record of all off site communications

7. Determine-what should be done with a unit that is not affected by the declared emergency. Consider the effect on the emergency unit, manpower utilization, plant and grid stability, and other relevant factors.

Page 8 of 11 Version 49

12/31/02 9:41:30 C I , -FNP-O-EIP-9.O L~iE~l~__GUIDELINE 3 GUIDELINE 3 ALERT H. Off Site Support

1. Ensure Radiation Monitoring teams have been dispatched per EIP 4.0.

2. Provide information to the Recovery Manager for use in press releases and recovery planning I. Information to Off Site Authorities

1. Provide periodic plant status updates, meteorological and dose estimates and release projections based on plant conditions and foreseeable contingencies.

J. Re-Assess plant conditions I. Continue to assess plant and radiological conditions to ensure the correct emergency classification is declared.

2. If a higher emergency classification is required immediately go to the appropriate guideline

3. If plant and radiological conditions no longer require the current emergency classification downgrade or close out the emergency class using FNP-0-EIP-28.0.

K. Long term concerns S1. Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, provide for full TSC and OSC reliefs

2. Within 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />, provide for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TSC and OSC coverage

3. If an LOSP has occurred evaluate the event to ensure that an adequate supply of fuel oil is available for the Diesel Generators for 7 days. Refer to REA 00-2337 and FNP-0-SOP-42.0 Figure 1.

L. Protective action recommendation guidance

1. Protective Action Recommendations are not required. Block A of line 15 on the notification form should be checked.

Page 9 of 11 Version 49

12/31/02 9:41:30 r~l Ja}~ jf tNP--EI9F GUIDELINE 3 ALERT YELLOW VERBAL NOTIFICATION FORM

1. ']mThis is a Drill [B]Actual Emergency

• Initial

2. Site: Farley Nuclear Plant 3.. Confirmation Phone Numbers: (334)899-5156 or (334)794-0800 Ext. 4662 or 4663

5. 1 Emergency Classification: Alert

6. X Emergency Declaration At: Time/Date _ - /

(centml) MM DD YY

7. Emergency Classification criteria: [] Al.I [] AI.2 E] A2.1 [I A2.2 [I A2.3 [I A3.1

[O A3.2 0 A4.1 [I A4.2 [I A4.3 [I A4.4 [I A4.5 [I A4.6 [I A5.1 [I A5.2 0 A5.3 ["1A5.4 [IA5.5 -0A6.1 0 A6.2 []A6.3 -A7.1 0-A7.2 E]A7.3

[IA7.4 [0A7.5 0 A7.6 [IA7.7 []A7.8 [IA8.1 0A8.2 Failed Barriers: E"RCS []Containment []Fuel Clad []none OHeat Removal Sys Inadequate 10 Emergency Releases: --]None Is Ocrring

14. Meteorological Data A[.Wind Direction (from) [ESpeed(mph) E[]AT

15. Recommended Actions:

XThere are no recommended protective actions.

16. Approved By: Emergency Director (Name) (Title)

A. Line I check box A or B.

B. Line 6 fill in the declaration time/date (time that you evaluated the condition in procedure).

C 1. Line 7 check the box(es) for the criteria requiring this emergency classification (only one required).

C2. Check all failed barriers or none; check heat removal inadequate if appropriate.

C3. If more information is required, list it on a separate page; read it over the ENN when line 7 is read.

D. Line 10 if an Emergency Radioactive release is in progress check box C otherwise check box A E. Line 14-enter the current met data (35 foot elevation preferred) from PPC (ERDS) or the BOP.

F. Line 16, the Emergency Director must sign this form.

G. Within 15 minutes of declaration time, using the ENN (instructions on following page), contact the state agencies listed below. Enter below the time of the attempted initial ENN contact (transmission time). Enter below the name of the person contacted once obtained. Check the acknowledged box when receipt of message is acknowledged. The table on the next page lists methods of contact.

Alabama Radiation Control/

Troopers/Houston Co. Time Name Acknowledged[]

GEMA/Early County Time Name Acknowledged[:]

If AEMA is not on the ENN, they are not required to be notified.

AEMA Time Name Acknowledged' H. Proceed to the following page for the REMAINING NOTIFICATIONS at step I.

Page 10 of I Version 49

12/31/02 9:41:30 SHARED GUIDELINE 3 FNP-0-EIP-9.0 ALERT YELLOW VERBAL NOTIFICATION FORM ENN INSTRUCTIONS FOR INITIAL NOTIFICATION

1. Pickup handset, dial CC9907 to open all speakers, DIAL ** on the ENN, wait 10 seconds, press to talk and announce "This is name/title at Farley Nuclear Plant. Please obtain an ALERT, YELLOW initial notification form and monitor the ENN."

2. Request a state level agency for Alabama and Georgia and the AEMA acknowledge manning of the ENN per step G on the previous page. Example "Alabama Radiation Control at Montgomery EOC are you on the line?"

3 Pickup handset, DIAL ** on the ENN, wait 10 seconds, press to talk and announce on the ENN "Please prepare to receive an ALERT, YELLOW initial notification message with acknowledgment", then slowly read the ALERT initial notification form over the ENN.

