ML20151W016
| ML20151W016 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 01/09/1986 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20151V997 | List: |
| References | |
| CON-#186-024, CON-#186-24 OL, PROC-860109, NUDOCS 8602110468 | |
| Download: ML20151W016 (32) | |
Text
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. Paga 1 of 5 Ravision 48 01/09/86
$. LIMERICK GENERATING STATION 3 $ f / 4Q QQ C)20 EMERGENCY PLAN PROCEDURE INDEX PROCEDURE REV. DATE SIGNED DATE OF LAST NUMBER NO. TITLE BY SUPER. PERIODIC REVIEW EP-101 4 Classification of 03/25/85 10/26/84 Emergencies EP-102 9 Unusual Event Response 09/27/85 10/26/84 EP-103 12 Alert Response 09/27/85 10/26/84 EP-104 11 Site Emergency Response 09/27/85 10/26/84 EP-105 11 General Emergency Response 09/27/85 10/26/84 EP-106 4 Written Summary 04/01/85 10/26/84 Notification EP-110 6 Personnel Assembly and 03/14/85 10/26/84 Accountability EP-120 3 Site Emergency Coordinator 04/01/85 10/26/84 EP-201 4 Technical Support Center 03/29/85 03/29/85
( (TSC) Activation EP-202 3 Operations Support Center 12/12/84 10/26/84 (OSC) Activation EP-203 5 Emergency Operations 04/01/85 04/01/85 Facility (EOF) Activation EP-208 4 Security Team 12/12/84 10/26/84 l
[ EP-210 3 Dose Assessment Team 12/12/84 10/26/84 l
EP-211 2 Field Survey Group 03/25/85 10/26/84 EP-220 CANCELLED EP-221 CANCELLED EP-222 CANCELLED O.M.APDOIIfE EP-230 5 Chemistry Sampling pRd '
0.0/26/84 l ; 01/44,38p
' La h h ell l Analysis Team %CO h j EP-231 10 Operation of Post- . /85 10/26/84 Accident Sampling Systems 7'..e , _0.8/0p/ '
3i (PASS) b_~'d'd .
%d4"d E I
}'I{.{' F 469 860121 p ADOCK 050003sp PDH
. . . . . . ~ . _ _ _ _. - _ _
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. . Pcgs 2 of 5 Rcvision 48 01/09/86 LIMERICK GENERATING STATION EMERGENCY PLAN PROCEDURE INDEX PROczoURE REV. DATE SIGNED DATE OF LAST NUMBER NO. TITLE BY SUPER. PERIODIC REVIEW EP-233 6 Retrieving and Changing 12/18/85 10/26/84 Sample Filters and Cartridges from the Containment Leak Detector During Emergencies EP-234 6 Obtaining Containment 12/18/85 10/26/84 Gas Samples from the Containment Leak Detector !' During Emergencies EP-235 5 Obtaining Reactor Water 03/14/85 10/26/84 Samples from Sample Sinks Following Accident Conditions EP-236 5 Obtaining Cooling Tower 03/14/85 10/26/84 Blowdown Line Water l
Samples Following Radioactive Liquid
, Release after Accident Conditions EP-237 7 Obtaining the Iodine / 03/28/85 10/26/84 Particulate and/or Gas Samples from the North Vent Wide Range Gas Monitor (NRCM)
EP-238 4 Obtaining Liquid Radwaste 12/12/84 10/26/84 Samples from Radwaste , Sample Sink Following Accident Conditions EP-240 CANCELLED EP-241 8 Sample Preparation and 03/14/85 10,'26/84 Eandling of Highly Radioactive Liquid Samples EP-242 5 Sample Preparation and 03/28/85 10/26/84 Handling of Highly Radioactive Particulate Filters and Iodine Cartridges EP-243 5 Sample Preparation and 12/12/84 10/26/84 Eandling of Highly Radioactive Gas Samples EP-244 3 Offsite Analysis of 03/12/85 10/26/84 High Activity Samples
~ 8 . _ . . . . . _ - . _ . . . . _ _ . . .
