ML20098B174

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Public Version of Revised Emergency Plan Implementing Procedures,Including EP-222 Re Field Survey Group & EP-315 Re Calculation of Offsite Doses Using Rmms in Manual Mode & Revised Index.W/Jm Felton 840914 Memo
ML20098B174
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 07/11/1984
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
References
PROC-840711, NUDOCS 8409250453
Download: ML20098B174 (50)
v • d • e


Text

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3843036870

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EP-222, Rov. 2 Page 1 of 19 REL/nlp

?HILADELPHIA ELECTRIC COMPANY '

'N LIMERICK GENERATING STATION N

EMERGENCY PLAN IMPLEMENTING PROCEDURE

~ ' m mg EP-222 FIELD SURVEY GROU1

't

[f' 1.0 PURPOSE is ' d' ;ma N\

_ The purpose of this procedure is to provide instructions and guidelines for the actions of the Field Survey Group.

2.0 RESPONSIBILITIES 2.1 The Field Survey Group Leader shall be respansible to direct the actions of the field survey group members.

2.2 The Field Survey Group members shr.ll be. responsibla to conduct field surveys as directed by the Field Survey Group leader and this procedure.

3.0 APPENDICES 3.1 EP-222-1, Emergency Exposure Guidelines 3.2 EP-222-2, Field Survey Group Survey Record 3.3 EP-222-3, Field Survey Group Exposure Record l 3.4 EP-222-4, Field evey Air Jamgle Data Record 3.5 an . . H p r= q .

l EP-222-5, Field . Survey Group Lead r bata* Rec,ord l 3.6 EP-222-6,FieldSurveyKip,IpvN~ toy eklist

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] 3.7 EP-222-7, Field Survey;U v .. ChecklistO/

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YN U'l bI I !!!'!i 4.0 PREREQUISITES k M.EY 4.1 Emergency has been declared per EP-101, Classification of Emergencies.

8409250453 840711 PDR ADOCK 05000352 F PDR e

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t EP-222, Rev. 2 Page 2 of 19

.. REL/nlp 5.0 SPECIAL EQUIPMENT l 5.1 Radio with 2 Battery Packs 5.2 Field survey kits S.3 Vehicle l S.4 Emergency Dosimetry (0-1500 mR and 0-5 R LRD's) 6.0 SYMPTOMS 4

6.1 An actual or potential release of radioactive material beyond the site boundary in excess of technical specifications.

7.0 ACTION LEVEL 1

7.1 The Field Survey Group shall be activated at the Alert level or as determined by the Dose Assessment Team Leader.

8.0 PRECAUTIONS l 8.1 The group members exposure shall be limited to the guidelines in EP-222-1, Emergency Exposure Guidelines.

8.2 Meteorological conditions, expected radiation levels, and other hazards shall be used to determine the positioning of field survey groups.

I J

. 9.0 PROCEDURE l 9.1 Activation 9.1.1 The Field Survey Group Leader (FSGL) shall:

9.1.1.1 Report to the Technical Support Center (TSC) .

'.'- y l EP-222, Rsv. 2 Page 3 of 19

.I

  • REL/ nip 9.1.1.2 Discuss the situation with the Dose Assessment Team Leader. This discussion should include: the potential for release, the magnitude of the radioactive source term, meteorological conditions and potential for change, and the number of field survey squads needed.

9.1.1.3 Coordinate the formation of the necessary l number of field survey squads from personnel supplied by the Operations Support Center (OSC). A squad consists of a Health Physics Technician and a driver'.

9.1.1.4 Obtain drivers and vehicles from the Fire and Damage Team Leader and have them report to the TSC.

9.1.1.5 Direct field survey squads to obtain emergency dosimetry.

9.1.1.6 Instruct the H.P. Technicians to secure and inventory the required number of field survey kits and radios, and perform equipment checks. The radios are located in the Dose Assessment Room in the Technical Support Center and the field survey kits are located in the storage closets in the Personnel Entry Area of the Technical Support Center.

9.1.1.7 Discuss the situation with each squad, assign each squad a unique color designation, and direct them to specific initial locations in the field.

9.1.1.8 Notify Security Team Leader of the, names of field survey squad members so that they will not be detained upon leaving the site.

9.1.2 Field survey # squad members shall:

9.1.2.1 Report to the Field Survey Group Leader (FSGL) at the Technical Support Center or the Personnel Safety Team Leader after the EOF has'been activated.

9.1.2.2 Obtain a field survey kit and a radio.

9.1.2.3 Break the seal on the field survey kit and check equipment for operability including source check of survey equipment. Document equipment checks on EP-222-2.

, 7 .' EP-222, Rev. 2 Page 4 of 19

,, REL/nlp l NME IF THE SEAL ON THE FIELD SURVEY KIT WAS ALREADY

- BROKEN, PERFORM AN INVENTORY OF THE KIT CONTENTS PER APPENDIX EP-222-6, FIELD SURVEY KIT INVENTORY CHECKLIST 9.1.2.4 Obtain emergency dosimetry (0-1500 mR and 0-5 R Direct Reading Dosimeters (DRDs).

Ensure that DRDs are zeroed prior to leaving

. the TSC.

9.1.2.5 Obtain information from the FSGL on the situation, plan of action, specific survey locations, and necessary precautions.

l NOTE i

ISSUANCE OF k 0-5 R DRD IS NOT TO BE INTERPRETED AS AN AUTHORIZATION TO EXCEED STATION ADMINISTRATIVE GUIDELINES.

9.1.2.6 Upon leaving the TSC keep all dosimetry.

9.1.2.7 Ensure that the E-520/HP-270 or equivalent is on and operating prior to leaving the TSC.

9.1.2.8 Perform communication check of radios with

the FSGL prior to leaving the site.

9.1.2.9 Proceed to the first field survey point as directed by the FSGL.

l 9.2 Implementation 4 9.2.1 The Field Survey Group leader shall:

9.2.1.1 Maintain communication with and direct the activities of.the field survey squads.

Ensure that the location of each squad on the Field Sudvey display map is updated as '

necessary. -

l 9.2.1.2 Obtain field survey results as provided by i field survey squads and record results on l EP-222-5, Field Survey Group Leader Data Record.

9.2.1.3 Provide the field survey squads with status updates including: radiological and meteorological conditions, etc.

9.2.1.4 Dispatch the field survey squads to additional survey locations as necessary.

I 9.2.1.5 Field Survey Group Exposure Record, Appendix .

EP-222-3, shall be completed ~as directed by the Field Survey Group Leader.