4. Have the agencies contacted above, acknowledge receipt of the message.

5. Pickup handset, Dial CC9900 to close all speakers opened in step 1.

6. If any required agency could not be contacted on the ENN, then use numbers listed below or in FNP-0-EIP-8.3 to contact them by any available means.

NOTIFICATION MEANS (underlined numbers are available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day)

-- v i ALABAMA State Agencies in preferred order GEORGIA State Agencies in preferred order Alabama Radiation Control at Montgomery EOC GEMA at Atlanta EOC ENN (11), OPX (6628), phone (334-242-4378) ENN (2 1) PX (6629). Phone (404-635-7200)

FAX (334-264-4396) FAX (404-627-4850)

State Troopers In Montgomery GEMA at Georgia Forward EOC ENN(12) phone (334-242-4378.4379) ENN (22) OPX (6626) phone (229-723-4826)

Alabama Radiation Control at Alabama Forward FAX (8-257-2455)

EOC EARLY COUNTY ENN (13), OPX 6621), phone (334-793-1565) ENN(42) ENN(4 !) OPX (6622)FAX(8-257-2455)

FAX (8-257-1535) phone(229-723-3577. 3578,4826)

HOUSTON COUNTY ENN 13)IL ENN(13), OPX (6621), FLORIDA State Agency FAX(8-257-1535) Florida Department of Emergency Management phone (334-794-9720, 793-9655,334-677-4807,4808) phone (800-320-0519) (850-413- 9911)

AEMA COURTESY NOTIFICATION FAX (850-488-7841)

ENN (5 1 REMAINING NOTIFICATIONS (continued from previous page)

I Fax a copy of the previous page ALERT YELLOW VERBAL NOTIFICATION FORM to the State of Florida, EOF, and EOC using speed dial #10 or an alternative method of contact that is listed in the table above.

J Verify the State of Florida has received the FAX using the numbers listed in the table above.

K Complete Figure 6, side 1, follow-up message as soon as possible.

L Fax Figure 6 side 1, to state and local agencies as soon as possible, but within 30 minutes of the verbal notification per the instructions on Figure 6, side 2.

M._ Provide the information on Figure 6, side 1, to the NRC as soon as possible, but within one hour of the declaration per the instructions on Figure 6, side 2.

Page 11 of 11 Version 49

12/31/02 9:41:30 I A Ir12?T* FNP-0-EIP-9.0 S3&. i L..R J.#DGUIDELINE 4 GUIDELINE 4 NOUE

1. Criteria for Classification The classification of Notification of Unusual Event applies to situations in which events are in process or have occurred which could indicate a potential degradation of the level of safety of the plant. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occur.

(a) A NOTIFICATION OF UNUSUAL EVENT would be required for any plant condition that warrants increased awareness on the part of state and/or local offsite authorities or involve other than normal plant shutdown.

A Notification of Unusual Event would be declared for any of the following:

1.0 RCS FAULT N1.1 Failure of a pressurizer safety valve to close.

N1.2 Failure of the pressurizer power operated relief valve and its remote motor operated isolation valve to close.

N1.3 Initiation of safety injection either automatically or manually as a result of plant parameters approaching or reaching their setpoint.

N1.4 Complete loss of forced RCS flow as indicated by RCS flow indicators on all three RCS loops.

2.0 SG FAULT OR RUPTURE N2.1 Failure of any steam generator safety valve to close N2.2 Failure of any steam generator power operated relief valve to close N2.3 Loss of secondary coolant outside containment concurrent with ECCS activation Page 1 of 10 Version 49

12/31/02 9:41:30 T 1 FNP-0-EIP-9.0

.l, 41,1,\.,L..* GUIDELINE 4 GUIDELINE 4 NOUE 3.0 DEGRADED CORE/FUEL FAULT N3.1 Indicated subcooling (margin to saturation) decreased below 10F.

N3.2 Inadvertent loading of a fuel assembly into an improper position which causes Fq to be greater than the Technical Specification limit.

N3.3 RCS activity exceeds Tech. Spec. 3.4.16 limit that requires shutdown or Dose Equivalent Iodine greater than T.S. Figure 3.4.16-1 20% limit.

4.0 HIGH EFFLUENT Radiological effluents at the site boundary (combined effluent from both units) in excess of the radiological technical specifications instantaneous limits (based on ODCM) as follows:

N4.1 Liquids 10CFR20 Appendix B, Table 2 Column 2 N4.2 Liquids: Dissolved or entrained noble gases 1.0 E-4 I.tCi/ml N4.3 Noble gases (whole body) 5.7E-5 Rem/hr (5.7E-2 mrem/hr)

N4.4 Noble gases (skin) 3.4E-4 Rem/hr (3.4E-1 mrem/hr)

N4.5 Airborne radioiodine and particulates other than noble gases:

1.7E-4 Rem/hr (1.7E-I mrem/hr) 5.0 EQUIPMENT/STRUCTURE FAILURE N5.1 Loss of containment integrity requiring shutdown to HOT SHUTDOWN.