. Paga 3 of 5 Ravision 48 01/09/86 s LIMERICK GENERATING STATION -
EMERGENCY PLAN PROCEDURE INDEX PRocsuGRE REV. DATE SIGNED DATE OF LAST i NUMBER NO. TITLE BY SUPER. PERIODIC REVIEW l l t EP-250 2 Personnel Safety Team 12/12/84 10/26/84 EP-251 2 Plant Survey Group 12/12/84 10/26/84 EP-252 6 Search and Rescue /First 04/22/85 04/01/85 Aid Group EP-253 0 Personnel Dosimetry, 12/12/84 12/12/84 Bioassay, and Respiratory Protection ' Group EP-254 3 Vehicle and Evacuee 02/04/85 10/26/84
- Control Group EP-255 2 Vehicle Decontamination 12/12/84 10/26/84 EP-260 2 Fire and Damage 12/12/84 10/26/84 Control Team EP-261 2 Damage Re pair Group 12/12/84 10/26/84 EP-272 4 Philadelpsia Electric 02/04/85 10/26/84 Company Officials
, Phone List j EP-273 6 Limerick Station 01/02/86 01/02/86 i Supervision Call List EP-275 CANCELLED
- EP-276 6 Fire and Damage 04/22/85 04/22/85 Team Phone List j EP-277 8 Personnel Safety 01/09/86 01/09/86 l- Team Phone List EP-278 5 Security Team Phone 03/25/85 10/26/84 List l
EP-279 6 Emergency Operations 06/27/85 10/26/84 - Facility (EOF) Group l Phone List EP-280 7 Technical Support 06/27/85 10/26/84 Center Phone List l EP-282 5 Government and 04/22/85 04/22/85 Emergency Management Agencies Phone List EP-284 4 Company Consultants 01/22/85 10/26/84 l and Contractors Phone List EP-287 3 Nearby Public and 02/11/85 10/26/84 Industrial Users of Downstream Water t i 8
._. - - - _ - - _ - __ . - - - - - -. .. . . _ ___ . ~. . _
l
,' Paga 4 of 5 Ravision 48 01/09/86 .,
LIMERICK GENERATING STATION
\! '
EMERGENCY PLAN PROCEDURE INDEX l l PROCZDURE REV. DATE SIGNED DATE OF LAST i NUMBER NO. TITLE BY SUPER. PERIODIC REVIEW EP-291 6 Staffing Augmentation 04/18/85 10/26/84 EP-292 9 Chemistry Sampling and 12/18/85 04/22/85 Analysis Team Phone List EP-294 7 Dose Assessment Team 01/09/86 01/09/86 Phone List EP-301 1 Operating the Evacuation 12/12/84 10/26/84 Alarm and River Warning System i EP-303 3 Local Evacuation 52/12/84 12/12/84 EP-304 3 Partial Plant Evacuation 12/12/84 10/26/84 EP-305 5 Site Evacuation 03/25/85 10/26/84 EP-306 2 Evacuation of the 04/18/85 10/26/84
. Information Center EP-307 2 Reception and Orientation 12/12/84 10/26/84 of Support Personnel EP-312 5 Radioactive Liquid 01/09/86 01/09/86 l Release EP-313 2 Distribution of Thyroid 12/12/84 10/26/84 Blocking Tablets EP-314 1 Emergency Radiation 03/29/85 12/06/84 !
Exposure Guidelines and controls EP-315 6 Calculation of Offsite 01/09/86 01/09/66 l Doses During a (Potential) Radiological Emergency Using RMMS in the Manual Mode EP-316 3 Cumulative Population 04/01/85 10/26/84 and Near Real-Time Emergency Dose , Calculations for Airborne Releases
, Manual Method i EP-317 3 Determination of 03/25/85 10/26/84
! Protective Action i Recommendations j EP-318 2 Liquid Release Dese 04/01/85 04/01/85 Calculations Method for Drinking Water 4 4
,..' Pcgs 5 of 5 Ravicion 48 01/09/86 LIMERICK GENERATING STATION .
EMERGENCY PLAN PROCEDURE INDEX PROCEDURE REV. DATE SIGNED DATE OF LAST NUMBER NO. TITLE BY SUPER. PERIODIC REVIEW EP-319 2 Fish Ingestion Pathway 03/29/85 03/29/85 Dose Calculation EP-325 3- Use of Containment 02/27/85 10/26/84 Dose Rates to Estimate Release Source Term EP-330 4 Emergency Response 03/14/85 10/26/84 Facility Habitability EP-333 1 Adjustment of Wide 05/08/85 05/08/85 Range Gas Monitor Conversion Factors EP-401 2 Entry for Emergency 12/12/84 10/26/84 Repair and Operations EP-410 3 Recovery Phase 03/29/85 10/26/84 Implementation EP-500 2 Review and Revision 12/12/84 10/26/84 of Emergency Plan n { l l I __,6 ._ ,, _..
