ML020640358
| ML020640358 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 02/13/2002 |
| From: | Gallagher M Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Security and Incident Response |
| References | |
| Download: ML020640358 (45) | |
Text
Exel nr.
Exelon Nuclear www.exeloncorp.com Nuclear 200 Exelon Way Kennett Square, PA 19348 1 OCFR50, Appendix E February 13, 2002 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Limerick Generating Station, Units 1 & 2 Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos. 50-352 and 50-353 ERP-316, Revision 1, "Operation of the Dose Assessment Computer" ERP-326, Revision 1, "Shift Dose Assessment Personnel (SDAP)"
ERP-360, Revision 4, "Adjustment of Wide Range Gas Monitor Conversion Factors"
Dear Sir/Madam:
Enclosed are revised Emergency Response Procedures (ERPs) for Limerick Generating Station (LGS), Units 1 and 2. These procedures are required to be submitted within thirty (30) days of their revision in accordance with 10CFR50, Appendix E, and 10CFR50.4.
Also, enclosed is a copy of a computer generated report index identifying the latest revisions of the LGS ERPs.
If you have any questions or require additional information, please do not hesitate to contact us.
Very truly yours, M. P. Gallagher Director - Licensing & Regulatory Affairs Mid-Atlantic Regional Operating Group Enclosures cc:
H. J. Miller, Administrator, Region I, USNRC (2 copies)
A. L. Burritt, USNRC Senior Resident Inspector, LGS
ATTACHMENT 1 LIMERICK GENERATING STATION, UNITS 1 & 2 Docket Nos.
License Nos.
50-352 50-353 NPF-39 NPF-85 EMERGENCY RESPONSE PROCEDURES ERP-316, "Operation of the Dose Assessment Computer" - Revision 1 ERP-326, "Shift Dose Assessment Personnel (SDAP)"
Revision 1 ERP-360, "Adjustment of Wide Range Gas Monitor Conversion Factors" - Revision 4
Effective Date: 2i 9
ERP-316, Rev.
1 Page 1 of 16 KLM/mes EXELON NUCLEAR LIMERICK UNITS 1 AND 2 EMERGENCY RESPONSE PROCEDURE ERP-316 OPERATION OF THE DOSE ASSESSMENT COMPUTER (CM-3)
WARNING THIS PROCEDURE SHALL BE IMPLEMENTED UPON DECLARATION OF AN EMERGENCY OR AT THE DISCRETION OF THE SHIFT MANAGEMENT AT THE AFFECTED SITE.
1.0 RESPONSIBILITIES 1.1 The Dose Assessment Coordinator (DAC) shall perform dose projections using this procedure when required.
2.0 INITIAL ACTIONS 2.1 Activate computers used for dose assessment.
2.1.1 Turn on computer power.
2.1.2 IF computer and printer do not activate THEN ensure individual switches are turned on.
2.1.3 Verify paper is loaded in adequate supply.
2.1.4 Log onto the Computer Dose Assessment System.
2.1.4.1 Control Room
- a. Password = MCR
- b. User ID = 111111 2.1.4.2 TSC
- a. Password = TSC
- b. User ID = 222222 2.2 IF equipment failure occurs in the MCR, THEN using a
D1512 key relocate to the Technical Support Center (TSC)
Dose Assessment Room.
ERP-316, Rev.
1 Page 2 of 16 NOTE THE PASSWORD AND USER ID FOR THE CONTROL ROOM DOSE ASSESSMENT COMPUTER WILL ALLOW ACCESS TO FAST MODE A, AUTO MODE A, OR LIQUID DOSE CALCULATIONS.
THE PASSWORD AND USER ID FOR THE TSC DOSE ASSESSMENT COMPUTER WILL ALLOW ACCESS TO FAST MODE A, MODE A, AUTO MODE A, LIQUID DOSE CALCULATIONS, OR BACK CALCULATION SOURCE TERM.
2.3 Collect appropriate data for section(s) of attachment 1 and 6, IF actual values are not available THEN use default values as stated in Mesorem.
CM-1 3.0 CONTINUING ACTIONS 3.1 IF performing dose projections in the Limerick Control Room, THEN select either, Fast Mode A or Auto Mode A.
3.1.1 For Auto Mode A, see attachment 2 titled, "Auto Mode A"l.
3.1.2 For Fast Mode A, see attachment 3 titled, "Fast Mode A".
3.1.3 For Liquid Dose Calculations, see attachment 5
- titled, "Liquid Release".
3.2 IF performing dose projections in the Limerick TSC, THEN select F2, Execute Dispersion Model from the command menu.
3.2.1 For Auto Mode A, see attachment 2 titled, "Auto Mode A"l.
3.2.2 For Fast Mode A, see attachment 3 titled, "Fast Mode A"l.
3.2.3 For Mode A, see attachment 4 titled, "Mode A".
3.2.4 For Liquid Dose Calculations, see attachment 5
- titled, "Liquid Release".
3.2.5 For unmonitored releases, evaluate source term based on field survey data.
3.2.5.1 Select F5, Back Calculate Source Term from the command menu AND enter data from attachment 1 titled, "Input Parameters" Part 4, in response to system prompts.
3.3 Verify all data inputs on printout match data sheet.
ERP-316, Rev.
1 Page 3 of 16 3.4 Advise the Emergency Director and/or Shift Management of results of dose projection.
3.5 Repeat dose projections as new information becomes available or until relieved by the PBAPS DAC or EOF Dose Assessment Team.
4.0 FINAL CONDITIONS 4.1 Terminate use of the procedure when:
4.1.1 The Emergency Director determines that the dose assessment function is not longer required.
4.1.2 The potential for and/or actual airborne release has been alleviated.
4.1.3 The Peach Bottom DAC or EOF Dose Assessment Team has taken over the dose assessment function.
4.2 Records generated are compiled for review and submitted to the Nuclear Records Management System (NRMS).
5.0 ATTACHMENTS AND APPENDICES 5.1
- "Input Parameters" 5.2 "Auto Mode A" 5.3 "Fast Mode A" 5.4 "Mode A" 5.5
- "Liquid Release" 5.6
- "Meteorological Parameter Resources" 6.0 SUPPORTING INFORMATION 6.1 PURPOSE To provide directions for using the Dose Assessment Computer System.
6.2 CRITERIA FOR USE This procedure shall be implemented when an Alert or higher level emergency has been declared in accordance with ERP-101, Classification of Emergencies, or at the discretion of the affected site Emergency Director.
6.3 SPECIAL EQUIPMENT 6.3.1 Mesorem Jr.
ERP-316, Rev.
1 Page 4 of 16
6.4 REFERENCES
6.4.1 Nuclear Emergency Plan 6.4.2 ERP-301, "Dose Assessment Coordinator (DAC)"
6.4.3 ERP-300,
" Dose Assessment Coordinator" (LGS) 6.4.4 ERP-315, "Operation of the Dose Assessment Computer" (PBAPS) 6.4.5 ERP-325, "Shift Dose Assessment Personnel" (PBAPS) 6.4.6 ERP-326, "Shift Dose Assessment Personnel" (LGS) 6.4.7 Offsite Dose Calculation Manual (ODCM) 6.4.8 MESOREM, Jr., System Atmospheric Dispersion and Dose Assessment Program (Version 8.3) 6.4.9 EPA-400, "Manual for Protective Action Guides and Protective Actions for Nuclear Incidents" 6.5 COMMITMENT ANNOTATION 6.5.1 CM-i, NRC Inspection 93-03/03, T02541 (section 2.3) 6.5.2 CM-2, Letter to NRC, 08/15/86, T01949 (attachment 5) 6.5.3 CM-3, Letter to NRC, 12/30/83, T03167 (refers to entire procedure)
ERP-316, Rev.
1 Page 5 of 16 ATTACHMENT 1 INPUT PARAMETERS (Page 1 of 3)
EVENT INFORMATION Unit Accident Type
] LOCA.
D Minor damage, D MCA Data (Default = LOCA)
Time of Release in Military Format (HH:MN)
Date of Release in Standard Format
/
/_
(MM/DD/YY)
Night or Day?
(N or D)
Adverse Weather or Normal Weather?
(A or N)
Estimated Release Duration:
(HH:MM)
(Default Value 4 Has the Release been in Progress?
(Y or N)
If Yes:
Time Release has been in Progress (HH:MM)
If No:
Time Until Release Begins:
(HH:MM)
Has the Reactor reached 0% Power?