6.0 ELECTRICAL/INSTRUMENTATION FAULT N6.1 Loss of both trains of offsite power (an unplanned loss of power to the emergency 4160 volt busses F and G from off site sources that are not part of a pre-planned test sequence) (LER #2000-005-00 Unit 1) OR loss of all onsite emergency power (diesel generators and auxiliaries).

N6.2 Loss of control room indication or annunciation to an extent requiring shutdown.

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12/31/02 9:41:30 S HAREDGUIDELINE 4 FNP-0-EIP-9.0 GUIDELINE 4 NOUE 7.0 SITE HAZARDS Natural phenomena being experienced or projected to affect the plant site as follows:

N7.1 Any earthquake.

N7.2 Unusual river water level caused by flood, low water or hurricane surge.

N7.3 Any tornado onsite.

N7.4 Any threatening hurricane.

Hazards experienced onsite or within one mile of the site boundary which could affect plant operations, such as:

N7.5 Aircraft crash.

N7.6 Explosion.

NOTE: Any fire or explosion affecting the following two types of systems, such that the train or system cannot perform its Intended function or be used to maintain safe shutdown, would be used to declare a NOUE per N7.7 or N7.8:

1. A safety related system other than ECCS (i.e. safety related system excluding high head, low head or accumulators).

2. A non-safety related nuclear process system (e.g. BTRS, GFFD, etc).

ula rcs N7.7ll Fieafcigasft rltdo o-aey eae N7.7 Fire affecting a safety related or a non-safety related nuclear process system.

N7.8 Fire or explosion affecting safe shutdown capability.

N7.9 Release of toxic gas.

N7.10 Release of.flammable gas.

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FNP-0-EIP-9.0 12/31/02 9:41:30 SHTARED GUIDELINE 4 GUIDELINE 4 NOUE 8.0 SECURITY/EVACUATION N8.1 Attempted unauthorized entry into a vital area, attempted sabotage of vital equipment or a plant specific credible threat notification. If the basis for declaring this emergency classification is based on security concerns, then refer to table 3 prior to taking actions that will cause people to report to the site or change locations on site.

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12/31/02 9:41:30 r FNP-0-EIP-9.0 Ff _I-1),GUIDELINE 4 GUIDELINE 4 NOUE

11. Emergency Director Actions NOTE: THE OPERATIONS SHIFT SUPERINTENDENT SHALL PERFORM THE DUTIES OF THE EMERGENCY DIRECTOR UNTIL HIS ARRIVAL AND ASSUMPTION OF DUTIES.

Initials A. Announce the condition and give needed evacuation instructions over plant public address system.

B. Evacuate affected areas of the plant as appropriate.

C. Fill in the NOUE Initial Notification Form (last two pages of this guideline).

NOTE: INITIAL NOTIFICATIONS WILL NORMALLY BE MADE BY THE SHIFT CLERK, BUT MAY BE MADE BY OPERATIONS STAFF, TSC STAFF OR OTHER QUALIFIED PERSON USING THE INITIAL NOTIFICATION FORM (LAST TWO PAGES OF THIS GUIDELINE).

NOTE: INITIAL AND UPGRADE CLASSIFICATIONS AND NOTIFICATIONS SHOULD BE DONE FROM THE CONTROL ROOM OR THE TSC, WITH THE EOF INFORMED AS SOON AS POSSIBLE.

D. Initial Notifications

1. Within 15 minutes of declaration, verbally notify the state and local agencies using the NOUE Initial Notification Form (last two pages of this guideline).

2. Verify notifications complete and documented on the NOUE Initial Notification Form (last two pages of this guideline).

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12/31/02 9:41:30 SH1,A R IF-D GUIDELINE 4 FNP-0-EIP-9.0 GUIDELINE 4 NOUE

1. IF an NOUE was declared due to radiological effluents greater than or equal to NOUE limits which are Technical Specification limits, THEN enter the following information on the Emergency Notification form (Figure 6, line 7) when making the initial hardcopy notification of the NOUE:

a. ODCM site boundary dose rates from EIP-9.5.

and

b. The following note:

"Dose rate at site boundary has been calculated using the ODCM as required by the FNP Technical Specification.

EDCM calculation is not appropriate."

E. Emergency Organization Notifications NOTE: TABLE 2 PROVIDES GUIDANCE AS TO THE REQUIRED LEVEL OF ACTIVATION OF THE TSC AND EOF. LEVEL OF ACTIVATION, IF ANY, IS AT THE DISCRETION OF THE EDIRM. SEE EIP-6/27 FOR GUIDANCE.

THE COMPLETE EOF AND TSC STAFF CAN BE CALLED OUT USING THE ERO CALLOUT SYSTEM PER FNP-0-EIP-8.3, TABLE 2 AND STEP 11 IF DESIRED.