- 9.2.1.6 If the field survey squad members and/or vehicles become contaminated inform the l

Personnel Safety Team Leader.

9.2.1.7 When advised that the EOF has taken over the Dose Assessment function, inform the field survey squads. Perform a formal turnover with the EOF Field Survey Group Leader and

- report to the Dose Assessment Team Leader.

l 9.2.2 Field survey squad members shall:

9.2.2.1 While in transit, ensure that the E-520/HP-270 or equivalent is on and switched to the lowest appropriate scale. Hold the probe outside the vehicle and have the driver proceed until the specified survey location is reached. Continuously monitor the survey instrument while in transit.

9.2.2.2 When survey location is reached, pull off the road and turn on emergency flashers.

Exit vehicle and determine the maximum dose rate at waist height in a 360 degree radius using the E-520/HP-270 or equivalent. Take readings with the probe shielded and unshielded. If the unshielded reading is greater than two times the shielded reading, assume that you are immersed in the plume (as opposed to seeing the effects of skyshine).

9.2.2.3 Record all results on EP-222-2, Field Survey Group Survey Record, and transmit information to the FSGL by radio. 'If the radio does not function properly, locate a tele hone and 'eco r t survey information.

all EOF and ask . vey roup Lea .

9.2.2.4 Take air sample at the location if directed by the FSGL as follows:

l CAUTION ENSURE THAT THE ON/OFF SWITCH IS OFF PRIOR TO CONNECTING THE AIR SAMPLER TO THE VEHICLE BATTERY.

CONNECT RED LEAD TO THE POSITIVE BATTERY TERMINAL AND BLACK LEAD TO NEGATIVE BATTERY TERMINAL.

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EP-222, Rsv. 2

, .  ; , Paga 6 of 19 l

, REL/nlp a) Connect terminals of Radeco H809C or equivalent to vehicle battery with -

}. engine running as stated above. Place air sampler on an elevated surface, not the ground. j b) Mark filter and silver zeolite cartridge l to indicate air flow direction.

l c) Orient the air sampler toward the plant and run air sampler for 5 minutes or as directed by FSGL. Record the indicated

., flow rate on EP-222-4, Field Survey Air Sample Data Record.

d) While air sampler is running, label one j envelope and one small plastic bag with the following information: Location, 1 Date, Flow rate, Time On, and Time Off.

I l NOTE AIR SAMPLER SHOULD NOT BE RUN AT GREATER THAN 2.5 cfm.

ADVISE FSGL IF SUCH IS THE CASE.

9.2.2.5 If so directed by the FSGL take 6 inch and waist level shielded probe measurements

- using the E-520/HP-270. If the 6 inch reading is greater than the waist level reading, take several disc smears of representative flat environmental surfaces.

Using caution to prevent the spread of -

contamination, place smears in labelled envelopes for counting at a later time.

1 9.2.2.6 When you have finished collecting the Air S ample , inform the FSGL that the air sample i is ready to be analyzed. Disconnect air sampler, place air sampler in vehicle, and drive to a low background counting area, as ,

directed by the FSGL. While in transit, monitor E-520/HP-270 or equivalent for .

radiation levels. Note minimum and maximum i readings and transmit the location of these I readings to the FSGL.

l 9.2.2.7 Upon arrival at the low background counting  !

. area, set up the SAM-2 or equivalent and '

allow to warm up and stabilize, as follows:

a) Connect cable from RD22 probe to

" Detector" jack on the front of the SAM-2.

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, EP-222, Rev. 2 Page 7 of 19

. REL/nlp b) Connect the battery lead to the

" Battery" jack on the back of the SAM-2.

Plug other end of lead into the socket on the side of the battery pack.

c) Set the SAM-2 Controls as follows:

l Stabilizer: OFF .

Count Mode: TIMED

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Meter Channel: 1 l Window: Set as shown on Calibration Sticker Threshold: Set as shown on Calibration Sticker Multiplier: x10 4

Response: " Midrange" "IN" Count Time: 5x1

, l Channel 1: In , +

l Channel 2: Off,out H.V.: As shown on the SAM-2 Calibration Sticker, d) Switch the " Power" Switch on the back of the SAM-2 to "ON". Press the " RESET START" button on the front of the SAM-2 and allow the instrument to count for 5 minutes to warm up.

  • l NOTE -

l IF THE "BATT OK" LIGHT IS NOT LIT, INFORM FSGL.

9.2.2.8 Remove only the particulate filter from the air sampler head and perform an analysis of the particulate filter using the E140N/HP- l a

210T with the SH4A sample holder. Record background readings and sample readings in EP-222-4, Field Survey Air Sample Data Record.

l CAUTION IF BACKGROUND RADIATION LEVELS EXCEED 300 CPM USING THE E-140N/HP-210 T, INFORM THE FSGL AND MOVE TO

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. l EP-222, Rev. 2 Page 8 of 19 REL/nlp ANOTHER COUNTING AREA WHERE THE BACKGROUND IS LESS THAN OR EQUAL TO 300 CPM.

G.2.2.9 Run the air sampler for one minute with the silver zeolite cartridge in place to purge the cartridge.

9.2.2.10 Place the Ba-133 check source cartridge against the end of the RD22 probe in the sample holder and set the count time on the

~ SAM-2 to 2x1 minutes. Press the " RESET START" button and count. Record total l number of counts on Appendix EP-222-4.

9.2.2.11 To establish the background of the counting system, exchange a clean silver zeolite cartridge for the Ba-133 check source and press " RESET START". Record total number of

\ counts on Appendix EP-222-4.

9.2.2.12 Compute the net count rate as follows:

NET (CPM) = GROSS COUNTS-BKG COUNTS 2

_ l and record on Appendix EP-222-4.

9.2.2.13 Compare the net count rate to the allowable net count rate listed on the SAM-2 calibration label. If the measured net count rate is within the range specified, l proceed to 9.2.2.14 and use the SAM-2 for I-131 determination. IF THE NET COUNT RATE FALLS OUTSIDE OF THE ALLOWABLE RANGE, REPEAT STEPS 9.2.2.10 TO 9.2.2.13 ONE TIME. If results are still unsatisfactory, inform the Field Survey Group Leader. '

l NOTE THE BA-133 SOURCE CHECT STEPS 9.2.2.10 to' 9.2.2.13, MUST BE PERFORMED INITIALLY TO VERIFY SATISFACTORY OPERATION OF THE SAM-2 COUNTING SYSTEM. THIS CHECK  !