(Y or N)
Time of Reactor reaching 0% Power (HH:MM)
Account for Wet Deposition?
(Y or N)
Release Points (check one or more)
[]
Main Stack El Unmonitored Release Is release from 11 Drywell F Suppression Pool D Other
- 00)
Drywell sprays F]
ON OFF Is Suppressions Chamber 1]
Saturated 0
Supercooled F]
Unknown Simultaneous Release?
(Y or N)
Verify Standby Gas Treatment Efficiency.
Utilize 95.0% default value until the current efficiency can be verified by Peach Bottom Shift Management and/or System Engineer or by the most recent surveillance test.
ERP-316, Rev.
1 Page 6 of 16 ATTACHMENT 1 INPUT PARAMETERS (Page 2 of 3)
PART I.
IA.
IB.
- 2.
Information required only if Auto Mode A is unavailable.
METEOROLOGICAL PARAMETERS (For backup or alternate source inputs, refer to the attachment 6
- titled, "Meteorological Parameter Resources")
For Main Stack Release Wind Speed mph from Tower 2, 320 ft.
Wind Direction from Tower 2, 320 ft.
Delta Temperature
°F from Tower 2, 316' 33' Ambient Temperature OF for Tower 2, 33 ft.
Precipitation (60 minute total from MET screen or 'N'
= not available)
For Unmonitored Release Wind Speed mph from River Tower Wind Direction from River Tower Delta Temperature
°F from Tower 2, 316' 33' Ambient Temperature OF for Tower 2, 33 ft.
Precipitation (60 minute total from MET screen or 'N'
= not available)
ERP-316, Rev.
1 Page 7 of 16 II.
IIA.
PART 3 I.
Total Iodine Concentration Ci/cc PART 4. Unknown Isotopic Breakdown for Unmonitored Release Field Survey Whole Body Dose Rate mR/hr Field Survey Thyroid Dose Rate mR/hr Distance from the plant to where the field survey readings were obtained miles.
Angle between the field reading location and 0 degrees North Angle is positive in the clockwise direction and must be 180 degrees from the wind direction already inputted.
ATTACHMENT 1 INPUT PARAMETERS (Page 3 of 3)
EFFLUENT PARAMETERS For Main Stack Release Count Rate Ci/cc (Check which parameter used)
Low Range (red),
panel 00C014 Mid Range (blue),
panel 00C014 High Range (green),
panel 00C014 Flow Rate kcfm (FRS-0470, panel 30C010)
Information required for known isotopic projections.
Isotopic Breakdown If known, enter sample results.
Kr 83m Xe 131m Kr 85m Xe 133m Kr 85 Xe 135m Kr 87 Xe 135 Kr 88 Xe 137 Kr 89 Xe 138 Total Noble Gas Concentration
_tCi/ccjiCi/c 1-131 1-133 1-135 T-139 1-134 I
C
ERP-316, Rev.
1 Page 8 of 16 ATTACHMENT 2 AUTO MODE A (Page 1 of 4)
- 1.
From Mode A or Auto A Menu Choose;
- a.
F3 --
Auto Mode A -
Initiate automatic data collection
- 2.
Choose DBA from Accident Menu
- 3.
Answer the following prompts:
- a.
Enter the time of the release in military format (Current system time = <ENTER> = 07:42)
- b.
Enter the date of the release in standard format (Current system time = <ENTER> = 09/23/93):
- c.
Night or Day?
(N or D,
<ENTER> = D):
- d.
Adverse Weather or Normal Weather?
(A or N,
<ENTER> = N):
- e.
Enter estimated release duration.
(00:01 to 999:00,
<ENTER>
4:
0):
NOTE:
TO USE AUTO MODE A THE FOLLOWING PROMPT MUST BE ANSWERED "Y",
OTHERWISE, YOU WILL BE PROMPTED TO SWITCH TO FAST MODE A.
(AUTO DATA COLLECTION CANNOT HAPPEN FOR A RELEASE THAT HAS NOT YET OCCURRED).
- f.
Has the release been in progress?
(Y or N,
<ENTER> = N):
Y
- g.
Time the release has been in progress.
(Format is (HH:MIM),
<ENTER> = 0:
0):
- h.
When did the reactor reach 0% power?
- 1. Date = <ENTER> = 09/23/93:
- 2.
Time in 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> format = <ENTER> = (00:00)
Time since reactor shutdown will be displayed
- i.
Do you wish the model to account for wet disposition?
(Y or N,
<ENTER> = N):
Select appropriate tower/sensor data from this table.
ERP-316, Rev.
1 Page 9 of 16 ATTACHMdENT 2 AUTO MODE A (Page 2 of 4)
NOTE:
METEOROLOGICAL AND RADIOLOGICAL DATA FOR THE TIME IN QUESTION WILL BE DISPLAYED.
ANY OF THIS DATA CAN BE EDITED BY THE USER.
ANY DATA MARKED WITH A CHECK MARK TO THE LEFT IS BAD DATA AND WILL NOT BE USED BY THE SYSTEM.
THE BAD DATA MARK CAN BE REMOVED BY PRESSING ALT-B WITH THE CURSOR ON THAT DATA.
THIS WILL CAUSE THE PROGRAM TO USE THAT DATA AS GOOD DATA.
DATA MARKED WITH AN "R" IS DATA THAT IS OUT OF RANGE.
THIS DATA CANNOT BE USED BY THE PROGRAM AND MUST BE CORRECTED.
The Auto Mode A Screen is then displayed:
- j.
View data and press F10 to continue.
- 1.
If any of the data points are out of range, a warning will be displayed at the bottom of the screen and the cursor will go to the bad data point.
This situation must be corrected before continuing.
- 2.
If any meteorological data points are displayed as "bad data",
the backup sensor will be used by the program.
If radiological data for the release point in question is bad, or if all of a particular met quantity is bad, Auto Mode A will cease and the operator will be forced to use Fast Mode A or Mode A.
- k.
Choose release point from release point menu.
- 1. Met Data that will be used will be displayed.
- 1. Enter whether isotopic breakdown is known or unknown at breakdown menu.
- 1. If unknown isotopic breakdown.
For PBAPS Main Stack, (For other release points, no SGTS prompt)
Enter the current stand-by-gas-treatment efficiency.
Range is
[.0000 to 99.99
]
[<ENTER> =
95.0
]
Use the default value unless instructed otherwise.
ERP-316, Rev.
1 Page 10 of 16 ATTACHMENT 2 AUTO MODE A (Page 3 of 4)
- 2.
If known isotopic breakdown,
- a. Then choose from isotope mix menu:
Isotopic Mix in Percentages Isotopic Mix in Concentration Isotopic Mix in Release Rate
(%)
(tCi/cc)
(4Ci/sec)
- b. How long after scram was the sample taken?
(Enter 00:00 if the sample was taken before the scram)
(Make sure a colon ":" separates the hours and minutes)
(Format is (HH:MM),
<ENTER> = 0:
0):
- c. Enter each noble gas and iodine isotope:
(in units chose at menu)
- d. Enter total iodine concentration (jiCi/cc).
Range is
(.0000 to 1.0000E+08)
(<ENTER> =.0000
):
- e. Do you wish to enter additional isotopes?
(Y or N, <ENTER> = N) : Y
- f.
If answered "Y",
additional isotopes may be entered.
NOTE:
DEPENDING ON RELEASE POINT AND ANSWERS TO THESE PROMPTS, SEVERAL PROMPTS WILL APPEAR CONCERNING THE RELEASE PATH.
THESE ARE USED TO DETERMINE THE NOBEL GAS TO IODINE RATIO AND ALL HAVE "UNKNOWN" AS AN OPTION.
THIS PROMPT IS AN EXAMPLE:
IS THIS RELEASE FROM DRYWELL ATMOSPHERE, SUPPRESSION CHAMBER ATMOSPHERE, OR OTHER?
(D, S, 0, UNKNOWN = 0 <ENTER> = 0):
ERP-316, Rev. 1 Page 11 of 16 ATTACHMENT 2 AUTO MODE A (Page 4 of 4)
NOTE:
ADDITIONAL NUCLIDES MAY BE ENTERED BY SYMBOL, MASS NUMBER, AND RELEASE RATE IN ý.Ci/cc.
A MAXIMUM OF UP TO 33 NUCLIDES MAY BE ENTERED.