1. TSC Staff, if activated by the ED

2. EOF Staff, if activated by the RM

3. On-call Emergency Director

4. On-call Recovery Manager

5. Emergency Support Manager

6. Notify Security of Emergency, incoming personnel and access restrictions (PAX 4611).

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12/31/02 9:41:30 FNP-0-EIP-9.0

• Y *LI\ - *L.* -*GUIDELINE 4 GUIDELINE 4 NOUE F. Other Notifications

1. NRC (Perform immediately after state notification and within one hour of declaration per Figure 6, side 2).

2. If personnel injury or fire is involved, refer to FNP-0-EIP- 11.0 and 13.0 respectively for additional notifications.

3. U.S. Army EOD group at Fort Benning, GA, if necessary

4. Savannah River Operations Office, if necessary

5. If there is a security event involved, ensure appropriate notifications and actions of FNP-0-AOP-49 and FNP-0-SP 37.0 are performed.

G. In Plant Protective Actions

1. Ensure personnel accountability per EIP-10.0, if any areas of the plant were evacuated due to hazardous conditions.

2. Plan and initiate re entries per EIP-14.0, if any areas of the plant were evacuated due to hazardous conditions.

3. Ensure proper Control Room response.

4. Assign an individual to provide periodic plant status updates.

5. Assign an individual to maintain a log of important Emergency Director activities.

6. Assign an individual to keep a record of all off site communications.

7. Determine what should be done with a unit that is not affected by the declared emergency. Consider the effect on the emergency unit, manpower utilization, plant and grid stability, and other relevant factors.

H. Off- Site Support S1. Ensure Radiation Monitoring teams have been dispatched per EIP-4.0.

2. Provide information to the Recovery Manager for use in press releases and recovery planning.

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12/31/02 9:41:30 SHARELD GUIDELINE 4 FNP-0-EIP-9.0 GUIDELINE 4 NOUE I. Information to Off-Site Authorities

1. Provide periodic plant status updates, meteorological and dose estimates and release projections based on plant conditions and foreseeable contingencies.

J. Re-Assess plant conditions

1. Continue to assess plant and radiological conditions to ensure the correct emergency classification is declared.

2. If a higher emergency classification is required immediately go to the appropriate guideline.

3. If plant and radiological conditions no longer require the current emergency classification downgrade or close out the emergency class using FNP-0-EIP-28.0.

K. Long term concerns I

I. Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, provide for full TSC and OSC reliefs.

2. Within 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />, provide for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TSC and OSC coverage.

3. If an LOSP has occurred evaluate the event to ensure that an adequate supply of fuel oil is available for the Diesel Generators for 7 days. Refer to REA 00-2337 and FNP-0-SOP-42.0 Figure 1.

L. Protective action recommendation guidance

1. Protective Action Recommendations are not required. Block A of Line 15 on the notification form should be checked.

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12/31/02 9:41:30 SHARED GUIDELINE 4 FNP-0-EIP-9.0 NOTIFICATION OF UNUSUAL EVENT BLUE VERBAL NOTIFICATION FORM

1. I-]This is a Drill j-]Actual Emergency A Initial

2. Site: Farley Nuclear Plant

3. Confirmation Phone Numbers: (334)899-5156 or (334)794-0800 Ext. 4662 or 4663 I

5. EEergency Classification:

MNotification Of Unusual Event

6. )Q Emergency Declaration At: Time/Date /

tvccnum)

7. Emergency Classification criteria: r]Nl.l 0I"N1.2 [-IN 1.3 NIA.4 0N2.1 El N2.2 0N2.3 0 N3.1 [I N3.2 [I N3.3 0 N4.1 [I N,4.2 0 N4.3 L] N4.4 DN4.5 QN5.1 0N6.1 [ N6.2 El N7.1 [I N7.2 [I N 7.3 [ N7.4 0 N7.5 DN7.6 0N7.7 0N7.8 [IN7.9 E] N7.10 [1 N8.1 Failed Barriers: QRCS OContainment OFuel Clad Dnone [Heat Removal Sys Inadequate 10 Emergency Releases: -, -None I'-]Is Occurring I

14. Meteorological Data [ ind Direction (from) peed(mph)_ []T 15 Recommended Actions:

XThere are no recommended protective actions.

16. Approved By: Emergency Director (Name) (Title)

A. Line 1 check box A or B.

B. Line 6 fill in the declaration time/date (time that you evaluated the condition in procedure).

C l. Line 7 check the box(es) for the criteria requiring this emergency classification (only one required).

C2. Check all failed barriers or none; check heat removal inadequate if appropriate.

C3. If more information is required, list it on a separate page; read it over the ENN when line 7 is read.

D. Line 10 if an Emergency Radioactive release is in progress, check box C; otherwise, check box A.

E. Line 14-enter the current met data (35 foot elevation preferred) from PPC (ERDS) or the BOP.

F. Line 16, the Emergency Director must sign this form.

G. Within 15 minutes of declaration time, using the ENN (instructions on following page), contact the state agencies listed below. Enter below the time of the attempted initial ENN contact (transmission time). Enter below the name of the person contacted once obtained. Check the acknowledged box when receipt of message is acknowledged. The table on the next page lists methods of contact.

Alabama Radiation Control/

Troopers/Houston Co. Time Name AcknowledgedO GEMA/Early County Time Name Acknowledged[]

If AEMA is not on the ENN, they are not required to be notified.

AEMA Time Name AcknowledgedD H. Proceed to the following page for the REMAINING NOTIFICATIONS at step I.