NEED NOT BE PERFORMED PRIOR TO COUNTING SUBSEQUENT AIR SAMPLES UNLESS THERE IS REASON TO SUSPECT A PROBLEM WITH THE SAM-2 COUNTING SYSTEM. THE BACKGROUND, HOWEVER, MUST BE COUNTED PRIOR TO COUNTING EACH AIR SAMPLE.

9.2.2.14 Remove the silver zeolite cartridge with the field sample from t.he air sampler head and carefully wrap the cartridge in cellophane.

9.2.2.15 Place the wrapped cartridge in the sample holder and press " RESET START". Record

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/, EP-222, Rav. 2 Page 9 of 19 REL/ nip TOTAL number of counts on EP-222-4 when the count is complete,

, 9.2.2.16 Calculate I-131 concentration using the equation listed in EP-222-4, Part 2 and transmit the results to the FSGL.

9.2.2.17 Rebag the samples for transport back to the site for analysis.

9.2,2.18 Await further instructions from the Field

. Survey Group Leader.

l 9.2.2.19 Before returning to the site, survey sel.

and vehicle for contamination. If contamination is found, inform the Field Survey Group Leader and take the vehicle to the designated Vehicle Decontamination Facility.

9.2.2.20 Bring all environmental samples to the Personnel Decontamination Facility in the Radwaste Enclosure and turn them over to a member of the Chemistry Sampling and Analysis Group or as directed by the FSGL.

- 9.2.2.21 Place all data forms in a clean plastic bag and have a noncontaminated individual bring the bag to the Field Survey Group Leader in the TSC.

9.2.2.22 The Health Physics Technician shall inventory the field survey kit upon returning to the site and report results to FSGL.

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. , i EP-222, Rev. 2

. Page 10 of 19 REL/ nip APPENDIX EP-222-1

. EMERGENCY EXPOSURE GUIDELINES Projected Whole Body Thyroid Authorized Function Dose Dose By

.. 1. Life Saving and Reduction of Injury 75 rem

  • 375 rem (Interim)

Emergency **

Director

2. Operation of Equipment to Mitigate an Emergency 25 rem
  • 125 rem (Interim)

Emergency **

Director

3. Protection of Health and Safety of the Public 5 rem 25 rem (Interim)

. Emergency **

Director

4. Other Emergency 10 CFR 20 10 CFR 20 (Interim)

Activities limits limits Emergency Director

5. Re-entry / Recovery Station Station Activities Administra- Adminis-tive Guide- trative lines Guide-lines N/A

Reference:

EP A-5 20/1-7 5-001 Table 2.1

    • Such exposure shall be on a voluntary basis J

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', EP-222, Rev. 2 Page 11 of 19 APPENDIX EP-222-2 s FIELD SURVEY GROUP SURVEY RECORD l (Page 1 of 2) l Field Survey Team l Team Members: Date: / /

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l INSTRUMENT INVENTORY l Instrument Type Serial Number Calibration ok Batt ok Response ok l RO-2A l E-520 4

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, EP-222, Rsv. 2 Pcga 13 of 19 REL/ nip l APPENDIX EP-222-3 FIELD SURVEY GROUP EXPOSURE RECORD Field Survey Team Date: / /

Time:

Dose Rec'd. Time Spent In Name (mR) Area (H r s . ) MPC-hours **

(A) HP TECH (B) DRIVER (C) OTHER

  • MPC-hr s (I 131) = (Detected conc. uCi/cc I 131) (Time in Area) (1.llP8 MPC/uCi/c
    • NOTES:
1. MPC-HOURS ARE CALCULATED USING I-131 AS THE LIMITING ISOTOPE

_ 2. MPC-HOURS ARE ADMINISTRATIVELY CONTROLLED AT 20 MPC-HRS /WK; Exposures >20 mp:/ hrs /wk to 40 mpc-hrs /wk can be authorized by the Senior Health Physicist (A) (B) (C) (A) (B) (C)

Previous Daily Exposures (mR) W/B MPC-hrs.

Exposure from this entry + (mR) W/B MPC-hrs.

Exposure Totals '(mR) W/B M?C-hrs.

J Remaining Balance (mR) W/B MPC-hrs.

3. INDIVIDUALS SUSPECTED OF EXCEEDING 10 MPC-HRS /WK ARE REQUIRED TO HAVE A WHOLE BODY COUNT
4. DOSIMETRY RECORDS ARE REQUIRED FOR EXPOSURES > 2 MPC HRS / DAY,

>10 MPC HOURS /WK.

OPIES TO: - FIELD SURVEY TEAM LEADER; - DOSE ASSESSMENT TEAM LEADER o

EP-222, Rev. 2

, Paga 14 of 19 REL/ nip 4

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APPENDIX EP-222-4 FIELD SURVEY AIR SAMPLE DATA RECORD l Date: / / Time:

Survey Team " Location Sector l PART 1

1. Air Sample " Time On"

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2. Air Sample " Time Off"
3. Air Sample Run Time minutes
4. Air Sample Flow Rate cfm S. E-140N/HP-210T Background cpm
6. Particulate Filter Gross Count Rate cpm
7. Particulate Filter Net Count Rate cpm (net)

. 8. AgX Cartridge Gross Count Rate cpm

9. AgX Cartridge Net Count Rate cpm (net) 4 *10. SAM-2 Ba-133 Check source Counts /2 min.
11. SAM-2 Background (clean cartridge) Counts /2 min.
  • 12. Ba-133 Net Counts Counts /2 min.
13. SAM-2 I-131 field sample Counts /2 min.

l

  • Perform initially to verify operation of SAM-2-See NOTE, sec. 9.2.2.13 l PART 2 -

j Determination of I-131 Concentration 1.' Air Sample volume:

Run Time (#3) X Flow Rate (#4) = cubic feet (ft3) l 2.

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(#13) (411)

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~ Counts - Bkg l l l

. 2 Minutes _ _ Eff _ ,_ Volume _ _ 0.95 _ x 1.99 Nil = uCi/cc I

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_ 1 1

_ 2 Min _ _ _ _ _ _ 0.95 _ x 1.59 Nil = uCi/cc ,

I l PART 3 l Determination of MPC Fraction (If directed by FSGL)

E-140N - (Net CPM)

= 4 MPC (Volume) (18.7)

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EP-222, Rsv. 2

, "; - Paga 15 of 19 REL/nlo l\.