ENTER THE SYMBOL UP TO 2 LETTERS AT THE FIRST
- PROMPT, THE ATOMIC WEIGHT UP TO 3 DIGITS AT THE SECOND PROMPT ALONG WITH THE CHARACTER "M" IF THE NUCLIDE IS IN THE METASTABLE STATE.
(I.E Xe <-- AT THE FIRST PROMPT 133M <-- AT THE SECOND PROMPT)
- g.
Enter the nuclide symbol.
radionuclides):
(<ENTER> = No other
- h.
Enter nuclide mass number, including M for metastable:
- i.
Enter the amount of release in ýtCi/cc.
Range is
(
.0000 to 1.0000E+20)
(<ENTER>
=
.0000
):
- j.
View isotopic breakdown.
- 3.
Would you like an automatic dump to the printer?
(Y or N,
<ENTER> = Y) :
Output will be produced designated location.
- 4.
Will this be a simultaneous release?
(Y or N,
<ENTER> = N) :
- 5.
Receptor Display Menu will appear.
NOTE:
THESE OPTIONS ARE SELF EXPLANATORY EXCEPT FOR F7 RECEPTOR INFORMATION.
THIS OPTION GIVES THE OPPORTUNITY TO DISPLAY ALL INFORMATION FOR A PARTICULAR RECEPTOR.
TPARD = TOTAL PROTECTIVE ACTION RECOMMENDED DOSE =
EXTERNAL DOSE + ADULT CEDE + 4 DAY.
4DAY
= SHINE DOSE FROM 4 DAYS' EXPOSURE TO GROUND DEPOSITION FROM RELEASE.
=
PLUME ARRIVAL TIME DOSE RATIO RATION OF EXTERNAL DOSE + CEDE (TEDE)
TO EXTERNAL DOSE.
THIS RATION GIVES A METHOD TO ESTIMATE TEDE FROM EXTERNAL DOSE (DRD READING).
USED PRIMARY FOR FIELD TEAM DOSE ESTIMATION.
ERP-316, Rev.
1 Page 12 of 16 ATTACHMENT 3 FAST MODE A
- 1.
Select Fl, Fast Mode A, from the Command Menu.
- 2.
IF isotopic breakdown unknown THEN select Fl, Loss of Coolant Accident; IF isotopic breakdown is known THEN select FI0, MCA Data
- 3.
Enter data recorded on attachment titled "Input Parameters" in response to system prompts and menus.
- 4.
Ensure appropriate device is selected for printer output.
- 5.
Make appropriate printout selection.
- 6.
IF a release is in progress from more than one release point THEN enter a "Y" after the prompt, "Will this be a simultaneous release?"
AND repeat until data for all release points has been entered.
- 7.
IF specific receptor data is
- desired, THEN select the appropriate receptor from the Receptor Display Menu OR select Q to leave the menu.
- 8.
IF another dose projection is
- desired, THEN respond "Y" to the prompt OR respond "N" to leave the system.
ERP-316, Rev.
1 Page 13 of 16 ATTACHMENT 4 MODE A
- 1.
Select Fl, update data, from the command menu.
- 2.
Select files to be updated from File Menu.
- 3.
Enter data recorded on attachment titled, "Input Parameters",
in response to system prompts and menus.
- 4.
Once all files have been updated, select "Q" to return to the Command Menu.
- 5.
Select F2, Execute Dispersion Model, from the Command Menu.
- 6.
Select F2, Mode A, from Mode A Menu.
- 7.
Make appropriate printout selection.
- 8.
Respond to prompts to calculate a simultaneous release, view specific receptor data, run another dose projection, or exit the system, as desired.
ERP-316, Rev.
1 Page 14 of 16 ATTACHMENT 5 LIQUID RELEASE (Page 1 of 2)
- 1.
From Mode A or Auto Mode A Menu, select F4, Liquid Dose Calculations and enter data from this attachment.
- 2.
Source of sample:
NOTE:
BEFORE:
DILUTION CORRECTION APPLIED AFTER:
DILUTION CORRECTION NOT APPLIED Before (Liquid release is to the discharge canal and the sample was obtained prior to dilution in the discharge canal.)
After (Liquid release is to the discharge canal and the sample has been obtained from the discharge canal after dilution by circulation water pump flow OR liquid release is exiting the site by means other than the discharge canal.)
- 3.
Estimated duration of the liquid release:
- 4.
Number of circ water pumps in operation
- 5.
Estimated volume of the liquid release:
hours gallons
- 6.
Isotopic concentrations from analysis of release sample:
Zn-65 __
Ci/ml Co-60 _tCi/ml 1-131 __
Ci/ml Cs-134 Cs-137 Ci/ml Ci/ml NOTE:
THIS ATTACHMENT APPLIES TO LIQUID RELEASES THRU THE DISCHARGE CANAL TO THE RIVER OR LIQUID RELEASES EXITING THE SITE BY MEANS OTHER THAN THE DI-SCHARGE CANAL.
CM-2
ERP-316, Rev.
1 Page 15 of 16 ATTACHMENT 5 LIQUID RELEASE (Page 2 of 2)
- 7.
Make appropriate printout selection.
NOTE:
LIQUID EFFLUENT RELEASE LIMIT PER THE OFFSITE DOSE CALCULATION MANUAL (ODCM).
ODCMS 3.8.B.2 A)
DURING ANY CALENDAR QUARTER,
< 3.0 MREM TO THE TOTAL BODY AND < 10.0 MREM TO ANY ORGAN.
B)
DURING ANY CALENDAR YEAR,
< 6.0 MREM TO THE TOTAL BODY AND < 20.0 MREM TO ANY ORGAN.
- 8.
IF results exceed ODCM limits, THEN the Peach Bottom Emergency Director should ensure notification of the Department of Environmental Resources and downstream domestic water users from the Emergency Response Telephone Directory.
ERP-316, Rev.
1 Page 16 of 16 ATTACHMENT 6 METEOROLOGICAL PARAMETER RESOURCES (Listed in order of preference)
- 1.
Main Control Room Instrument Panels (Control Room Only)
- 2.
Plant Monitoring System (PMS)
(Primary for TSC)
Select appropriate tower/sensor data from this table Release Point MAIN STACK Wind Speed (mph)
Wind Direction 'Deg Azm)
Delta Temoerature (Deg F)
Sigma Theta (Dec.
Azm)
Amilent Temperature (Deg F)
Precipitation (in/hr)
VENT STACK Wind Speed (mph)
Wind Direction (Deg Azir.)
Delta Temperature (Deg F)
Sigma Theta (Deg.
Azm)
Ambien, Temperature (Deg F)
Precipitation (in/hr)
UJNTONITORED RELEASE Wind Speed (mph)
Wind Direction (Deg Azm)
Delta Temperature (Deg F)
Sigma The-a (Deg.
Azm) abient Temperature (Deg F)
Precipitation (in/hr)
Primary Twr 2-320' Twr 2-320' Twr 2-316'-33 Twr 2-75' Twr 2-33' Twr 2 Twr 2-75' Twr 2-75' Twr 2-316'-33' Twr 2-75' Twr 2-33' Twr 2 River Twr 33' River Twr 33' Twr 2-316'-33' Twr 2-75' Twr 2-33' Twr 2 PMS Screen NET MET NET MET NET MET NET MET NET
]YET NET NET NET NET N'sE I
NET NET ET Backup Twr 2-75' Twr 2-75 Twr 2-150' None None TwrA Twr 2-32C' Twr 2-320' Twr 2-150'-33' None None Twr A Twr 2-75' Twr 2-75' Twr 2-150'-33' None None Twr A
- 3.
National Weather Service A.
PENN State NWS:
9-1-814-237-1152 B.
Mount Holly NWS:
9-1-609-261-6604 or 9-1-800-697-0010 Obtain the following meteorological parameters:
Wind Direction (WD30)
Wind Speed (WD30)
Cloud Cover (CLCVR)
Cloud Ceiling (CLCEG)
Ambient Temperature Precipitation deg. az.
knots tenths ft deg.
F in/hr Forecast:
Contact:
PMS Screen NE T NE*T
.NET NET NET MET YET MET NET
ýET NE<T NET MET NET NET NET NET NET
-T ime
Effective Date:
z ERP-326, Rev.