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12/31/02 9:41:30 SHTIARED GUIDELINE 4 FNP-0-EIP-9.0 NOTIFICATION OF UNUSUAL EVENT BLUE VERBAL NOTIFICATION FORM ENN INSTRUCTIONS FOR INITIAL NOTIFICATION I. Pickup handset, dial CC9907 to open all speakers, DIAL ** on the ENN, wait 10 seconds, press to talk and announce "This Is name/title at Farley Nuclear Plant. Please obtain a Notification of Unusual Event, BLUE initial notification form and monitor the ENN."

2. Request a state level agency for Alabama and Georgia and the AEMA acknowledge manning of the ENN per step G on the previous page. Example "Alabama Radiation Control at Montgomery EOC are you on the fine?"

3 Pickup handset, DIAL ** on the ENN, wait 10 seconds, press to talk and announce on the ENN "Please prepare to receive a Notification Of Unusual Event, BLUE initial notification message with acknowledgment", then slowly read the NOUE initial notification form over the ENN.

4. Have the agencies contacted above, acknowledge receipt of the message.

5. Pickup handset, Dial CC9900 to close all speakers opened in step 1.

6. If any required agency could not be contacted on the ENN, then use numbers listed below or in FNP-0-EIP-8.3 to contact them by any available means.

NOTIFICATION MEANS (underlined numbers are available 24 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> hours aa day day)

NOTMCATIONI MEANS (underlined numbers are available GEORGIA State Agencies in preferred order ALABAMA State Agencies in preferred order Alabama Radiation Control at Montgomery EOC GEMA at Atlanta EOC ENN (11), OPX (6628), phone (334-242-4378) ENN (2 1). OPX (6629). Phone (404-635-7200)

FAX (334-264-4396) FAX (404-627-4850)

State Troopers In Montgomery GEMA at Georgia Forward EOC ENN (12). phone (334-242-4378. 4379) ENN (22) OPX (6626) phone (229-723-4826)

Alabama Radiation Control at Alabama Forward FAX (8-257-2455)

EOC EARLY COUNTY ENN (13), OPX 6621), phone (334-793-1565) ENN(42) ENN(41) OPX (6622)FAX(8-257-2455)

FAX (8-257-1535) phone(229-723-3577. 3578,4826)

HOUSTON COUNTY ENN(3 1). ENN(13), OPX (6621), FLORIDA State Agency FAX(8-257-1535) Florida Department of Emergency Management phone (334-794-9720, 793-9655, 334-677-4807,4808) phone (800-320-0519) (850-413- 9911)

AEMA COURTESY NOTIFICATION FAX (850-488-7841)

ENN (51)

REMAINING NOTIFICATIONS (continued from previous page)

I Fax a copy of the previous page NOUE BLUE VERBAL NOTIFICATION FORM to the State of Florida, EOF, and EOC using speed dial #10 or an alternative method of contact that is listed in the table above.

J Verify the State of Florida has received the FAX using the numbers listed in the table above.

K Complete Figure 6, side 1, follow-up message as soon as possible.

L Fax Figure 6, side 1, to state and local agencies as soon as possible, but within 30 minutes of the verbal notification per the instructions on Figure 6, side 2.

M Provide the information on Figure 6, side 1, to the NRC as soon as possible, but within one hour of the declaration per the instructions on Figure 6, side 2.

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1')/'11/N"J O.A1 -*N PNP-O-P*IP-9.0 SHARED_ A- E TABLE 1 REFERENCES Joseph M. Farley Nuclear Plant Emergency Plan FNP-0-RCP-25, Health Physics Activities During a Radiological Accident FNP-0-EIP-29, Long Term Dose Assessment FNP-0-EIP-20, Chemistry and Environmental Support to the Emergency Plan a FNP-0-M-007, Emergency Dose Calculation Method a FNP-0-M-01 1, Offsite Dose Calculation Manual

• EPA "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents"

• NUREG-0654, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants"

• FNP-O-CCP-641, "Operation of the Plant Vent Stack Monitoring System" a NT-86-0014, Gaseous Releases, Emergency Classifications

• NT-87-0543, Protective Action Recommendation Policy ALA 88-694, Westinghouse "Potential Radiological Impact of Steam Generator Tube Uncover" FNP-0-CCP- 1300, Chemistry and Environmental Activities During a Radiological Accident SCS letter File: ENG 15 94-0466 Log: FP 94-0364, Containment Dose R-27 to DEI Conversion Page 1 of 1 Version 49

12/31/02 9:41:30 0, A- j-'. FNP-0-EIP-9.0 TABLE 2 EMERGENCY FACILITY ACTIVATION Unusual Site Area General Event Alert Emergency Technical Support

• Activate # Activate # Activate Center Operations Support Activate # Activate # Activate Center Emergency Operations Activate # Activate Facility Emergency Operations ** Activate # Activate Center Public Information *** Activate # Activate Corporate Offices News Media Center ## N/A *** Activate NOTE: (It is recommended that the full TSC and EOF staffs be called In at the ALERT level. After evaluating plant conditions, staff may be released below a GENERAL EMERGENCY (at the discretion of the RM/ED).