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i t- x i APPENDIX EP-222-5

. FIELD SURVEY GROUP LEADER RECORD l Date: / / Time: EST s

-l Survey Team " ' "

Location 6" Waist High Sector Area Dose Rate ( ) mR/Hr (shielded)E-520/HP-270 mR/Hr(unshielded)E-520/HP-270

() __

l Direct Frisk of Air Sample Filters i

l AgX net cpm l Particulate Filter net cpm l Air Sample Data (Part)' MFC Fraction (unidentified).

l (I - 131) uCi/cc Copies to: Field Survey Team Leader - Status Board Keeper - Dose Assessment Team Leader O

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- a EP-222, Rev. 2 Page 16 of 19 REL/ nip l APPENDIX EP 222-6 l FIELD SURVEY KIT INVENTORY (P ag e 1 of 2)

Quantity (Check)

1. Car Battery Operated Air Sampler (H809C) 1 a) Sampling Head 1 b) Filter Paper, Box 1 c) Silver Zeolite Cartridges 10
2. G. M. Counter (E520) 1 a) Probe (HP-27 0 ) 1 b) GM Headset 1 c) Spare Batteries (alkaline D cells) 2
3. Ion Chamber (RO2A) 1 a) Space Batteries (Alkaline 9 volt) 4
4. Frisker (E-140N) 1 a) Probe (HP-210T) 1 b) Sample Holder (SH-4A) 1 c) Spare Batteries (Alkaline D cells) 2
5. Stabilized Assay Meter (S AM-2) 1 a) Dstector (RD22) 1 b) Battery Pack (BP4) 1 c) Probe / Sample Holder 1 1.5")

d) Spacers (0. 5" , 1.0", 3 e) BA-133 Check Source _1

6. Flashlight 2 a) Spare Batteries (alkaline D cells) 4
7. Radiation Tape (roll) 1

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8. Clip Board 1
9. Log Book 1
10. Black Pens 3
11. Grease Pencils 1
12. Field Survey Maps (Book) 1
13. Smears (Book) 10
14. Envelopen for Smears (S tamped) 20
15. Ziplock Bags
  • 20
16. Felt Tip Marker 2
17. Plastic Wrap (roll) > 1
18. Masking Tape (2" roll) 2
19. Duct Tape (2" roll) 2
20. Masslinn (Package) 1
21. Quarters for Pay Phone (Roll) 1
22. Protective Clothing (set includes paper coveralls, cap, cotton liners) 2
23. Stopwatch 1
24. Pocket Knife 1
25. Tweezers 1
26. Pocket Calculator 1
27. Compass 1
28. Rain Suit (Pants & Jacket) 2
29. Plastic Bags (5 gallon) 25

EP-222, Rov. 2

  • Page 17 of 19 REL/ nip

} Appendix EP-222-6

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FIELL SURVEY KIT INVENTORY (Page 2 of 2)

Quantity (Check)

30. Plastic Bottle ( 1 liter) 3
31. Radiation Material Stickers 50
32. Gloves, plastic (pair) 30

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33. Shoe Covers (pair) 10
34. Telechone Directory (Site) 1
35. Current HP Procedures (set) 1
36. Rad Rope (50' roll) 1
37. Current EP Procedures (set) 1 4

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l EP-222, Rev. 2 Page 18 of 19 REL/nlp l APPENDIX EP-222-7 FIELD SURVEY CHECKLIST

1. BEFORE LEAVING SITE A) All Equipment accounted for and operable B) Have been briefed on situation, etc.

C) Have Emergency Dosimetry and they are zeroed D) Communication check performed E) ES20/HP270 is ON

2. AP THE SURVEY LOCATION AND WHILE IN TRANSIT A) Looked for and reported location where increasing

- radiation levels occured while s.till in transit to specified survey location l B) Performed survey using E-520/HP-270 to look for maximum dose rate at waist level in 360 deg. radius C) Survey with E-520/HP-270 with probe shielded and unshielded l D) Have notified FSGL of arrival and dose rate encountered l E) If advised to take air sample: ,

1) Particulate filter and s,ilver zeolite cartridge marked to indicate direction 2

of air flow

2) Air Sampler head loaded with filter located outside of cartridge
3) Air Sampler head oriented toward the plant and running -
4) F' low Rate observed and recorded b

EP-222, Rev. 2 Page 19 of 19 REL/nlp F) If direct'ad by FSGL, 6 inch gamma readings taken with E-520/HP-270 G) If 6" readings higher than waist level readings, smears taken H) Notified FSGL that Air Sample has been pulled and advised to move to low background counting area to analyze. sample I) E520/HP270 is ON during transit - looking for and reporting locations of maximum and minimum dose rates l 3) AT LOW BACKGROUND COUNTING AREA l A) SAM 2 set up and counting for 5 minutes to warm up

  • B) 2 minute count of Ba-133 check source (for initial analysis only) l C) Remove and count particulate filter with E-140N/HP-210T l D) Purge Silver zeolite cartridge for 1 minute l E) 2 minute count of Clean Silver Zeolite cartridge l F) 2 minute count of Sample Silver Zeolite cartridge l G) I-131 Concentration calculated l H) All results recorded and relayed to FSGL l I) Advised to move to new location '

J) If advised to return, monitor self and vehicle and relay findings to FSGL  ;

K) All samples turned over to Chemistry Sampling &

Analysis Group at Personnel Decon Facility in Radwaste Enclosure l L) All forms turned over to FSGL for subsequent dispostion

  • Perform initially to verify satisfactory operation of SAM-2 counting system only l

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'. 3843036880 EP-31s aav. o Page 1 of 21

, , -, GWM/no 7

) PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION

' l4&(!.?D EMERGENCY PLAT 7MPLNEN N RC,EDUpE.,_

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r 2 EP-315 CALCULATION OF OFFS AE D S$S G O I Ad EMERGENCY USING RMMS IN THE MANUAL MODE 1.0 PURPOSE .

The purpose of this procedure is to provide guidelines to RMMS operators and dose assessment personnel who are using RMMS to calculate offsite doses during a potential or actual radiological emergency.

The manual mode of RMMS will allow the coerator to bypass the use of real time radiation and meteorological data, enabling him to enter data of his own choosing.

Operation of RMMS in the manual mode is useful for investigating offsite doses during Emergency Plan exercises and in the event that radiation or meteorological data are anavailable in the real time mode.

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2.0 RESPONSIBILITIES 2.1 It is the responsibility of the Shift Technical Advisor in the control room, assigned to RMMS, to initiate dose calculations if there is an indication that a radiological release in excess of instantaneous Technical Soecifications limits has occurred.

2.2 It isthe,fspo&?

Je D nsi$h TE::hgsSh TV ft S'uperintendent to evaluat%#tte d sp dg re the apprc'priate EAL based on rele and assist the Emergency Director in maki p kmendations if warranted.