' l- -
. 3864000930 EP-277;Re;;8
, jek I
l l PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION . EMERGENCY PLAN IMPLEMENTING PROCEDURE l-l EP-277 PERSONNEL SAFETY TEAM PHONE LIST 1.0 PARTICIPANTS i ,' l.1 Personnel Safety Team Leader calls in Group Leaders. , 1.2 Plant Survey Group Leader calls the Health I Physics (EP) Unit Technical Assistant and the HP i Senior Technicians. 1.3 Health Physics (EP) Senior Technicians calls the I i HP technicians assigned to their shift. i NOTE: THE AREA CODE IS 215 UNLESS,OTHERWISE SPECIFIED. j 2.0 ACTIONS-IMMEDIATE ' 6, ! 2.1 Pedonnel Safety Team Leader:
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l EP-277, Rev. 8 h Page 2 of 5 7 MJR/jek 1 - 2.1.3 Personnel Dosimetry, Bioassay, and Respiratory - Protection Group Leader E Home Work Name .. QM%
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EP-277, Rev. 8 l Page 3 of 5 MJR/jek
] l NOTE THE FOLLOWING SHIFTS ARE THOSE IN EFFECT ON l 11/14/85. AS CHANGES OCCUR, THE SR. TECHNICIANS ;
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EP-277,'Rev. 8 Page 4 of 5 MJR/jek 1 Work l Name - Home . i 2.3.3 I l 1 ' 1 I I I I I i I I L . 3.0 ACTIONS-FOLLOW-UP 3.1 None required 4.0 APPENDICES l None f, 5.0 SUPPORTING INFORMATION ( Purpose ' 5.1 The purpose of this procedure is to provide guidelines and information to call in Personnel Safety Team Members. 5.2 Criteria for Use This procedure can be used when the Personnel
- Safety Team is activated or when additional people are needed.
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- EP-277, Rzv. 8
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Peg 2 5 of 5 g MJR/jek 5.3 Special Equipment 9 None 5.4 References None m e 1 l I l
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I, - 3864000940 EP-294 Rev. 7 Page.1 of 3 l
- JR/mc !
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, PHILADELPHIA ELECTRIC COMPANY / I l LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE
- EP-294 DOSE ASSESSMENT TEAM PHONE LIST 1.0 PARTICIPANTS I 1.1 Dose Asses,sment Team Leader _ shall be responsible to call
, in team members; and Field Survey Group Leader. j . 1.2 Field Survey Group Leader shall be responsible to obtain i group members.
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! 2.0 ACTIONS - IMMEDIATE 1 - 2.1 Dose Assessment Team Leader shall call people from the following list until appropriate positions are filled. ! 2.1.1 DOSE ASSESSM$NT TEAM LEADER (ONE) g Nahi'e ' Home Phone Work Phone 2.1.2 DOSE ASSESSMENT GROUP MEMBERS (3 MINIMUM) Name Home Phone Work Phone.'
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- EP-294
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Rev. 7 Page,2 of 3 l MJR/mc 2.1.3 FIELD SURVEY GROUP LEADER (ONE) ' l Name Home Phone Work Phone I 2.2 The field survey group leader shall obtain people from the Personnel Safety Team Leader until appropriate positions are fille,d (4 minimum). 2.2.1 The Field Survey Group Leader shall call the following individual (s) to obtain drivers for the Field Survey Group (4 minimum), or contact the Fire and Damage Team Leader (if available).
-WorkPho/.
Name Home Phone n_e 3.0 ACTIONS - FOLLOW-UP , ,
% \ ,_ , . , -
3.1 None rek'uired;" 4.0 APPENDICES None. 5.0 SUPPORTING INFORMATION 5.1 Purpose The purpose of this procedure is to provide guidelines and information to call in the Dose Assessment Team. 5.2 Criteria for Use l This procedure can be used when the Dose Assessment Team is to be activated or additional people are needed.
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EP-294 l- R2v. 7 Page 3 of 3 l 'MJR/mc 5.3 Special Equipment " None. 5.4 References None. , I i I s
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' 3864000950 EP-312 Rsv. 5 Page 1 of 3
. l MJR/ gs PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION -
EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-312 RADIOACTIVE LIQUID RELEASE 1.0 PARTICIPANTS 1.1 Emergency Director shall have the necessary actions performed to terminate the liquid release and evaluate the consequences of the release. l.2 Site Emergency Coordinator, *fj i < t ated, or Emergency Director shall direct the.*o 3p s - Actions of notification of downstre w 1 sampling, if requiren. { J /. oj],!Esandriver f .- fj 2.0 ACTIONS-IMMEDIATE ff 2.1 Eme rgencd t ht' hall: f yI' 2.1.1 i mediate steps necessary to terminate the _the river. I 2.1. 6 __he Chemistry Sampling and Analysis Team Leader r itiate sampling of the blowdown line in rdance with EP-236, Obtaining Cooling Tower B..owdown Line Water Samples Following Radioactive Liquid Release After Accident Conditions. 2.1.3 Direct the Dose Assessment Team Leader to estimate dose projections from the ingestion of drinking water and fish in accordance with EP-318, Liquid Release Dose Calculation Method for Drinking Water and EP-319, Fish Ingestion Pathway Dose Calculation, respectively. 2.2 SiteEmercf oc f at ; ,f - ated or Emergency Director e gg g .
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2.2.1 Based on results est-imated dose projections for downstream water sers.andQish ingestion, direct his communicator to n gJiepepartmentofEnvironmental T Resources. A.
. _ . _ _ . ._ . .o
. ~k EP-312 Rev. 5 Page 2 of 3 l -
MJR/rgs 2.2.2 If requested by the Department of Environmental
- Resources, direct his communicator to notify the downstream domestic water users in EP-287, Nearby Public and Industrial Users of Downstream Water.