NO ACTION, STANDBY OR ACTIVATE AT THE DISCRETION OF THE EMERGENCY DIRECTOR

• • NO ACTION, STANDBY OR ACTIVATE AT THE DISCRETION OF THE RECOVERY MANAGER S NASTANDBY OR ACTIVATE AT THE DISCRETION OF THE RECOVERY MANAGER

• *** ACTIVATION DEPENDENT ON LEVEL OF MEDIA INTEREST OR EOF ACTIVATION

1. FOLLOWING FULL ACTIVATION, FACILITY STAFFING WILL BE TO THE EXTENT DEEMED NECESSARY BY THE EMERGENCY DIRECTOR AND RECOVERY MANAGER

1. 1. AUTOMATICALLY ACTIVATED UPON EOF ACTIVATION Page I of 1 Version 49

• A hA d *AA A ....

12/31/02 9:41:30 .FNP--EIP-9.

TABLE 3 CONSIDERATIONS FOR EMERGENCY CLASSIFICATION BASED ON SECURITY EVENTS IF THERE IS A POTENTIAL HAZARD TO THE SAFETY OF PERSONNEL DUE TO THE SECURITY EVENT THAT IS IN PROGRESS, THE PROVISIONS OF THE EIPs MAY HAVE TO BE MODIFIED TO ENSURE THAT PLANT PERSONNEL ARE PROTECTED. CONSIDERATION SHOULD BE GIVEN TO THE SAFETY OF PERSONNEL WHO ARE ON SITE AND THOSE WHO WILL BE REPORTING TO THE SITE. THE FOLLOWING LIST DESCRIBES SOME OF THE ACTIONS THAT MIGHT BE DIFFERENT:

1. Do not delay declaring the emergency, some specific actions in the guidelines may have to be altered.

2. Contact security for recommendations to determine hazardous areas prior to taking any actions that would move people to different areas of the plant.

3. Ensure that control room or other supervisory personnel do not dispatch personnel to areas of the plant until it has been determined that those areas are safe.

4. If activating the plant emergency alarm (PEA) would put personnel at risk while proceeding to assembly areas, do not activate the alarm. In lieu of the PEA, consider making an appropriate announcement over the plant page with specific instructions such as to remain inside buildings, evacuate specific areas or other appropriate announcements based on security recommendations.

5. If having the TSC and EOF staffs report to the plant site would put them at risk, consider a manual callout of a minimum staff with specific instructions identifying where to report in lieu of using the ERO Callout System to activate.

6. Consider use of alternate facilities for the TSC and EOF staffs.

7. If the ERO Callout system is used to activate the TSC and EOF staffs, consider using message number 2 to have the EOF and TSC staffs report to the Alternate EOF.

8. After security reports that the security hazards have been eliminated, return to full implementation of the EIPs as appropriate.

Page 1 of 1 Version 49

C"p j rNr-U-rr-Y.U 12/31/0 9:41:30 S.iAED TABLE 4 INFORMATION LIKELY TO BE REQUESTED BY THE NRC IF AN EMERGENCY IS DECLARED (NRC INFORMATION NOTICE 98-08)

1. Is there any change to the classification of the event? If so, what is the reason?

2. What is the ongoing/imminent damage to the facility, including affected equipment and safety features?

3. Have toxic or radiological releases occurred or been projected, including changes in the release rate? If so, what is the projected onsite and offsite releases and what is the basis of assessment?

4. What are the health effect/consequences to onsite/offsite people? How many onsite/offsite people are/will be affected and to what extent?

5. Is the event under control? When was control established, or what is the planned action to bring the event under control? What is the mitigative action underway or planned?

6. What onsite protective measures have been taken or planned?

7. What offsite protective actions have been recommended to state/local officials?

8. What is the status of State/local/other Federal agencies' responses, if known?

9. If applicable, what is the status of public information activities, such as alarm, broadcast, or press releases (regulatee/state/local/other federal agencies)? Has a Joint Information Center (News Media Center) been activated?

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12/31/02 9:41:30 SHARED FNP-0-EIP-9.0 10 MILE EMERGENCY PLANNING ZONE

"--The boxes in each quadrant and at the top of the drawing, represent the time in minutes that it would take to evacuate the zones in that quadrant during a WD (week day), WN (week night), WE (week end) and AW (adverse weather conditions). The time includes a 15 minute allowance for notification.

Zones WD WN WE AW 2 Mile Zone A 95 80 90 95 l0 Mile All Sectors 140 115 115 150 270-360 Quadrant, 100% 000-090 Quadrant, 100%

Evacuation Times Evacuation Times Zones WD WN WE AW Zones WD WN WE AW 5 Mile 105 90 95 110 5 Mile 105 95 100 110 l0 mile 115 100 105 120 l0 mile 110 105 110 1 120 Circles represent 2, 5 and 10 mile radii 180-270 Quadrant, 100% 090-180 Quadrant, 100%

Evacuation Times Evacuation Times WD WN WE AW WD WN WE AW e 100 95 95 105 105 95 100 110 le 140 110 115 150 le 110 100 105 115 FIGURE I Version 49

EVENT OFFSITE DOSE ASSESSMENT See Note 1 See Note 2 YES YES YES Site Area Emergency Actions NO YES Note I If there is no MIDAS PC available YES then automated dose assessment per Alert EIP-9.1 may be used with caution.