2.3 It is the respons ty df the Dose Assessment Team Leader (u tivation of the TSC) to initiate and direct do c@ :iVn u the results, and assist th gN}.3-

Di(ru(119 d e EAL de:larations and PAG recommendations.

I 2.4 It is the responsibility of the RM-ll Operator in the l

TSC to provide radiation release cata to the RM-21A Operator and the Dose Assessment Team Leader.

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. ., EP-315 Rev. 0

. Pags 2 of 21 GWM/no

) 2.5 It is the responsibility of the RM-21A Operator in the TSC to enter radiation release data and meteorological data and generate offsite dose estimates.

2.6 It is the responsi.bility of the Field _ Survey Group Leader in the TSC to direct field survey squads to locations in the plume in order to acquire data which will augment and enhance the offsite dose estimates.

2.7 It is the responsibility of the Calculator in the TSC to assist the RM-21A Operator with data entry problems

- -- and to periodically update the Dose Assessment Status Board Keeper and Meteorological Status Board-Keeper with information.

2.8 It is the responsibility of the Dose Assessment Team Leader in the EOF to initiate and direct the offsite dose calculations when the EOF is activated and assist the Site _ Emergency Coordinator with EAL declarations and PAG recommendations.

2.9 It is the responsibility of the RM-21A Operator in the EOF to enter radiation release data and meteorological data and generate offsite dose estimates. ,

2.10 It is the responsibility of the Field Survey Group

. -) Leader in the EOF to direct field survey squads to locations in the plume in order to acquire data which will augment and enhance the offsite dose estimates.

2.11 It is :he responsibility of the Calculator in the EOF to assist the RM-21A Operator with data entry problems, and periodically update the Dose Assessment Status Board Keeper with information.

3.0 APPENDICES ,

None -

J 4.0 PREREQUISITES ,

None ,

l EP-315 Rev. 0

. Pcgo 3 of 21 GWM/no

) 5.0 SPECIAL EQUIPMENT 5.1 RM-21A consoles and hardcopy units 5.2 RM-ll consoles and printers 6.0 SYMPTOMS 6.1 An indication that a radiological release in excess of

. - instantaneous Technical Specifications limits has or may occur.

7.0 ACTION LEVEL None 8.0 PRECAUTIONS None

{ 9.0 PROCEDURE 9.1 Control Room Operations 9.1.1 Upon receiving an indication that a gaseous release in excess of instantaneous technical specifications may have occurred, the control rocm operator shall first acknowledge the alarm on the RM-ll console, and request that an offsite dose calculation be initiated to evaluate the release.

9.1.2 The following channels will provide an indication of a potential technical specificacion celease if in a blinking red state and audibly alarming:

9.1.2.1 North Vent Wide Rance Gas Monitor

~

' Channel 4TE076 s

J

EP-315 Rav. 0 Pago 4 of 21

- G~dM/no I Particulate, Iodine, Noble Gas Monitors Channel 2IE075 Channel SIE075 Channel 3GE075*

Channel 6GE075 9.1.2.2 South Vent - Unit 1 Particulate, Iodine, Noble Gas Monitors Channel 2IE185

. Channel SIE185 Channel 3GE185 Chanel 6GE185 9.1.2.3 South Vent - Unit 2 .

Particulate, Iodine, Noble Gas Monitors Channel 2IE285 Channel SIE295 Channel 3GE285 Channel 6GE285 9.1.3 The control room Shift Technical Advisor assigned to the RM-21A will logon to the system using the appropriate username and password, select option 6 (Emergency Dose Calculations) from the Primary Option Menu, then option 3 (C1&ss A Dose Model) from the secondary menu. ;

9.1.4 The RM-21A operator will choose ACRISO Run Control Parameter Menu option 3, All Manual Mode. ,

l 9.1.5 The operator will respond "yes" to reviewing the run control table and verify the table matches.the example exactly in Attachment 1.

If not he will edit the table.

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} 9.1.6 The operator should generate a hardcopy oi this and all other data displays for future reference.

9.1.7 The operator shall complete the following mandatory steps:

9.1.7.1 Enter Time of Reactor Trip or Scram. If the Reactor has not tripped or scramed enter the start time of the release.

- 9.1.7.2 Enter Time of Release. Enter the Start Time of the release or the beginning of the period to be evaluated. This time must be later than or equal to the Time of Reactor Trip.

NOTE EASTERN STANDARD TIME (EST) IS USED BY RMMS. EST IS EQUAL TO DAYLIGHT SAVINGS TIME MINUS 1 HOUR.

9.1.7.3 Enter the 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 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

NOTE 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 PAY BE EXCEEDED.

9.1.8 The operator shall respond to the following additional prompts:

9.1.8.1 Enter the Isotopsc Release Data for selected release point by selecting option 3 as follows:

A. Noble Gases The operator should choose gaseous isotope 8 Kr-88 and enter the isotopic ,

release rate obtained from channel 4TE076 on the RM-ll display console for the period of interest.

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.) B. Iodines The operator should select isotope 34,

. I-131 and enter the isotopic release cate as follows:

Obtain the average iodine concentration (uCi/cc) from channels 2IE075 and 5IE075, multiply this average by the process flow rate in CFM (obtained from

. the top of either above channel trend

. display), and multiply by 472 (to convert units to uCi/sec) 9.1.8.2 Enter the Vent Flow Rate (CFM)

Obtain this value from the top of any channel trend display associated with the release point of interest. (Indicated as process flow rate N. on the trend display).

NOTE IF OFFSITE POWER HAS SEEN LOST, CHOOSE PROCESS FLOW

, RATE "A" ON THE TREND DISPLAY.

9.1.8.3 Enter the Meteorological Data Obtain the data from the Meteorological Data-Logger and enter the sensor which corresponds to the p.:ompt. Refer to the cross reference attached to the RM-21A console for the correct sensor input.

~

NOTE IF METEOROLCGICAL DATA IS UNAVAILASLE THE OPERATOR SHALL ATTEMPT TO OBTAIN THE DATA FROM THE FOLLOWING SOURCES (LISTED IN ORDER OF PREFERENCE):

1. CONTROL ROOM STRIP CHAR,.T RECORDERS. . . . . . . - - - - . . - - - -

'h. P3APS CONTROL OPERATOR (EXT EQUEST -

TOWER 2, 75' WIND SPEED AND DIRECTION, 300' - 30' )

DELTA T FOR STABILITY DETERMINATION j/

NATIONAL WEATHER' SERVICE 'I

.)