1 Page 1 of 11 KLM/mes EXELON NUCLEAR LIMERICK UNITS 1 AND 2 EMERGENCY RESPONSE PROCEDURE ERP-326 SHIFT DOSE ASSESSMENT PERSONNEL (SDAP) 1.0 RESPONSIBILITIES 1.1 Reports to the shift management at the affected site.
1.2 Capable of reporting to the Control Room within 15 minutes when requested to perform dose projections.
1.3 Provides off-site dose projections and applicable protective action recommendations due to radiological releases or projected radiological releases within 30 minutes of the initiating event (accident, transient).
1.4 Responsible for dose assessment functions until Technical Support Center (TSC)
Dose Assessment Coordinator (DAC) or the Emergency Operations Facility (EOF)
Dose Assessment Team (DAT) is assembled and turn-over is completed.
CM-I NOTE SDAP ACTIVELY PERFORMING DOSE PROJECTIONS SHALL HAVE NO OTHER RESPONSIBILITIES DURING EMERGENCIES THAT DETRACT FROM DOSE ASSESSMENT CALCULATIONS.
CM-2 2.0 INITIAL ACTIONS:
2.1 WHEN an alert or higher level emergency is declared OR WHEN requested by shift management at either site, THEN report to the Control Room.
2.2 IF performing a dose projection for PBAPS THEN upon reporting to LGS Control Room, obtain a copy of PBAPS ERP-200-6 that was Faxed to 802:2092.
WARNING THIS PROCEDURE SHALL BE IMPLEMENTED UPON DECLARATION OF AN EMERGENCY AT PEACH BOTTOM OR LIMERICK AT THE DISCRETION OF THE AFFECTED SITE SHIFT MANAGEMENT.
ERP-326, Rev.
1 Page 2 of 11 2.3 IF no FAX arrived, THEN contact PBAPS Shift Management (807:4687 or 81-231)
AND request ERP-200-6 be Faxed.
2.4 IF performing a dose projection for LGS, THEN request a completed copy of LGS ERP-200-2 from LGS Shift Management.
2.5 IF immediate dose projections are not necessary THEN become familiar with plant radiological conditions, effluent radiation monitors and release rates.
2.6 IF a probable offsite radiological release exists OR IF there is an unexpected or unexplained increase in the effluent radiation monitors, THEN perform a dose projection.
2.7 Activate computers used for dose assessment.
2.7.1 Turn on computer power.
2.7.2 IF computer and printer do not activate, THEN ensure individual switches are turned on.
2.7.3 Verify paper is loaded in adequate supply.
2.7.4 At desk top, choose icon for appropriate site that a dose projection will be performed for.
2.7.5 Log onto the Computer Dose Assessment System.
Use tab key to relocate cursor to next field.
2.7.5.1 Control Room
- a.
Password MCR
- b.
User ID 111111 2.7.6 IF equipment failure occurs THEN using key C-24 (D1512),
relocate to the TSC Dose Assessment Room.
2.7.6.1 TSC
- a.
Password = TSC
- b.
User ID = 222222 2.7.7 After log on, choose F1 or F2 for the appropriate site that a dose projection will be performed for (same site as specified in step 2.7.4).
ERP-326, Rev.
1 Page 3 of 11 NOTE THE PASSWORD AND USER ID FOR THE CONTROL ROOM DOSE ASSESSMENT COMPUTER WILL ALLOW ACCESS TO FAST MODE A, AUTO MODE A, OR LIQUID DOSE CALCULATIONS.
THE PASSWORD AND USER ID FOR THE TSC DOSE ASSESSMENT COMPUTER WILL ALLOW ACCESS TO FAST MODE A, MODE A, AUTO MODE A, LIQUID DOSE CALCULATIONS, OR BACK CALCULATION SOURCE TERM.
2.8 IF performing dose projections in the Control Room, THEN select F3.
Use Auto Mode A (Initiate Automatic Data Collection) and input parameters given by affected site shift Management.
2.8.1 Verify all data inputs on printout match data sheet.
2.8.2 Advise Shift Management and/or DAC/DAT of results of dose projection.
2.8.3 Repeat dose projections as new information becomes available until relieved by the Dose Assessment Coordinator or EOF Dose Assessment Team.
2.9 IF performing dose projections in the Limerick TSC, THEN select F2, Execute Dispersion Model, from the command menu, then select F3, Auto Mode A, and input data from.
2.9.1 IF Auto Mode fails, THEN request additional information from affected site's Shift Management AND use Fl, Fast Mode A.
Initiate model from sequential screens.
2.10 For unmonitored releases, contact affected site's Shift Management to dispatch Radiation Protection Technician to perform site boundary survey.
2.11 IF the dose projection indicates that an emergency action level has been reached, THEN immediately advise shift management.
2.12 Submit any dose projections and protective action recommendations to affected site's shift management for evaluation.
For PBAPS, fax to 807:4793.
3.0 CONTINUING ACTIONS 3.1 Monitor plant radiological parameters and possible radiological release pathways.
ERP-326, Rev.
1 Page 4 of 11 3.2 Inform affected site Shift Management if any radiological parameters change significantly.
3.3 WHEN the affected site Dose Assessment Coordinator (DAC) arrives at the TSC, THEN:
3.3.1 Provide the DAC with current information, including any protective action recommendations, and any previous dose projections.
3.3.2 Discuss whether to remain in the Control Room or terminate the SDAP position.
3.4 WHEN the EOF dose assessment team is activated, THEN perform turnover using attachment 4 titled, "Dose Assessment Turnover Sheet".
4.0 FINAL CONDITIONS 4.1 Exit this procedure when either:
4.1.1 Turnover to the Dose Assessment team is completed and no other assistance is requested by Shift Management at the affected site or 4.1.2 The Emergency Plan has been exited and no other assistance has been requested by Shift Management at the affected site.
5.0 ATTACHMENTS AND APPENDICES 5.1, "Auto Mode A" 5.2,
"Fast Mode A" 5.3,
"Meteorological Parameter Resources" 5.4,
"Dose Assessment Turnover Sheet" 6.0 SUPPORTING INFORMATION 6.1 PURPOSE To provide guidance and direction for Shift Dose Assessment Personnel performing dose assessment.
6.2 CRITERIA FOR USE This procedure is to be implemented upon declaration of an emergency at PBAPS,
- LGS, or at the discretion of Shift Management at the affected site.
ERP-326, Rev.
1 Page 5 of 11 6.3 SPECIAL EQUIPMENT 6.3.1 None
6.4 REFERENCES
6.4.1 ERP-200, "Emergency Director" (PBAPS) 6.4.2 ERP-200, "Emergency Director" (LGS) 6.4.3 ERP-301, "Dose Assessment Coordinator" (PBAPS) 6.4.4 ERP-300, "Dose Assessment Coordinator" (LGS) 6.4.5 ERP-315, "Operation of the Dose Assessment Computer" (PBAPS) 6.4.6 ERP-316, "Operation of the Dose Assessment Computer" (LGS) 6.4.7 ERP-325, "Shift Dose Assessment Personnel" (PBAPS) 6.4.8 ERP-C-1300, "Dose Assessment Team" 6.5 COMMITMENT ANNOTATIONS 6.5.1 CM-i, Letter to NRC, 02/11/86, T01935 (section 1.4) 6.5.2 CM-2, Letter to NRC dated 8/8/86, in response to NRC PB Insp. Rpt.
86-06106, T03210 (section 1.0)
ERP-326, Rev.
1 Page 6 of 11 ATTACHMENT 1 AUTO MODE A (Page 1 of 3)
- 1.
From Mode A or Auto A Menu Choose;
- a.
F3 --
Auto Mode A - Initiate automatic data collection
- 2.
Choose DBA from Accident Menu
- 3.
Answer the following prompts:
- a.
Enter the time of the release in military format (Current system time = <ENTER> = 07:42)
- b.
Enter the date of the release in standard format (Current system time = <ENTER> = 09/23/93):
- c.
Night or Day?
(N or D,
<ENTER>
D)
- d.
Adverse Weather or Normal Weather?
(A or N,
<ENTER> = N) :
- e.
Enter estimated release duration.
If unknown released duration, use default value (default is 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />).
(00:01 to 999:00,
<ENTER> = 4:
0):
NOTE:
TO USE AUTO MODE A THE FOLLOWING PROMPT MUST BE ANSWERED "Y",
OTHERWISE, YOU WILL BE PROMPTED TO SWITCH TO FAST MODE A.