2.2.3 If necessary, direct the HP&C Coordin1 tor to activate and request the Environmental Samplin' Coordinator to assign personnel to sample the river t ter near the intake for the following water compan s sampled at-the appropriate time based on th'eig t ted Transit Time for that location. 7 u 3 D The Estimated Transit Time'is the time required for the material rele sed 'tio reach the location of rest I f
/ Estimated Transit ation Time (hrs)
. Citizens Utilities Home 1.5 Water Company-Royersford
, B. Phoenixville Water 10 ! I C. Philadelphia Suburban 16 , Water ' D. Norristown Water 27 E. Philadelphia Belmont Water 50 l 2.2.4' Direct the Chemistry Sampling and Analysis Team Leader and/or Environmental Sampling Coordinator to transmit l the sampling results back to them. 3.0 ACTIONS-POLLOW-UP i None i i 1
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- EP-312 Rsv. 5 Paga 3 of 3 MJR/rgs l
4.0 - APPENDICES None 5.0 SUPPORTING INFORMATION 5.1 Purpose The purpose of this procedure is to provide guidelines for the actions to be taken when an uncontrolled liquid release of radicactive material occurs. 5.2 Criteria for Use 5.2.1 A liquid effluent release in excess of Technical Specification 3.11.1.1 or 3.11.1.2 has occurred. 5.3 Special Equipment None 5.4 References
, 5.4.1 Limerick Generating Station Emergency Plan ,
5.4.2 EP-236 Obtaining Cooling Tower Blowdown Line Water , Samples Following Radioactive Liquid Release After Accident Conditions 5.4.3 EP-318 Liquid Release Dose Calculation Method For Drinking Water 5.4.4 EP-319 Fish Ingestion Pathway Dose Calculation 5.4.5 EP-287 Nearby Public And Industrial Users Of i Downstream Water l 5.4.6 EROL Appendix 5.2A Radiological Dose Model-Liquid Effluents 5.4.7 10CFR Part 20 Appendix B 5.4.8 LGS Technical Specifications 1r -W % m -4 =4p- gyaw y a pp. g --we ha-- A e gy+ . * * +e. w. m
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i 3864000960 EP_315, Ray. 6
" , Page 1 of 14 l MJR/ C/ nip PHILADELPHIA ELECTRIC COMPANY / 4, LIMERICK GENERATING STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE EP-315 CALCULATION OF OFFSITE DOSES DURING A (POTENTIAL)
RADIOLOGICAL EMERGENCY USING RMMS IN THE MANUAL MODE s 1.0 PARTICIPANTS 1.1 The Shift Technical Advisor (STA) shall initiate dose calculations upon indication that an effluent monitor setpoint has been exceeded. ,. 1.2 The Shift Superintendent shall' evaluate the dose results, declare the appropriate EAL basedbon releases, and assist the Emergency Director in making protective action recommendations if. warranted. 1.3 The Dose Assessment Team Leader-(upon activation of the TSC, and/qr7the EOF) shall direct dose calculations, evaluate the results, and assist the Emergency Director with EAL declarations and protective' action recommendations. 1.4 The.RM-ll Operator in the TSC shall provide radiation release data to the Dose Assessment Team Leader and the RM-21A -Operator. 1.5 The RM'21A Operator shall use this data and meteorological information to generate offsite dose estimates using the RMMS computer. 1.6 The calculator shall assist the RM-21A Operator with data entry problems and periodically update the Status Board Keeper. l n m r n Em1t.LcF,. r ;c hA2 L c.v.y . bu:f 1 VLD DLY WHN RED (
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, 2.0 ACTIONS IMMEDIATE *
. e 2.1 Control Room Operations 4
2.1.1 Upon receiving an indication that an effluent release in excess of instantaneous Technical Specifications may have occurred, an offsite dose calculation shall be initiated by the STA to evaluate the release. He shall also request the .
, Chemistry Department to take an effluent at the point of release.
l INDICATORS OF EXCEEDED SETPOINTS - RM-ll ALARMS, AN RM-ll CHANNEL BLINKS, CHEMISTRY ANALYSES. FOR INDICATIONS BASED ON CHEMISTRY ANALYSES, GO DIRECTLY TO STEP 2.1.8. 2.1.2 The following channels on the RM-ll console provide an indication of a potential Technical Specification release if in a blinking red state and audibly alarming: North Vent South Vent , CHNL # DESCRIPTION CHNL # DESCRIPTION
, 4TE076 N STACK TOTAL EFFLUENT 2IE075 N STACK VENT EFL IOD 2IE185 S STACK VENT EFL IOD SIE075 N STACK VENT EFL IOD SIE185 S STACK VENT EFL IOD 3GE075 N STACK VENT EFL GAS 3GE185 S STACK VENT EFL GAS 6GE075 N STACK VENT EFL GAS 6GE185 S STACK VENT EFL GAS