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. EP-315 Rev. 0

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) 9.1.9 The operator shall review the following displays for accuracy and generate a hardcopy for his records. If the .

information shown on the displays is incorrect, he'should enter R to Restart his data entry.

9.1.9.1- Meteorological Data Summary Verify that the dates and times of the release are correct. Verify that the meteorological dat.a are correct. Generate hardcopy.

9.1.9.2 Release Summary Verify that the isotopic release data and vent flow data are correct. Generate i hardcopy.

9.1.10 The operator shall then review the Site Boundary Emergency Action Level Display for the current action level, generate a

.hardcopy and inform the shift superintendent of the action level.

)

9.1.11 The operator shall generate the following displays and obtain a hardcopy of each if a current action level of unusual event or greater is obtained:

9.1.11.1 X/O Display.

9.1.11.2 Projected Dose Summary.

9.1.11.3 Summary Report.

9.1.12 The RM-21A Operator should repeat th6 steps

> 'in 9.1.7 to 9.1.11 if any following condi-tion is obse'rved:

2 9.1.12.1 A new high alarm (red, bli nk ing ,- audible) is indicated on the RM-ll display console from any channel described in 9.1.2.

9.1.12.2 An upward trend is observed in any channel described in 9.1.2 while it is in the high alarm state. .

9.1.12.3 An EAL value described on either the RM-ll or RM-21A operator aid card is met or

/ exceeded.

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/ 9.1.13 Dose assessment turnover to the TSC Upon activation of the TSC, the RM-21A .

Operator in Control Room shall contact the IDose Assessment Team Leader, (extension and provide the following information it-an EAL based on a release has been '

determined.

9.1.13.1 Time of Reactor Trip or Scram 9.1.13.2 Time of Release 9.1.13.3 Estimated Duration of Release 9.1.13.4 Wind Direction 9.1.13.5 Location of Peak X/Q 9.1.13.6 Time to Reach Peak X/Q 9.1.13.7 Location and Value of Peak Whole Body Gamma Dose Rate .

9.1.13.8 Location and Value of Peak Thyroid'Dcse Rate 9.1.13.9 Whole Body Gamma Dose Rate at 2, 5 and 10 Miles 9.1.13.10 Phone number where the RM 21A operator in the Control Room can be contacted.

9.2 TSC Operations .

9.2.1 Upon turnover of dose assessment from the Control Room to the TSC, the Dose Assessment Team Leader shall do the following: ,

9.2.1.1 3rief team members on plant and release status.

J 9.2.1.2 A'ssign personnel as RM-21A Operator, RM-ll Operator, Calculator, Field Survey Group Leader.

9.2.1.3 Initiate and direct dose calculations using RMMS, 9.2.1.4 Review dose model inputs (Meteorological Data Summary and Release Summary Displays)

) for accuracy.

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EP-315 Rev. 0

, . Page 9 of 21 GWM/no 9.2.1.5 Evaluate dose model results (Summary Report

). and Projected Dose Su'a mary) against Whole Body Gamma and Thyroid Inhalation PAGs.

~ ~

9.2.1.6 Periodically brief the Emergency Director on offsite dose results and assist him with PAG recommendations if conditions are warranted.

9.2.1.7 Direct the Field Survey Group Leader to "

dispatch Field Survey Squads to areas within the plume (using chi /Q plot and Whole Body Gamma, Inhalation Thyroid prints and plots) in order to augment and enhance the offsite dose projections.

9.2.1.8 Periodically update the BRP on plant

, conditions, meteorology, and actual or potential releases.

9.2.2 The RM-ll Operator shall perform the i following:

9.2.2.1 Continuously assess radiological trends from the Drywell High Range Radiation Monitors and plant effluent monitors and inform the Calculator as conditions change.

9.2.2.2 Update the Calculator and Dose Assessment Team Leader on an approximately 15 minute basis, with information from the affected radiation effluent monitors unless otherwise directed by the Dose Assessment Team Leader.

9.2.2.3 Inform the Dose Assessment Team Leader immediately in the event that any EAL condition specified on the operator aid card has been reached or exceeded.

9.2.3 The Calculator shall perform the foll'owing:

9.2.3.1 Obtain approximat'ely every 15 minutes, the effluent releaseJdata from the RM-ll  ;

operator. l 9.2.3.2 l Perform, as requested by the Dose Assessment e Team Leader, EP-325 for input to the RMMS dose model. l 9.2.3.3 Select and calculate, as directed by the Dose Assessment Team Leader, isotopic i ,3 breakdowns of the source term for input to

,j .the RMMS dose model.

b l

. ., , _P-315 Rev. 0 Paga 10 of 21 GWM/no 9.2.3.4 Note on the dose model output cover sheet, the time of tne calculations and assumptions used. '

9.2.3.5 Update dose trending sheets as required.

9.2.3.6 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.

9.2.3.~7 Update the status board keepers with the requested information.

9.2.4 The RM-21A Operator shall perform the following:

9.2.4.1 Logon to the RM-21A system using the appropriate user name and password.

9.2.4.2 Obtain meteorological data for the period of interest by selecting option 4 (Meteorological Data Collection and Processing) from the Primary Option Menu, then option 3 (Meteorological Data

-,) Processing), then option 3 (Review Current Averages) or option 4 (Meteorological Data Averages) if the evaluation is to be done with historical meteorological data.

Respor.d to the prompts as displayed and generate a hardcopy to transcribe the sensor names into RMMS inputs.

NOTE THE RM-21A OPERATOR SHOULD EVALUATE THE METEOROLOGICAL DATA FOR CHANGES EVERY 15 MINUTES OR AS DIRECTED BY THE DOSE ASSESSMENT TEAM LEADER. ,

9.2.4.3 Return to the Primary Option Menu and select option 6 (Emergency Dose Calculations), then option 3 (Class A Dose Model) from the secondary menu.

9.2.4.4 The RM-21A Operator will choose ACRISO Run Control Parameter Menu option 3 (All Manual Mode).

9.2.4.5 The Operator will respond "yes" to reviewing the Run Control Table and verify the table

.i matches exactly the examole in Attachment 1.

~

~# If not, he will edit the table.

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. EP-315 Rev. 0 Page 11 of 21

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) NOTE THE OPERATOR SHOULD GENENATE A HARDCOPY OF THIS AND ALL REQUESTED DATA DISPLAYS FOR FUTURE REFERENCE.