(AUTO DATA COLLECTION CANNOT HAPPEN FOR A RELEASE THAT HAS NOT YET OCCURRED).
- f.
Has the release been in progress?
(Y or N, <ENTER> = N):
Y
- g.
Time the release has been in progress.
(Format is (HH:MM),
<ENTER> = 0:
0):
- h.
Has the reactor been scrammed?
(Y or N,
<ENTER> = N):
Y
- i.
When did the reactor reach 0% power?
- 1. Date = <ENTER> = 09/23/93:
- 2.
Time in 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> format = <ENTER> = (00:00)
Time since reactor shutdown will be displayed
- j.
Do you wish the model to account for wet disposition?
(Y or N,
<ENTER> = N):
Select appropriate tower/sensor data from this table.
ERP-326, Rev.
1 Page 7 of 11 ATTACHMENT 1 AUTO MODE A (Page 2 of 3)
NOTE:
METEOROLOGICAL AND RADIOLOGICAL DATA FOR THE TIME IN QUESTION WILL BE DISPLAYED.
ANY OF THIS DATA CAN BE EDITED BY THE USER.
ANY DATA MARKED WITH A CHECK MARK TO THE LEFT IS BAD DATA AND WILL NOT BE USED BY THE SYSTEM.
THE BAD DATA MARK CAN BE REMOVED BY PRESSING ALT-B WITH THE CURSOR ON THAT DATA.
THIS WILL CAUSE THE PROGRAM TO USE THAT DATA AS GOOD DATA.
DATA MARKED WITH AN "R" IS DATA THAT IS OUT OF RANGE.
THIS DATA CANNOT BE USED BY THE PROGRAM AND MUST BE CORRECTED.
The Auto Mode A Screen is then displayed:
- j.
View data and press F10 to continue.
- 1.
If any of the data points are out of range, a warning will be displayed at the bottom of the screen and the cursor will go to the bad data point.
This situation must be corrected before continuing.
- 2.
If any meteorological data points are displayed as "bad data",
the backup sensor will be used by the program.
If radiological data for the release point in question is bad, or if all of a particular met quantity is bad, Auto Mode A will cease and the operator will be forced to use Fast Mode A or Mode A.
- k.
Choose release point from release point menu.
- 1. Met Data that will be used will be displayed.
- 1. At breakdown menu, select Fl "Isotopic Breakdown Unknown".
- m.
When projecting dose assessment for LGS, you will be prompted for Iodine Concentration calculations from iodine/noble gas ratio.
Enter 'Y' (default value).
- n.
When projecting dose assessment for LGS, you will be prompted if release is processed through SGTS.
IF yes, THEN provide efficiency and supply information for RERS filters.
- o.
IF no for SGTS, THEN you will be prompted to answer "Is this release from drywell atmosphere, suppression chamber atmosphere, or other?".
(D, S,
0, UNKNOWN 0 <ENTER> = 0):
ERP-326, Rev.
1 Page 8 of 11 ATTACHMENT 1
AUTO MODE A (Page 3 of 3)
NOTE:
DEPENDING ON RELEASE POINT AND ANSWERS TO THESE PROMPTS, SEVERAL PROMPTS WILL APPEAR CONCERNING THE RELEASE PATH.
THESE ARE USED TO DETERMINE THE NOBEL GAS TO IODINE RATIO AND ALL HAVE "UNKNOWN" AS AN OPTION.
THIS PROMPT IS AN EXAMPLE:
IS THIS RELEASE FROM DRYWELL ATMOSPHERE, SUPPRESSION CHAMBER ATMOSPHERE, OR OTHER?
(D, S,
0, UNKNOWN = 0 <ENTER> = 0)
- 1. Would you like an automatic dump to the printer?
(Y or N, <ENTER> = Y) :
Output will be produced designated location.
- 2.
Will this be a simultaneous release?
(Y or N, <ENTER> = N):
ERP-326, Rev.
1 Page 9 of 11 ATTACHMENT 2 FAST MODE A
- 1.
Select Fl, Fast Mode A, from the Command Menu.
- 2.
Ensure appropriate device is selected for printer output.
- 3.
Make appropriate printout selection.
- 4.
IF a release is in progress from more than one release point, THEN enter a "Y" after the prompt, "Will this be a simultaneous release?"
AND repeat until data for all release points has been entered.
- 5.
IF specific receptor data is desired, T-HEN select the appropriate receptor from the Receptor Display Menu OR select Q to leave the menu.
- 6.
IF another dose projection is desired, T-HEN respond "Y" to the prompt OR respond "N" to leave the system.
ERP-326, Rev.
1 Page 10 of 11 ATTACHMENT 3 METEOROLOGICAL PARAMETER RESOURCES (Listed in order of preference)
- 1.
Main Control Room Instrument Panels (Control Room Only)
- 2.
National Weather Service A.
PENN State NWS:
9-1-814-237-1152 or 9-1-800-697-0010 B.
Mount Holly NWS:
9-1-609-261-6604 Obtain the following meteorological parameters:
Wind Direction (WD30)
Wind Speed (WD30)
Cloud Cover (CLCVR)
Cloud Ceiling (CLCEG)
Ambient Temperature Precipitation deg. az.
knots tenths ft deg.
F in/hr Forecast:
Time NWS
Contact:
ERP-326, Rev.
1 Page 11 of 11 ATTACHMENT 4 DOSE ASSESSMENT TURNOVER SHEET Turnover of dose assessment responsibility from one Dose Assessment team/location to another Dose Assessment team/location should include the transmittal of any available information listed below:
- 1. Affected Station Unit
- 2. Contact person:
a) Dose Assessment Coordinator (DAC)
PBAPS Phone:
(81:280),807:4644,4645 LGS Phone:
Name b) Dose Assessment Team Leader (DATL)
(257), 803:3843 Name Phone
- 3. Time of reactor trip/scram
- 4. Plant Status
- 5. Release Point
- 6.
Start time of release
- 7. Estimated duration of release
- 8. Method(s) used to calculate doses E Auto-A D Fast-A D Mode A
- 9. Design Basis Accident 10.Site evacuation assembly area 1l.Results of dose calculations, based on dose projection, Protective Action Recommendation.
Completed By Date/Time
Effective Date:
ERP-360, Rev.
4 Page 1 of 12 KLM/mes EXELON NUCLEAR LIMERICK GENERATING STATION EMERGENCY RESPONSE PROCEDURE ERP-360 ADJUSTMENT OF WIDE RANGE GAS MONITOR CONVERSION FACTORS 1.0 RESPONSIBILITIES 1.1 The TSC Dose Assessment Coordinator (DAC) shall coordinate the changing, if necessary, of the Wide Range Gas Monitor (WRGM) conversion factors.
1.2 The EOF Dose Assessment Team Leader (DATL) shall direct the TSC Dose Assessment Team to change if necessary, the WRGM conversion factors.
1.3 The Emergency Director (ED) shall be apprised of any changes to the WRGM conversion factor and any impact the changes may have on Emergency Action Levels (EALs) or Protective Action Recommendations.
1.4 The Emergency Response Manager (ERM) shall be apprised of any changes to the WRGM conversion factor and any impact the changes may have on EALs or Protective Action Recommendations.
2.0 INITIAL ACTIONS 2.1 The TSC DAC while activated, shall:
2.1.1 Determine a new WRGM conversion factor approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, 24
- hours, 2 days, and 4 days following reactor shutdown or until termination of the release.
2.1.1.1 IF the suspected source term is a LOCA, (Major Fuel Damage-D/W Rad monitor
>100 R/mr)
THEN refer to ERP-360-1 to calculate AND document the new WRGM conversion factors.
ERP-360, Rev.
4 Page 2 of 12 2.1.1.2 IF the suspected source term is not a
- LOCA, (Minor Fuel Damage-D/W Rad monitor
<100 R/mr)
THEN obtain an isotopic analysis AND refer to ERP-360-2 to calculate and document the new WRGM conversion factors.
2.1.2 Inform the ED of the need to change the WRGM conversion factors and any impact the changes may have on EALs or Protective Action Recommendations.
2.1.3 Upon concurrence from the ED, request that a Communicator notify the Shift Supervisor in the Control Room of the planned action.
2.1.4 Direct I&C to apply the new calibration factors to the mid and high-range channels as follows:
NOTE The Supervisory Key Switch for the WRGM RM-23 Indicating Controller RIX-026-076 is located to the right of the RM-23.