Actions EIP-9.1 automated dose assessment NO will not meet all long term dose NO assessment requirements.

Note 2 For long term dose assessment EIP 9.3 should be used in the TSC. If there is no MIDAS PC available then automated dose assessment per YES YES EIP-9.1 may be used with caution.

EIP-9.1 automated dose assessment NOUE Actions will not meet all long term dose assessment requirements.

FIGURE 2 Version 49

12/31/02 9:41:30 I 9:41:30 12/31/02 FNP-0-EIP-9.0 flfI\E.

TELECOPY GROUP DIAL NUMBERS

,,ielecopy (fax) the initial or followup emergency notification form (Fig. 6) to all of the locations using the group dial numbers listed on the below flow chart. When the activity report is received retransmit the form to any location that did -not receive the form using the individual speed dial numbers listed below. Verify that the form has been received at all locations through the ENN, OPX or commercial phone number. The telecopy to the Florida FDEM needs only to be verified for the initial notification or classification SSTART upgrade.

A I DO NOT USE TELECOPY Read the message over the ENN or commercial telephone YES Use group dial number 28 on the operable fax machine AORC at Montgomery EOC

>1o I m AORC at Alabama FEOC GEMA at Atlanta EOC GEMA at Georgia FEOC AEMA at Clanton EOC FDEM at Tallahassee TSC/EOF number 25 on both the Al. and Ga. fax FNP EOC in Birmingham AL. FAX MACHINE GA. FAX MACHINE group dial number 25 group dial number 25 ARCD at Montgomery EOC GEMA at Atlanta EOC ARCD at Al. FEOC GEMA at GA FEOC AEMA at Clanton EOC FDEM at Tallahassee TSC/EOF FNP EOC in Birmingham FAX ENN ENN IND PHONE Refer to FNP-0-EIP-8.1 or FIG. 6 for OPX/commercial numbers. SPEED LOCATION DIAL NUMBER Alabama Office of Radiation Control At Montgomery EOC I 11 Alabama Office of Radiation Control At Alabama Forward EOC 3 13 Alabama Emergency Management Agency at Clanton EOC 7 51 FNP TSC 5 62 FNP EOF (from opposite location) 5 63 Georgia Emergency Management Agency at Atlanta EOC 2 21 Georgia Emergency Management Agency at Georgia Forward EOC 4 22 Florida Department of Emergency Management at Tallahassee 8 none FNP EOC in Birmingham 6 65 FIGURE 3 Version 49

FNP-0-EIP-9.0 12/31/02 9:41:30 SHARED FIGURE 4 THIS FIGURE HAS BEEN DELETED FIGURE 5 THIS FIGURE HAS BEEN DELETED Version 49

12/31/ .0 2 9:41SI0 FNP-0-EIP-9 EMERGENCY NOTIFICATION

[A]This is a Drill [']Actual Emergency [C]Initial [']Follow-up* Message Number

""J 2. Site: Farley Nuclear Plant Unit: Reported By:.

(334)899-5156 or

3. Transmittal Time/Date: / / Confirmation Phone Numbers: (334)794-08oo Ext.

(central) num dd y Telecopy Phone Number:. n"(205) 257-1155 ["n(205) 257-1035 Fl TSC EOF Other

4. Authentication (if required): N/A N/A

5. Emergency Classification:

S[A- Notification Of Unusual Event (Number)

["]Alert []

(Codeword)

Site Area Emergency ['J General Emergency I

6. [*]Emergency Declaration At: [5Termination At: Time/Date______ / / (If B go to item 16)

(central) mm ddDp e

7. Emergency Description/Remarks: __________________________

Problems Include: iA IRCS FB Containment iCFuel Damage Indicated ID Heat Removal

[ Systems Inadequate FEt.on Additional comments following page

((Leaking ((Leaking U

8. Plant Condition: Z Improving F]Stable [c]Degrading [D]RMTs Dispatched E] Site Evacuation

9. Reactor Status: []Shutdown Time/Date: __ __/ / [] __  % Power (central) MM dd yy

10. Emergency Releases:

[A-']None (go to item 14)_ [ P]Potential (go to item 14) ["]Is Occurring [D]Has Occurred

11. Type of Release AIGround Level [B] Mixed Mode

[c-] Airborne: Started: _ _ _/ / []'Stopped: / /

Time (central) Date Time (central) Date ME Liquid: Started: _ ___/ - / _ ]Stopped: _/ -/

Time (central) Date Time (centrajl Date

12. Release Magnitude ["]pCurie per Sec. [']Curies Tech. Specification Limits IJBelow ']Above

[ENoble Gases _ __ [Iodines

[G]Particulates _['] Other

13. Estimate Of Projected Off Site Dose [X]New [']Unchanged ["]Estimated Duration: Hrs.

Site Boundary [~] TEDE (mrem)

_ _ _ _EI_

Thyroid CDE_ (mtem)_ _

2 miles M' MG 5miles _ _M 10 miles [E]'_ [ _

14. Meteorological Data [A- Wind Direction (from) 0 [-]Speed(mph)

[ Stability Class _ _D-] Precipitation (type)

15. Actions:

SThere are no recommended protective actions.