**** 4TE076 WILL BLINK IN YELLOW
**** FOR AN IODINE ALARM, DO NOT DECLARE AN UNUSUAL EVENT UNTIL THE CHEMISTRY SAMPLE BECOMES AVAILABLE FOR EVALUATION.
**** COMMON CHANNELS: (2IE075, SIE075);
(3GE075, 6GE075); (2IE185, 5IE185); I (3GE185, 6GE185). l 2.1.3 When the RM-ll alarms or a specified channel L blinks in red, enter GRID I. 2.1.4 Access the channel (displayed by an alphanumeric code in an alarming / blinking state) by entering the following: L (Numeric portion of the code, SEL, 10 MIN TREND) l- If a North Vent (NV) channel has alarmed, enter (4076) i as the numeric code. l l^ i s wk-w - ~- -m n . -- ,s.m... ---, - _,
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EP-315, RGv. 6 Paga 3 of 14 MJR/MAC/ nip 2.1.5 Note the value units (in the , upper right hand corner of the RMMS console) > in the RMMS Log. This represents the concentration (uC1/cc) or release rate (uci/sec) at this channel. For simultaneous valid alarms on 2 common (same stack, same type), channels, take the average of the 2 concentrations. 2.1.6 Note process flow N. (in the upper middle of the RM-ll console) in the RMMS Log. Process flow A is used only when offsite power has been lost or the fans to the major enclosures have been turned off. UCI/SEC, OBTAINED FROM A NV CHANNEL, IN STEP 2.1.5, MUST BE CONVERTED TO UCI/CC: uCi/cc = uCi/sec (process flow) x (472) 2.1.7 The STA (RM-21A Operator) will logon to the RMMS-RM-21A system using the appropriate user name and password. 2.1.8 The RM-21A Operator will select the following options: 2.1.8.1 #6 - Emergency Dose Calculations, enter 2.1.8.2 #3 - Class A Dose Model, enter 2.1.8.3 #3 - All Manual Mode, enter THE OPERATOR SHALL GENERATE A HARD' COPY OF ALL INFORMATION. 2.1.9 Review the run control table. , Edit the table to reflect the Appropriate release point (s). (COPY) Release point 1 = North vent ! Release point 2 = South vent l Release point 4 = Hot Maintenance Shop Enter return to get back to "date of reactor trip". i i l l
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EP-315, Rav. 6 Page 4 of 14 MJR/MAC/ nip 2.1.10 Enter the following information: , 2.1.10.1 date of reactor trip - If the reactor has not tripped or scrammed, enter the start time of the release. 2.1.10.2 time of release -Enter start time of release or the beginning of the period to be evaluated. This time must be equal to or later than the time of reactor trip. EASTERN STANDARD TIME (EST) IS USED BY RMMS.- EST IS EQUAL TO DAYLIGHT SAVINGS TIME MINUS 1 HOUR. 2.1.10.3 remaining duration of release - The operator must request that the Shift Supervisor provide him with an estimated duration of release. If the duration cannot be estimated with confidence, enter 1 hour. (COPY) THE REMAINING DURATION OF RELEASE IS USED IN THE EAL TABLE WHICH PROVIDES THE OPERATOR WITH INFORMATION REGARDING CLASSIFICATION OF AN EMERGENCY BASED ON RADIOLOGICAL RELEASES. IT IS ALSO-USED IN THE PAG
SUMMARY
DISPLAY TO PROVIDE GUIDANCE ON WHEN PAGS MAY BE EXCEEDED. 2.1.10.4 isotopic release data
- 1. #2 - isotopic percent fraction (sum = 100.0) l 2. Select the desired isotopes based on ,
the following criteria: i ALARMING MONITOR
*If the reactor has not scrammed, enter the isotopic abundance for the month. This information is provided by the chemistry department. The chemistry sampling data must indicate the presence of isotopes having activities greater than the LLD values. Values less than or equal to LLD preclude the need to perform dose assessment.
*If the reactor has scrammed, enter the isotopic abundance per Appendix EP-315-1, which is also located in the EP-315 guide next to the RMMS console.
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EP-315, R2v. 6 Page 5 of 14 MJR/MAC/nlp CHEMISTRY ANALYSIS ,
- Utilize the isotopic mix used by chemistry to determine that the setpoint has been exceeded.
2.1.10.5 vent flow rate - see step 2.1.6, (COPY) 2.1.10.6 gross concentration of the release ALARM - see step 2.1.5 CHEMISTRY - taken from the analysis report Remember to convert (uCi/sec) to (uCi/cc) if necessary. 2.1.10.7 meteorological data - Obtain[the data from l the Meteorological Data-Log'ger and enter the
- sensor data which corresponds'.to the prompt.