2.1.4.1 Obtain the key for the supervisory key switch for RIX-026-076, located on panel 00-C691.
2.1.4.2 Select the Supervisory Position of the key switch for the WRGM, RY-026-076.
2.1.4.3 At RIX-026-076, press CH2.
2.1.4.4 At RIX-026-076, press 011, THEN press ITEM.
2.1.4.5 At RIX-026-076, enter the new mid-range value of the conversion factor.
2.1.4.6 At RIX-026-076, press ENTER.
2.1.4.7 At RIX-026-076, press CH2.
2.1.4.8 At RIX-026-076, press CH3.
2.1.4.9 At RIX-026-076, enter 011, THEN press ITEM.
2.1.4.10 At RIX-026-076, enter the new high-range value of the conversion factor.
ERP-360, Rev.
4 Page 3 of 12 2.1.4.11 At RIX-026-076, press ENTER.
2.1.4.12 At RIX-026-076, press CH3.
2.1.4.13 Place key switch on Panel 00-C691 to the NORMAL position and remove key.
2.1.4.14 Return the key.
2.2 The EOF DATL shall upon turnover from the TSC:
2.2.1 Determine a new WRGM conversion factor approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, 24
- hours, 2 days, and 4 days following reactor shutdown or until termination of the release.
2.2.1.1 IF the suspected source term is a LOCA, (Major Fuel Damage-D/W Rad monitor >100 R/mr)
THEN refer to Appendix 1 to calculate and document the new WRGM conversion factors.
2.2.1.2 IF the suspected source term is not a
- LOCA, (Minor Fuel Damage-D/W Rad monitor
<100 R/mr)
THEN obtain an isotopic analysis and refer to ERP-360-2 to calculate and document the new WRGM conversion factors.
2.2.2 Inform the ERM of the need to change the WRGM calibration factors and any impact the changes may have on EALs or PAG Recommendations.
2.2.3 Upon concurrence from ERM, request the a Communicator notify the Shift Supervisor in the Control Room of the planned action.
3.0 CONTINUING ACTIONS 3.1 The EOF DATL shall:
3.1.1 Upon termination of the release, evaluate the applicability of the current conversion factors.
4.0 FINAL CONDITIONS 4.1 Upon termination of the emergency, I&C shall return WRGM conversion factors to normal setting.
ERP-360, Rev.
4 Page 4 of 12 5.0 ATTACHMENTS AND APPENDICES 5.1 ERP-360-1, Mid and High-Range Conversion Factor Adjustment Worksheet for a Suspected LOCA 5.2 ERP-360-2, Mid and High-Range Conversion Factor Adjustment Worksheet for Non-LOCA Source Terms 6.0 SUPPORTING INFORMATION 6.1 Purpose 6.1.1 The purpose of this procedure is to provide instructions in the determination and the application of WRGM conversion factors during an emergency as a function of time after reactor shutdown.
6.2 Criteria For Use 6.2.1 A release of significant magnitude has occurred resulting in the activation of the mid or high range channel of the WRGM.
6.3 Special Equipment None 6.4 References 6.4.1 G. A. Technologies, INC, Calibration Report RD-72 Wide Range Gas Monitor High and Mid-Range Detectors, E-255-961 (Rev.
- 2) 6.4.2 LGS RD-72 Transfer Calibration Procedure (0366-9010) 6.4.3
- Memo, L.
G. Pyrih to R.
H. Logue, Limerick Generating Station Units I and 2,
Subject:
Wide Range Accident Monitor Calibration Factors, dated Aug.
27, 1984.
6.5 Commitment Annotation None
ERP-360, Rev.
4 Page 5 of 12 MID AND HIGH-RANGE CONVERSION FACTOR ADJUSTMENT WORKSHEET FOR A SUSPECTED LOCA Time after reactor shutdown (hrs)
Mid-range calibration factor (Determine from Figure 1):
Mid-range conversion factor =
cpm
[Lci/cc 1
Mid-range calibration factor A.
New Mid-range conversion factor =
for channel RE26076-1 JC i/cc cpm High-range calibration factor:
cpm (Determine from Figure 2) kC i/cc High-range conversion factor 1
High-range calibration factor New Mid-range conversion
_Ci/cc for channel RE26076-3 cpm Apply Value A to channel item 11 of RE26076-I Apply Value B to channel item 11 of RE26076-3 Date:
Time:
B.
(
i(
ERP-360, Rev.
4 Page 6 of 12 Appendix ERP-360-1 FIGURE 1 Mid-Range Detector Response Vs.
Time I
r I
" 1.
AI.
I
£9 b
ma
- B g
i...Li
I I II Aj I1I
/
ERP-360, Rev.
4 Page 7 of 12 Appendix ERP-360-1 FIGURE 2 Mid-Range Detector
Response
Vs.
Time
ý-
r,
(
ERP-360, Rev.
4 Page 8 of 12 APPENDIX ERP-360-2 Mid and High-Range Conversion Factor Adjustment Worksheet for Non-LOCA Source Terms INSTRUCTIONS Do one worksheet each for the mid-range and high-range channels.
Complete the worksheets as follows:
- 1.
Fill in the appropriate information at the top of the worksheet.
- 2.
List the suspected or actual isotopic makeup of the release in the first column.
- 3.
Provide the concentration or curie amount in the second column.
- 4.
Determine the fractional abundance of each isotope in the source term.
The sum of all isotopic abundances should approximately equal 1.
- 5.
Obtain the values for B, C, and D from the Table of Isotopes, Radiological Health Handbook or any acceptable reference document.
- 6.
Obtain the value for E from Figure 3 and Figure 4 for the mid range and high-range channel respectively.
Use the gamma curve for each gamma emitted and the beta curve for each beta emitted.
- 7.
Determine the isotopic conversion factor for each emission (F) by multiplying column D times E.
- 8.
Calculate the expected yield for each emission (G) by multiplying columns A times F times Cf.
NOTE CF VALUES ARE DETECTOR CORRECTION FACTIONS OBTAINED FROM TRANSFER CALIBRATION PROCEDURE (0366-9010).
THE VALUE IS 1.29 FOR BETA AND 1.07 FOR GAMMA.
- 9.
Calculate the Total Expected Yield for the Source Term (CPM/uCi/cc) by adding all expected yields for each emission in column G.
- 10.
Calculate the new conversion factor for each channel by taking the reciprocal of the Total Expected Yield.
- 11.
Apply the new conversion factor determined in step 9 to channel item 11 for the channel of interest.
ERP-360, Rev.
4 Page 9 of 12 APPENDIX ERP-360-2 DATE:
Mi TIME:
Time after reactor Shutdown:
d and High-Range Calibration Factor Adjustment Worksheet 131 on-.,77Soure Trms (See notes on tollowing page)
MID-RANGE P T C T-T - D1\\Tr2-'
Source Term Radiations Produced cpm c
uCi/cc uCi/cc Intensity from Graph D x E Expected cf-beta
= 1.29 Yield cf-gamma
= 1.07 A x F x CF E(MeV)
B or No.
per Concentration Dis Isotope or Activity A
B C
D E
F G
t t
t
+/-
F
+
4 t
-t
+/-
1-F
+/-
4 i
I
+
i
-I I4 r
r 1-1-
1
+
4 F
F
+
+
4 t
F
+/-
+
F
- 4.
4 F
F F
+
+
F 4-4 1
= 1 ENTER THE RECIPROCAL OF THE TOTAL EXPECTED YIELD IN CHANNEL ITEM 11:
1 TOTAL EXP.
YIELD uCi/cc CPM
(
(
F F
+/-
- _____
I
ERP-360, Rev.
4 Page 10 of 12 APPENDIX ERP-360-2 NOTES A
Fractional abundance of each isotope in source term.
The sum of all isotopes should approximately equal 1.
B,C,D Obtain these values from the Table of the Isotopes or the Radiological Health Handbook.
E Obtain these values as a function of beta or gamma energy from Figure 1 (Mid-range detector) and Figure 2 (High-range detector) of this Appendix.
F D times E G
=
A times F times Cf Cf These values are actual values obtained from the transfer calibration procedure (0366-9010) and are 1.29 for betas and 1.07 for gammas.
ERP-360, Rev.
4 Page 11 of 12 APPENDIX ERP-360-2 FIGURE 3
- 7. V.-.