[E]We would like to discuss recommended protective actions.

[C] Evacuate and control access in down wind zone(s)

I-DJ Shelter and control access in down wind zone(s)

AND In all affected areas: Monitor environmental radiation levels, locate and evacuate hot spots and implement control and possible confiscation of food and water supplies and consider evacuation of children and pregnant women.

['E"] Other

16. Approved By: Time/Date / /

(Name) (Title) (central) mm dd yy

• lfitems 9- 13 have not changed, onlyitems I -8 and 14- 16 arerequired to be completed FIGURE 6 SIDE 1 Version 49

12/31/02 9:41:30 FNP-0-EIP-9.0 SHARED COMMUNICATIONS MEANS 1)0 NOT TELECOPY THIS SIDE 17.0 For initial and upgrade declarations only, Notify NRC Headquarters. Read side one of this form. Immediately after State Notification, within one hour of Declaration.

[o ENS (301-816-5100; 301-951-0550; 301-415-0550)

[]Commercial (1-301-816-5100; 1-301-951-0550; 1-301-415-0550 Date/Time Person contacted date time 18.0 For initial, upgrade and follow-up notifications, fax figure 6 side 1 to state, local and company agencies using the speed dial button determined in figure 3 as soon as possible. For initial and upgrade notifications fax within 30 minutes of the verbal notification. 1 19.0 Verify that the following agencies received the fax using the ENN or other numbers listed below Person Contacted Date/Time Alabama Radiation Control at Montgomery EOC Alabama Radiation Control at Alabama FEOC (Houston County)

GEMA at Atlanta EOC GEMA at Georgia FEOC (Early County)

AEMA at Clanton EOC FDEM at Tallahassee TSC/EOF CEOC in Birmingham NOTIFICATION MEANS (underlined numbers are available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day)

ALABAMA State Agencies in preferred order GEORGIA State Agencies in preferred order Alabama Radiation Control at Montgomery EOC GEMA at Atlanta EOC ENN (11), OPX (6628), phone (334-242-4378) ENN (2 ). OPX (6629). Phone (404-635-7200)

FAX (334-264-4396) FAX (404-6274850)

State Troopers In Montgomery GEMA at Georgia Forward EOC ENN (12) phone (334-2424378.4379) ENN (22) OPX (6626) phone (229-7234826)

Alabama Radiation Control at Alabama Forward FAX (8-257-2455)

EOC EARLY COUNTY ENN (13), OPX 6621), phone (334-793-1565) ENN(42) ENN(41) OPX (6622)FAX(8-257-2455)

FAX (8-257-1535) phone(229-723-3577. 3578, 4826)

HOUSTON COUNTY ENNA(31). ENN(13). OPX (6621), FLORIDA State Agency FAX(8-257-1535) Florida Department of Emergency Management phone (334-794-9720, 793-9655, 334-677-4807,4808) phone (800-320-0519) (850-413- 9911)

AEMA COURTESY NOTIFICATION FAX (850-488-7841)

ENN (51)

Figure 6 side 2 Version 49

FNP-0-EIP-9.0 12/31/02 9:41:30 ST4ARFED EMERGENCY NOTIFICATION CONTINUATION SHEET ***

7. (Continued) Additional Comments: Message Number

-I

• • • This form is only required if 7E is checked on Figure 6.

Figure 7 Version 49

12/31/02 9:41:30 FNP-0-EIP-9.0

'QT ALF Dose Equivalent Iodine Estimation

"*thebelow graph and table can be used to estimate if dose equivalent iodine (DEI) is above 300 microcuries per gram. When using this figure the following rules must be used:

1. The only radiation monitors that can be used to enter the graph or table are R-27A or B.

2. The leak rate is assumned to be constant for the time period specified.

3. The bottom of the scale for the R-27 monitors is 1 REM/hr.

4. Any R-27 reading greater than 1 REM/hr for a leak rate of 50 gpm or less is an indication of DEI being greater than or equal to 300 microcuries per gram.

5. Enter the graph with the R-27 reading and the length of time that the leak has been in progress. If the intersection of R-27 and time is above and to the left of the curve for the specific leak rate the DEI is likely to be greater than 300 microcuries per gram.

6. Enter the table with the number of minutes since the start of the leak and the leak rate. If the actual R-27 dose rate is above the value listed in the table the DEI is likely to be greater than 300 microcuries per gram.

60MINJ 120MIN I80MIN 240MIN TIME 5 MIN 10MIN 30MIN LEAK 1000 1 11.9 18.1 22.3 4 25 4 I RATE 500 5.93 9.06 11.1 12.5

[GPM]

100 1.19 1.81 2.23 2.5 100 U

10 0

1+/-

N 1

0 30 60 90 120 150 180 210 240 MNUTES SINCE START OF LEAK FIGURE 8 Version 49