9.2.4.6 The Operator shall complete the following mandatory steps:

A. Enter the Time of Reactor Trip.or Scram.

~

This prompt is chiefly used for decaying default accident isotopic spectra or isotopic data collected at the source, (e.g.', P.A.S.S. or containment air sample) to the time of release. If the isotopic data provided to the operator is data obtained from the release point, enter the time (cf release. Also, if exact isotopic composition of the release is unknown, enter the time of release.

Enter Time of Release B.

f Enter the start time of the release.

If release has begun, enter the beginning of the period to be evaluated. This time must be later than, or equal to the Time of Reactor Trip.

NOTE EASTERN STANDARD TIME (EST) IS USED BY RMMS.

, EST TS EQUAL TO DAYLIGHT SAVINGS TIME MINUS 1 HOUR.

C. Enter Remaining Duration of Release The Operatop must request that the Dose Assessment Teer Leader provide him with an estimated duration of release. If the duration cannot be estimated with confidence, enter 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

' NOTE -

l 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.

i

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) 9.2.4.7

.d k The Operator b ;ikb i shall respond to the following additional prompts. Radiation effluent data shall'be obtained from the Calculator.

Meteorological data shall be obtained from the RM-21A console for the period of interest.

A. Enter the Isotopic Release Data for the release point of interest by selecting option 3 or as ctherwise directed by the Dcse Assessment Team Leader:

1. For Noble Gases, choose gaseous isotope 8, Kr-88, and enter the gross isotopic release rate (s) provided by the Calculator.
2. For Iodines, the operator should select isotopes 34 and 35, I-131 and I-133 respectively, and enter the isotopic release rate (s) provided by the Calculator.
3. Enter the Vent Flcw Rate (CFM)

Enter the flow rate provided by the Calculator.

C. Enter the Meteorological Data Enter the Metecrological Data obtained frtm the RM-21 console for the time pericd of interest.

NOTE IF METEOROLOGICAL DATA IS UNAVAILABLE, THE OPERATOR SHALL ATTEMPT TO OSTAIN THE DATA FROM THE FOLLOWING SOURCES (LISTED IN ORDER OF PREFERENCE):

1. Conrrdi Rcom Strip Chart Recorders
2. P DS Centrol Operator (ext Ibt . 1 Request Tower 2, 75' wind speed and direction, 300'-30' delta T for stability

. determination W

3. National Weather Service

_ . _. __ i l

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. . , , EP-315 Rev. 0 Page 13 of 21 GWM/no l

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) 9.2.4.8 The operator shall review the following displays for accuracy and generate hardcopy for his records. If the information shown

. on the displays is incorrect, he should enter R to Restart his data entry.

A. Meteorological Data Summary Verify the da,tes 6nd times of the release are correct. Verify the meteorological data is correct.

Generate hardcopy.

B. Release Summary Verify the isotopic release data'and vent flow data are as entered.

Generate hardcopy.

9.2.4.9 The operator shall then review the Site aoundary Emergency Action Level Display for the current action level, generate a hardcopy and inform rhe Dose Assessment Team Leader of the action level.

9.2.4.10 The operator shall generate the following

~ ./ displays and cbtain a hardcopy of each if a current action level of unusual event or greater is obtained or as directed by the Dose Assessment Team Leader:

A. X/O Display B. Skin Isopleth C. Gamma Isopleth D. Inhalation Thyroid Isopleth ,

E. Projected Dose Summary F. Summary Repbrt 9.2.4.11 The operator should repeat steps 6.2.4.1 through 6.2.4.10 if any of the following occur:

A. Meteorology changes significantly.

B. New isotopic data is made available.

/ C. An upward trend is observed in any effluent channel of interest.

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/. . EP-315 Rev. 0 Page 14 of 21 GWM/no 3 D. An EAL value described on either the RM-ll or RM-21A operator aid card is met or exceeded.

E. As directed by the Dose Assessment Team Leader.

9.2.5 The Field Survey Group Leader shall do the following:.

9.2.5.1 Assign drivers and technicians to Field Survey Squads.

9.2.5.2 Assist the Dose Assessment Team Leader in briefing squad members on plume dimensions, location of peak Chi /Q, and dose rates, initial instructions, and potential sample locations.

9.2.5.3 Dispatch Field Sarvey Squads to positions near or within the plume and coordinate their activities.

9.2.5.4 Receive periodic updates on dose rates and meteorological conditions from the Dose

) Assessment Team Leader via the RMMS Chi /Q Gamma Whole Body, and Inhalation Thyroid prints and plots.

9.2.5.5 Instruct the Field Survey Clerk to record Field Survey Squad data.

9.2.5.6 Updare the Dose Assessment Team Leader with actual exposure rates and concentrations at the designated sample locations.

9.3 EOF Operations 9.3.1 Upon turnover of dose assessment from the TSC to the EOF, the Dose Assessment Team Leader shall do ,the following:

9.3.1.1 Assign personnel as RM-21A Operator  :

Calculator, and Field Survey Group Leader.  !

9.3.1.2 Periodically brief team members on the i status of plant, radiological, and meteorological parameters.

, 9.3.1.3 laitiate and direct dose calculations using RMMS.

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EP-315 Rev. 0

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Page 15 of 21 l GWM/no 9.3.1.4 Revied dose model inputs (Meteorological Data Summary and Release Summary Displays) r for accuracy.

9.3.1.5 Evaluate-dose medel results (Summary Report and Projected Dose Summary) against Whole Body Gamma and Thyroid Inhalation PAGs.

9.3.1.6 Pe.riodically brief the Emergency Director on offsite dose results and assist him with PAG recommendations if conditions are warranted.

9.3.1.7 Direct the Field Survey Group Leader to dispatch Field Survey Squads to areas within the plume (using chi /Q plot and Whole Body Gamma, Inhalation Thyroid prints and plots).

In order to augment and enhance the offsite dose projections.

9.3.1.8 Periodically update the 3RP on plant conditions, meteorology, and actual or potential releases.

9.3.2 The Calculator shall perform the following:

') 9.3.2.1 Obtain (approximately every 15 minutes) the effluent release data and meteorological data from the RM-21A operator.

9.3.2.2 Perform, as requested by the Dose Assessment Team Leader, EP-325 for input to the RMMS dose model.

9.3.2.3 Select and calculate, as directed by the Dose Assessment Team Leader, isotopic breakdowns of the source term as input to the RMMS dose model, o

9.3.2.4 Note on the dose model output cover sheet, '

the time of the calculations and the assumptions used, 9.3.2.5 Update dose trending sheets as required.

9.3.2.6 Review dose model results for key information. Immediately inform the Dose Assessment Team Leader if dose model results

indicate PAG levels are being met or exceeded.