(COPY) Refer to Appendix P-3,15-2 If Data-Logger is unavailable, the Operator shall obtain the data from'the following sources (listed,in order of preference):
./ >
- 1. o
- p ,C'ntrol Room refer ~ to 0 Strip App'endix Chart Recorders, EP-315-2 l 'Ndtion 1 Weather Service 2.1.11 Rev.iewl,the SiteiBoundary Emergency Action Level
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Display for..the' current action level, generate a hard copy,sandlinform the Shift Superintendent of the action level "
**** Repeat steps 2.1.8 through 2.1.11 for each release point
**** If this procedure is initiated due to an RM-11 alarm, repeat all calculations using the isotopic mix
. provided by Chemistry as soon as the mix becomes available.
2.1.12 For a current action level of unusual event or greater, generate a hardcopy of the following reports, unless otherwise directed by the Dose Assessment Team Leader. - 2.1.12.1 (X/Q) Display 2.1.12.2 Projected dose summary 2.1.12.3 Summary report
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O 2.1.13 Repeat steps 2.1.8 through 2.1.11 where any following condition is observed: '
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2.1.13.1 A new high alarm (blinking, audible) from any channel per step 2.1.2 is indicated on the RM-ll console. 2.1.13.2 An upward trend is observed in any channel per step (2.1.2) while it is in the high alarm state. 2.1.13.3 An EAL value described on either the RM-11 or RM-21A Operator Aid card is met or exceeded. AT THIS TIME, IT IS AT THE DISCRETION OF SSVN TO TERMINATE THE PROCEDURE OR INSTRUCT THE STA TO PERFORM PERIODIC DOSE ASSESSMENT CALCULATIONS (AND/OR) IMPLEMENT THE NEXT STEP OF THIS PROCEDURE. To terminate the RMMS program, enter ( /E, return) 2.2 Dose Assessment Turnover to the TSC _ 2.2.1 Upon activation of the TSC, the RM-21A Operator in Control Room will provide the following information to the Dose Assessment Team Leader in the TSC. 2.2.1.1 time of reactor trip or scram 2.2.1.2 location of release 2.2.1.3 time of release 2.2.1.4 estimated duration of release 2.2.1.5 Containment Radiation Monitor information to include: primary containment leakage, drywell purging, number of fans operating, hours purged 2.2.1.6 wind direction, ground and elevated 2.2.1.7 location and value of peak (X/Q), depleted and undepleted 2.2.1.8 time to reach peak (X/Q) 2.2.1.9 location and value of peak whole body gamma dose rate 2.2.1.10 location and value of peak thyroid dose rate U. f e--. . _ . . ._ ..
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MJR/MAC/nlp 2.2.1.11 whole body gamma dose rate at (Site boundar,y; 2, 5, 10) miles 2.2.1.12 phone number where the RM-21A Operator in the Control Room can be contacted. 2.2.1.13 Protective Action Recommendation (s) if any were made
- 2.2.2 Upon turnover of dose assessment from the Control Room to the TSC, the Dose Assessment Team Leader shall:
i 2.2.2.1 Brief team members on plant and release status. 2.2.2.2 Assign personnel as RM-21A Operator, RM-ll Operator, Calculator, Field Survey Group Leader. 2.2.2.3 Contact Chemistry for the status of the plant to include SGTS filter efficiency and isotopic breakdown of drywell air, effluent release and reactor water. 1 ] 2.2.2.4 Initiate and direct dose calculations. i 2.2.2.5 Review dose calculation parameters. 2.2.2.6 Evaluate results (Summary Report and Projected Dose Summary) against whole body 4 gamma and thyroid inhalation PAGs. i 2.2.2.7 Periodically brief the Emergency Director on offsite dose results and assist him with PAG recommendations if conditions are warranted. 2.2.2.8 Periodically update the BRP on plant conditions, meteorology, and actual or potential releases. 2.2.3 The RM-ll Operator shall: l 2.2.3.1 Continuously assess radiological trends from the drywell high-range radiation monitors
, and plant effluent monitors and inform the Dose Assessment Team Leader and Calculator as conditions change.
2.2.3.2 Update the Calculator and Dose Assessment . Team Leader, on an approximately 15 minute l basis, with information from the affected
, radiation effluent monitors unless otherwise directed by the Dose Assessment Team Leader.
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, EP-315, R3v. 6 P&ga 8 of 14 MJR/MAC/nlp 2.2.3.3 Inform the Dose Assessment Team Leader immediately in the event that any EAL has '
been reached or exceeded. 2.2.4 The Calculator shall: 2.2.4.1 Obtain, approximately every 15 minutes, the effluent release date from the RM-ll Operator. 2.2.4.2 Perform, as requested by the Dose Assessment Team Leader, EP-325 for input to the RMMS ' dose model. 2.2.4.3 Select and calculate, as directed by the Dose Assessment Team Leader, isotopic breakdowns of the source term for input to the RMMS dose model. 2.2.4.4 Note on the dose model output cover sheet, the time of the calculations and assumptions used. 2.2.4.5 Update dose trending sheets as required. 2.2.4.6 Review dose model results for key information. Immediately, inform the Dose Assessment Team Leader if dose model results indicate PAG levels may be met or exceeded. 2.2.4.7 Update the status board keepers with the requested information. 2.2.5 The RM-21A Operator shall: 2.2.5.1 Log onto the RM-21A system using the appropriate user name and password, i 2.2.5.2 Obtain metr.orological data for the period of interest by selecting the following options:
- 1. #4 - Meteorological Data Collection and Processing
, 2. #3 - Meteorological Data Processing
- 3. #3 - Review Current Averages -or- #4 Meteorological Data Averages, if the evaluation is to be done with historical data.