KZJfL L }L...L.
S... W
+...
1 Xe-133 -i 4-;---
KFG*-- GAMMA --
"--+ 1
-ý! ;=-)'BETA -- --
7.;..
L..++_4_
1L S -_
L: [7 T--" -7:
+---
+,
T 7 -:
, + +7 7
20 '0 200 77 -47,-.
i1Th1
!LLI:
1000 2000 l-H""Tl 4LI 500 ENERGY (keV) (E/3max.)
Fig. 3.
Mid-range detector energy response curve 200 100
+
ih~:
L-;--l--,
a C
,"3 <t Z cc CU 00,,
S-E LUJ 20 10 5
2 1
50 4°- - -.....-..-
-Th-*-"tI 100 I:--
iZ
5000 1;i3
-r- --r 77-
ERP-360, Rev.
4 Page 12 of 12 APPENDIX ERP-360-2 FIGURE 4 iI:j'jIiiI. :jii.I I I
GAMMA.--.-- --
I I i Ii i t ! i, I:
-r-rr--i------
-r
- 47 7
I.
BETA T
- i
-i i -i5-'
I$
- nt
- 1'-T.'__-_._ 7_1
~N_~w-~
.j
- t2Ti:\\17 4 1:
-- Z4 :2474::.
7-4
- 77
.*_._[
7 z f
,[ {
-9 -
zz
444 TTTTF..
= =
=
=
F
-i+-----4--- 1*
200 500 1000 I-2000
..q _j 5000 ENERGY (kev) (E/
max.)
Fig. 4.
High-range detector energy response c.urve 500 200 Xe-13.
100 z
Lu ZcZ 0
LL CDj L<4<
N<
z CO~
in 5-C.3 ~20 z
10 5
50 100
- ---+------F-----R-----+
75Z El:
EU
_7::
- J.
- i*.
l i
ATTACHMENT 2 LIMERICK GENERATING STATION, UNITS 1 & 2 Docket Nos.
License Nos.
50-352 50-353 NPF-39 NPF-85 EMERGENCY RESPONSE PROCEDURES REPORT INDEX
PAGE PROCEDURE INDEX REPORT; LIMERICK GENERATING STATION DOC PROC FAC TYPE TYPE LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP PROCEDURE NUMBER ERP-C-1I000 ERP-C-1000-1 ERP-C-1000-2 ERP-C-1000-3 ERP-C-1000-4 ERP-C-1000-5 ERP-C-1100 ERP-C-1200 ERP-C-1200-1 ERP-C-1200-2 ERP-C-1200-3 ERP-C-1200-4 ERP-C-1210 ERP-C-1250 ERP-C-1250-1 ERP-C-1250-2 ERP-C-1250-3 ERP-C-1250-4 ERP-C-1300 ERP-C-1300-1 ERP-C-1300-2 ERP-C-1300-3 ERP-C-1300-4 ERP-C-1300-5 ERP-C-1300-6 ERP-C-1300-7 ERP-C-1300-8 ERP-C-1300-9 ERP-C-1310 ERP-C-1310-1 ERP-C-1310-2 ERP-C-1310-3 ERP-C-1310-4 ERP-C-1320 ERP-C-1320-1 ERP-C-1320-2 ERP-C-1320-3 ERP-C-1400 CURR REV NBR 0006 0004 0003 0000 0000 0000 0003 0011 0000 0000 0000 0000 0002 0004 0000 0002 0000 0000 0010 0004 0000 0004 0000 0001 0002 0000 0000 0001 0003 0000 0000 0000 0000 0007 0002 0001 0002 0005 TITLE EMERGENCY OPERATIONS FACILITY (EOF)
ACTIVATION/DEACTIVATION EOF ACTIVATION CHECKLIST EOF DEACTIVATION CHECKLIST EOF BUSINESS HOURS FIRST RESPONDER CHECKLIST EOF AFTER HOURS FIRST RESPONDER CHECKLIST MIMIMUM STAFFING POSITIONS NECESSARY TO ACTIVATE THE EOF EOF STAFF AUGMENTATION INCORPORATED INTO ERP-C-1250 EMERGENCY REPSONSE MANAGER EMERGENCY RESPONSE MANAGER TURNOVER/BRIEFING FORM PROTECTIVE ACTION RECOMMENDATION WORKSHEET CANCELLED ERM PAR DELIVERY CHECKLIST MINIMUM STAFFING POSITIONS NECESSARY TO ACTIVATE THE EOF ASSISTANT EMERGENCY RESPONSE MANAGER (AERM)
CANCELLED EMERGENCY PREPAREDNESS COORDINATOR/EOF EMERGENCY POWER INSTRUCTIONS EMERGENCY PREPAREDNESS COORDINATOR INSTRUCTIONS FOR ASPEN BACKUP NOTIFICATION SYSTEM EMERGENCY PREPAREDNESS COORDINATOR INSTRUCTIONS TO STOP STAFFING ENERGENCY PREPAREDNESS COORDINATOR INSTRUCTIONS FOR SYSTEM RESET EMERGENCY OPERATIONS FACILITY (EOF)
DOSE ASSESSMENT TEAM LEADER DOSE ASSESSMENT TEAM LEADER (DATL)
INITIAL ACTIONS DOSE ASSESSMENT TURNOVER LIST PROTECTIVE ACTION RECOMMENDATION WORKSHEET OFFSITE SAMPLE ANALYSIS REQUESTS DETERMINATION OF PROTECTIVE ACTION RECOMMENDATIONS (PARS)
DOSE ASSESSMENT GROUP MEMBER (DAGM)
INITIAL ACTIONS OBTAINING EPDS MET/RAD DATA USE OF MODE A/MODE B CDM OBTAINING MET DATA FROM NATIONAL WEATHER SERVICE EMERGENCY OPERATIONS FACILITY (EOF)
DOSE ASSESSMENT GROUP CANCELLED DOSE ASSESSMENT GROUP LEADER INITIAL ACTIONS CANCELLED OBTAINING MET DATA FROM NATIONAL WEATHER SERVICE CANCELLED OBTAINING EPDS MET/RAD DATA CANCELLED USE OF MODE A /
MODE B OF CDM CANCELLED EMERGENCY OPERATIONS FACILITY (EOF)
FIELD SURVEY GROUP LEADER FIELD SURVEY GROUP LEADER INITIAL ACTIONS FIELD SURVEY GROUP LEADER TURNOVER SHEET FIELD SURVEY GROUP LEADER DATA SHEET ENGINEERING SUPPORT TEAM EFFECTIVE RESP SYSTEM DATE GROUP NBR 06/25/01 06/25/01 04/21/99 04/21/99 04/21/99 06/25/01 09/14/94 06/25/01 LWE 09/14/94 10/24/95 04/03/00 03/30/01 10/24/95 06/25/01 09/14/94 05/11/01 09/14/94 09/14/94 08/29/00 06/25/01 09/23/94 03/30/01 09/23/94 11/02/98 06/25/01 03/26/97 03/26/97 09/12/97 03/26/97 03/26/97 03/26/97 03/26/97 03/26/97 08/29/00 04/10/98 03/26/97 08/29/00 06/25/01 2/13/2002
PAGE 2
PROCEDURE INDEX REPORT:
LIMERICK GENERATING STATION DOC PROC FAC TYPE TYPE LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP PROCEDURE NUMBER ERP-C-1400-1 ERP-C-1410 ERP-C-1410-1 ERP-C-1410-2 ERP-C-1410-3 ERP-C-1410-4 ERP-C-1410-5 ERP-C-1410-6 ERP-C-1500 ERP-C-1500-1 ERP-C-1500-2 ERP-C-1900 ERP-C-1900-1 ERP-C-1900-2 ERP-C-1900-3 ERP-C-1900-4 ERP-C-1900-5 ERP-101 ERP-101 BASES ERP-106 ERP-110 ERP-120 ERP-140 ERP-200 ERP-200-1 APP ERP-200-2 APP ERP-230 ERP-230 ERP-230 ERP-230 ERP-230 ERP-300 ERP-300 ERP-300 ERP-300 ERP-300 ERP-300 ERP-300 ERP-300 ERP-300 ERP-300 ERP-300 ERP-300 ERP-300 ERP-300 ERP-300 ERP-316 APPENDIX APPENDIX APPENDIX APPENDIX APPENDIX APPENDIX APPENDIX APPENDIX APPENDIX APPENDIX APPENDIX APPENDIX APPENDIX APPENDIX APPENDIX APPENDIX APPENDIX APPENDIX 1
2 3
4 1
2 3
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10 11 12 13 14 CURR REV NBR TITLE 0002 0002 0000 0001 0001 0000 0002 0002 0006 0001 0001 0004 0000 0002 0002 0002 0002 0012 0003 0003 0033 0007 0010 0015 0012 0000 0014 0000 0000 0000 0000 0023 0000 0000 0001 0000 0000 0000 0000 0000 0001 0000 0000 0000 0000 0000 0001 ENGINEERING SUPPORT TEAM CHECKLIST CORE DAMAGE ASSESSMENT RADIOLOGICAL DATA HYDROGEN CONCENTRATION DATA CONTAINMENT RADIATION MONITOR DATA METAL WATER REACTION CANCELLED PERCENT OF FUEL INVENTORY AIRBORNE IN THE CONTAINMENT VS.