RESPOND TO ALL PROMPTS AND GENERATE A HARDCOPY.
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2.2.5.3 Return to the primary menu and repeat steps i 2.1.8 through 2.1.10.7. - GENERATE EARDCOPIES OF ALL SCREENS OR AS i DIRECTED BY THE DOSE ASSESSMENT TEAM LEADER ' 2.2.5.4 Review the Site Boundary Emergency Action Level Display for the current action level, generate a hardcopy and inform the Dose Assessment Team Leader of the action level. 2.2.5.5 For a current action level of unusual event or greater, generate a hardcopy of the following, unless otherwise directed by the Dose Assessment Team Leader.
- 1. (X/Q) Display
- 2. skin isopleth
- 3. gamma isopleth
- 4. inhalation thyroid isoplech
- 5. projected dose summary
- 6. summary report 2.2.5.6 Repeat steps 2.2.5.3 through 2.2.5.5 where any following condition is observed, unless otherwise directed by the Dose Assessment Team Leader.
- 1. meteorology changes significantly
- 2. new isotopic data is made available
- 3. An upward trend is observed on any
! effluent channel l
- 4. An EAL value is met or exceeded
- 5. As directed by the Dose Assessment Team Leader
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, MJR/MAC/nlp 2.3 Dose Assessment Turnover From the TSC to the EOF 2.3.1 Upon activation of the EOF, the Dose Assessment Team Leader in the EOF shall contact th Dose Assessment Team Leader in the TSC and request: ;
- 1. the l'nformation in steps 2.2.1
- 2. ground and elevated sigma-theta
- 3. ground and elevated delta temperature
- 4. stability class 1
- 5. basis for Noble Gas and Iodine source j term
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- 6. Field Survey Team inf$rmation: # teams available, # teams dispatched, time teams dispatched, locationgand results 2.3.2 The RM-21A Operator shall acklvate the RM-21 computer .s follows:
- 1. Lift.jhone receiver from cradle and pull'the left sw' itch hook into a full up, ward position.
2 B When a di'al tone is present, dia
'One ring followed by a tone hou b'e; heard.
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.' Press the switch hook down to the first
' notch. This engages the RM-21A terminal (Textronics 4014) to the VAX Computer.
- 4. Log onto the RM-21A system using the appropriate user name and password.
2.3.3 All functions and responsibilities described l in step 2.2.2 are applicable except anything pertaining to the RM-ll. All necessary radiological data shall be obtained from the RM-21 on an as needed basis. g.__..__...._...._..
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EP-315, R3v. 6 Pcg2 11 of 14 MJR/MAC/nlp 3.0 ACTIONS FOLLOW-UP None - 4.0 APPENDICES 4.1 EP-315-2 Data-Logger /RMMS Cross Reference 4.2 EP-315-1 Isotopic Abundance (LGS FSAR Table 15.6-14) 5.0 SUPPORTING INFORMATION 5.1 Purpose - The purpose of this procedure is to provide guidelines to calculate offsite doses during a potential or actual radiological emergency. 5.2 Criteria for Use 5.2.1 This procedure is used to evaluate offsite f*' doses when the effluent stream (potentially) exceeds the limits set forth in the technical specification. This can be determined by a chemical analysis or an alarm of an effluent monitor on the RM-ll. 5.2.2 Implement this procedure for either simultaneous, VALID alarms on two common (2EIO75 & SIE075), operating channels or a
*'ALID alarm on a single operating channel whose mate is inop. (3GE075 VALID alarm and 6GE075 is inop).
5.2.3 The manual mode of RMMS will allow the operator to bypass the use of real time radiological and meteorological data, enabling him to enter date of his'own choosing. 5.2.4 Operation of RMMS in the manual made is useful for investigating offsite doses during Emergency Plan exercises and in the - event that radiological or meteorological data are unavailable in the real time mode.
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-MJR/MAC/nlp 5.3 Special' Equipment 5.3.1 RM-21A consoles and User Guide 5.3.2 RM-ll consoles and User Guide 5.3.3 EP-315 Guide next to RMMS Console 5.4 References 5.4.1 LGS FSAR Table 15.6-14 i
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, MJR/MAC/ nip APPENDIX.EP-315-1 LOCA ISOTOPIC PERCENT ABUNDANCE IN PRIMARY Time after reactor scram:
Isotope 0-2 hrs I2-8 hrs 8-24 hrsL24-96 hrs'96-720 hrs Kr-83m 1.41 0.24 0.001 Kr-85 0.05 0.07 0.11 0.20 5.47 Kr-85m 6.61 3.89 0.48 Kr-87 5.64 0.36 Kr-88 13.6 4.64 0.13 . Kr-89 I Xe-131m 0.18 0.27 0.41 0.61 3.80 Xe-133m 0.95 1.35 1.71 1.22 0.01 Xe-133 38.9 57.9 82.4 97.4 90.3 Xe-135m 0.05 Xe-135 32.3 31.5 14.5 0.11 Xe-137 Xe-138 0.25 I-131 32.0 36.1 47.5 88.4 100.0 I-133 68.0 63.9 52.5 11.6 0.3 If venting through SGTS with a design basis filter efficiency, and 0.5%/ day leakage rate, then: - I-131 11.0 34.1 41.7 68.7 98.3 I-333 89.0 f5.9 58.3 31.3 1.65 References uGS FSAR USE ONLY IF REACTOR RAS SCRAMMED.
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APPENDIX EP-315-2 DATAIDGGER/RPMS CROSS REFERENCE RPMS MANUAI. DATAIDGGER DATAIDGGER RM-21A SENSOR , Channel No. & Met. Prompts Abbreviation Pa rameter Name Primary Secondary Ground Direction 0 30 ' Di r . / TIDRL 30'DIR/ (0)*, 159'DIR/ (15) 4 WDI .
,1 Ground Sigma Theta 0 30'DIR/ TIDRL 30'DIR/. (0), 159'DIR/ (15)
WDI/DEV l Ground Speed 1 30' Speed TISPL 30' Speed (1), 159' Speed (16) l WSI Ground Delta T 6 266'-26' T TLDT U-I. 266'-26' T(6), 300'-26' T(23) DTI i Elevated Direction 2 175' DIR./ T1 DRI 175' DIR/ (2), 304' DIR/ (20)
; WD2 Elevated Sigma Theta 2 175' DIR./ T1 DRI 175' DIR/ .(2), 304' DIR/ (20) , WD2/DEV l Elevated Speed 3 175' Speed TISPI 175' Speed (3), 304' Speed (21)*
4 WS2 Elevated Delta T 7 266*-26' T TIDL U-L 266'-26' T(7), 300'-26' T(23) DT2 Elevated Amb. Temp. 10 26' Ambient T2 AT L 26' Ambient (10), 26' Amb. T.(24) TR1
- Channel number from Data-logger in parenthesis ( ) ..
Wind Charts Wind Speed - red - (0-100 mph) full scale - Sigma theta - black - (0-100 mph) full scale Wind direction - red - (0-360-180) full scale 3
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[ i NUCLEAR REGULATORY COMMISSION 5 = wasmmorow. o. c. 20sss
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- p[~ February 4,1986 50-352/353 Limerick MEMORANDUM FOR: Chief, Document Management Branch, TIDC FROM: Director, Division of Rules and Records, ADM
SUBJECT:
REVIEW 0F UTILITY EMERGENCY PLAN DOCUMENTATION The Division of Rules and Records has reviewed the attached document and has determined that it may now be made publicly available. hf& ) Donnie H. Grimsley, Director 7 Division of Rules and Records (7 Office of Administration
Attachment:
As stated s 4 9 4
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) ACCESSIO 6e09800406 DOC. DATE: 86/01/21 NOTARIZED: YES DOCKET # FACIL: 50 2 Limerick Generating Etation, Unit 1, Philadelphia Ele 05000352 50-353 Limerick Generating Station, Unit 2, Philadelphia Ele 05000353 AUTH.NAME AUTHOR AFFILIAT7.ON DALTROFF,S.L. Philadelphia Ele:tric Co. + RECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E. Region 1, Office of Director
SUBJECT:
Forwards Central Files versions of revs to emergency plan implementing procedure 4, including Rev 8 to Procedure EP-277,
" Personnel Safety Team Phone List." Affidavit requesting withholding encl. Withheld (ref 10CFR 2.790).
DISTRIBUTION CODE: XOO5D COPIES RECEIVED: LTR _b ENCL J. SIZE: TITLE: Emerg Plan (CF Avail) NOTES: LPDR 2cys Transcripts. 05000352 OL: 10/26/84 LPDR 2cys Transcripts. 05000353 RECIPIENT COPIES RECIPIENT COPIES ID CODE /NAME LTTR ENCL ID CODE /NAME LTTR ENCL DWR PD4 PD 1 O MARTIN,R j$ f 1 1
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INTERNA DM/DRR 1 IE/DEPER/E'PB Jg40$b 2 2 E7DEPER/IRB" 1 1 NRR/DS10 DIR My 1 1 REG FILES / 1 1 NOTES: 2 2 l l i l TOTAL NUMBER OF COPIES REGUIRED: LTTR 10 ENCL 9
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