APPROXIMATE SOURCE AND DAMAGE ESTIMATE PROCEDURES FOR ESTIMATING FUEL DAMAGE BASED ON MEASURED 1-131 AND XE-133 CONCENTRATIONS LOGISTIC SUPPORT TEAM MESSAGE AND INFORMATION INSTRUCTIONS HELICOPTER LANDING INFORMATION RECOVERY PHASE IMPLEMENTATION RECOVERY PHASE IMPLEMENTATION FLOW CHART PEACH BOTTOM ATOMIC POWER STATION RECOVERY ACCEPTANCE CHECKLIST LIMERICK GENERATING STATION RECOVERY ACCEPTANCE CHECKLIST RECOVERY PLAN OUTLINE ASSESSMENT CONSIDERATIONS CLASSIFICATION OF EMERGENCIES LGS EAL TECHNICAL BASIS MANUAL WRITTEN
SUMMARY
NOTIFICATION EMERGENCY NOTIFICATION STATION EVACUATIONS STAFFING AUGMENTATION EMERGENCY DIRECTOR (ED)
RESPONSE
EMERGENCY DIRECTOR FORMS DOSE ASSESSMENT DATA SHEET OPERATIONS SUPPORT CENTER (OSC)
DIRECTOR OSC -
EMERGENCY COMMUNICATIONS EQUIPMENT CHECK LIST OSC DIRECTOR ACTIVATION CHECK-OFF LIST OPERATIONS SUPPORT CENTER FACILITY ACCOUNTABILITY LOG OSC DIRECTOR ACTIVATION DOSE ASSESSMENT COORDINATOR DOSE ASSESSMENT TEAM ACTIVATION DOSE ASSESSMENT TEAM CHECK-OFF LIST TURNOVER OF DOSE ASSESSMENT RESPONSIBILITIES DOSE ASSESSMEMT DATA SHEET USE OF MESOREM, JR, AUTO MODE A OBTAINING RADIOLOGICAL DATA OBTAINING MET DATA FROM PLANT MONITORING SYSTEM (PMS)
OBTAINING METEROLOGICAL DATA FROM NATIONAL WEATHER SERVICE PROTECTIVE ACTION WORKSHEET USE OF NORTH STACK DOSE RATE TO ESTIMATE RELEASE SOURCE TERM OPERATION OF IBM PS/2 MODEL L4OSX LIMERICK LIQUID RELEASE DOSE CALCULATIONS DOSE ASSESSMENT SELF-CHECK STABILTIY CLASS DETERMINATION OPERATION OF THE DOSE ASSESSMENT COMPUTER (CM-3)
EFFECTIVE RESP SYSTEM DATE GROUP NBR 11/02/98 09/09/98 09/14/94 09/09/98 09/09/98 09/09/98 06/01/01 06/25/01 04/14/00 10/24/95 10/24/95 11/02/98 06/28/93 04/02/98 04/02/98 04/02/98 12/28/99 02/08/02 02/08/02 11/22/95 06/12/01 12/07/01 12/07/01 12/07/01 12/07/01 06/20/00 04/14/00 04/14/00 04/14/00 04/14/00 04/14/00 01/31/02 04/03/00 04/03/00 06/19/00 04/03/00 04/03/00 04/03/00 04/03/00 04/03/00 06/19/00 04/03/00 04/03/00 04/03/00 04/03/00 04/03/00 02/15/02 LWE LWE LWE LWE LWE LWE LWE LWE LWE 2/13/2002
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PROCEDURE INDEX REPORT:
LIMERICK GENERATING STATION DOC PROC FAC TYPE TYPE PROCEDURE NUMBER CURR REV NBR TITLE EFFECTIVE RESP SYSTEM DATE GROUP NBR LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG LG 02/15/02 11/14/94 01/31/02 11/10/94 LWE LWE LWE 02/15/02 LWE 11/10/94 LWE 07/24/01 LWE 09/28/98 LWE 09/28/98 LWE 09/28/98 LWE PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC PROC ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP ERP END OF REPORT **
ERP-326 ERP-330 ERP-340 ERP-350 ERP-360 ERP-370 ERP-400 ERP-4 10 ERP-420 ERP-430 ERP-440 ERP-500 ERP-500 ERP-500 ERP-500 ERP-500 ERP-500 ERP-500 ERP-500 ERP-600 ERP-620 ERP-630 ERP-640 ERP-650 ERP-660 ERP-700 ERP-800 ERP-800 ERP-800 ERP-800 ERP-800 0001 0000 0009 0003 0004 0001 0013 0002 0002 0002 0002 0016 0000 0000 0000 0000 0000 0000 0000 0013 0002 0004 0008 0011 0007 0016 0020 0000 0001 0001 0001 SHIFT DOSE ASSESSMENT PERSONNEL (SDAP)
USE OF NORTH STACK-DOSE RATE TO ESTIMATE RELEASE SOURCE TERM CANCELLED INCORPORATED INTOERP-300 APP.1O FIELD SURVEY GROUP RADIOACTIVE LIQUID RELEASE CANCELLED ADJUSTMENT OF WIDE RANGE GAS MONITOR CONVERSION FACTORS USE OF RMMS FOR DOSE ASSESSMENT CANCELLED CHEMISTRY SAMPLING AND ANALYSIS TEAM SAMPLE PREPARATION AND HANDLING OF HIGHLY RADIOACTIVE LIQUID SAMPLES SAMPLE PREPARATION AND HANDLING OF HIGHLY RADIOACTIVE PARTICULATE FILTERS AND IODINE CARTRIDGES SAMPLE PREPARATION AND HANDLING OF HIGHLY RADIOACTIVE GAS SAMPLES OFF-SITE ANALYSIS OF HIGH ACTIVITY SAMPLES SECURITY TEAM SECURITY TEAM ACTIVATION SECURITY TEAM STAFFING GUIDELINES STAFFING FOR SITE EVACUATION SECURITY EVACUATION GUIDANCE SECURITY TEAM LEADER CHECK-OFF LIST EMERGENCY ASSEMBLY AREAS FACILITY ACCOUNTABILITY LOG TECHNICAL SUPPORT CENTER HEALTH PHYSICS TEAM PLANT SURVEY GROUP CANCELLED -
NO REPLACEMENT VEHICLE AND EVACUEE CONTROL GROUP EMERGENCY RESPONSE FACILITY HABITABILITY ENTRY FOR EMERGENCY REPAIR AND OPERATIONS DISTRIBUTION OF THYROID BLOCKING TABLETS TECHNICAL SUPPORT TEAM MAINTENANCE TEAM TASK BRIEFING/DEBRIEFING SHEET MAINTENANCE TEAM ACTIVATION TECHNICAL SUPPORT CENTER ACTIVATION OFFSITE SIRENS ACTIVATION (REF.
6.5.1) 03/29/95 04/14/00 04/14/00 04/14/00 04/14/00 04/14/00 04/14/00 04/14/00 04/14/00 01/31/02 05/02/95 01/31/02 04/17/99 01/31/02 01/31/02 02/15/01 12/15/00 04/14/00 07/24/01 12/15/00 12/15/00 1
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LWE LWE LWE LWE LWE LWE LWE LWE LWE LWE APPENDIX APPENDIX APPENDIX APPENDIX APPENDIX APPENDIX APPENDIX APPENDIX APPENDIX APPENDIX APPENDIX 2/13/2002