)

9.3.2.7 Update the status board keeper with the

appropriate insormation.

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9.3.3 The RM-fli~ pelaEor~stiail- Nerform the following:

- . 9.3.3.1 Logon to the RM-21A system using the appropriate username, password and following method:

A. Lift phone receiver from cradle and oull the lett switch hook into a full upwara posttion.

B. Wha- a dial tone is present, dial f

'One ring followed by a tone should be heard.

(

C. Press the switch hook down to the first notch. This engages the RM-21A terminal (Texrronics 4014) to the VAX Computer.

D. Logan to the RM-21A system using the appropriate username and password.

9.3.3.2 Obtain meteorological data for the period of interest by selecting option 4 (Meteorological Data Collection and

) Processing) frca the Primary Option Menu, then option 3 (Meteorological Data Processing), then option 3 (Review Current Averages) or cption 4 (Meteorological Data Averages) if the evaluation is to be done on historical meteorological data. Respond to the prompts as displayed and generate a hardcopy to transcribe the sensor names into RMMS inputs.

9.3.3.3 Return to the Primary Option Menu and select option 6 (Emergency Dose Calculations) then option 3 (Class A Dose Model) from the secondary menu.

9.3.3.4 The RM-21A Operador will choose ACRISO Run Control Parameter Menu option 3 (All Manual ,

Mode). ,

t NOTE THE RM-21A OPERATOR SHOULD EVALUATE THE METEOROLCGICAL i

DATA FOR SIGNIFICANT CHANGES EVERY 15 MINUTES OR AS l DIRECTED BY THE DOSE ASSESSMENT TEAM LEADER.

s I

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. . , EP-315 Rov. O Pago 17 of 21

. GWM/no 9.3.3.5 The Operator will respond "YES" to reviewing the Run Control Table and verify the table matches exactiv the example in Attachment 1.

If not he will edit the table.

NOTE THE OPERATOR SHOULD GENERATE A HARDCOPY OF THIS AND ALL REQUESTED DATA DISPLAYS FOR FUTURE REFERENCE.

9.3.3.6 The operator shall complete the following mandatory steps:

A. Enter time of Reactor Trip or Scram.

This prompt is chiefly used for decaying default accident isotopic spectra and isotopic data collected at the source, (e.g. P.A.S.S. or Containment Air Sample) to the time of release. If the isotopic data provided to the operator is from the release point, enter the time of release.

Also, if exact isotopic composition of the release is unknown, enter the time of release.

B. Enter time of release.

Enter the start time of the release or, if release has begun, enter the beginning of the period to be evaluated. This time must be later than, or equal to the Time of Reactor Trip.

NOTE EASTERN STANDARD TIME (EST) IS USED BY RMMS. EST IS EQUAL TO DAYLIGHT SAVINGS TIME MINUS 1 HOUR'.

J C. Enter remaining duration of release The operator must request that the Dose Assessment Team Leader provide him with an estimated duration of release. If the duration cannot be estimated with confidence, enter 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

. 1

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NOTE l

THE REMAINING DURATION OF RELEASE IS USED IN THE EAL TABLE DISPLAY 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.

9.3.3.7 The operator shall respond to the following additional prompts. Radiation effluent data and meteorological data shall be obtained fecm the RM-21A console for the period of interest.

A. Ente'r the Isotopic Release Data for the release point of interest by selecring option 3 as follows or as otherwise directed by the Dose Assessment Team Leader:

1. For noble gases, choose gaseous isotope 8, Kr-88, and enter the gross isotopic release rate (s) provided by the Calculator, d 2. For i3 dines, the operator should select isotopes 34 and 35, I-131 and I-133 respectively and enter the isotopic release rate (s) provided by the Calculator.

B. Enter the Vent Flow Rate (CFM)

g. Enter the Meteorological Data

. Enter the Meteorological Dara obtained from the RM-21 Console for the time period of interest.

NOTE 2

IF METEOROLOGICAL DATA IS UNAVAILABLE, THE OPERATOR SHALL ATTEMPT TO OSTAIN THE DATA FROM THE FOLLOWING SOURCES (LISTED IN ORDER OF PREFERENCE)

1. Control Room Strip Chart Recorders
2. co DS Control Operator (ext

. Request Tower 2,75

/ wind speed and direction, 300'-30'

! T for stability determination.

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EP-315 Rev. 0

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3. National Weather ervice 9.3.3.8 M

The operator shall review the followin'g displays for accuracy and generate hardccpy for his records. If the information shown on the displays is incorrect, he should enter R to Restart his data entry.

A. Meteorological Data Summary Verify the dates and times of the release are correct. Verify the meteorological data is correct.

Generate hardccpy.

3. Release Summary Verify the isotopic release data and vent flow data are as entered.

Generate hardcepy.

9.3.3.9 The operator shall then review the Site Soundary Emergency Action Level Display for the current action level, generate a

' ) hardcopy and inform the Dose Assessment Team Leader of the action level.

9.3.3.10 The operator shall generate the following displays and obtain a hardcopy of each if a current action level of unusual event er greater is obtained or as directed by the Dese Assessment Team Leader. .

A. X/Q Display

3. Skin Isopleth C. Gamma Isopleth D. Inhalation ghyroid Iscpleth l E. Projected Dose Summary l

l F. Summary Report 9.3.3.11 The operator should repeat steps A through J if any of the following occur:

1 A. Meteorology changes significantly. j 1

3. New isotopic data is made available.

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). ATTACHMENT 1

~

Site: . Limerick Unit: '01. -

USER: HPI Date: 7/10/84 18:11 ACRISO RUN CONTROL TABLE 3 .

- ITEM DESCRIPTION CURRENT SELECTION 1 Meteorlogical Data.................... Manual Entry 2 Data File Type....................... 15-Min Workspace 3 Q Data Source......................... Manual Q File Data 4 Vent Flow Data........................ Manual Entry 5 Maximum Downwind Distance (Miles).... 10.0 6 Output Media.......................... Plot 7 Background Map Selectors.............. Cities Rivers, Lakes and Ocean Roads State Boundaries Counties Text 8 Report Options........................X/Q Isopleth

  1. Depleted X/Q Isopleth Skin Isopleth Gamma Isopleth Inhal. Thyroid Isopleth Milk Thyroid Isopleth Project Gamma & Thyroid Summary Report Project Dose Summary Point of Interest Print 9 Release Point for X/Q Output......... 1 10 Isopleth Contour Spacing.............. 1,1,1,2,2,2,2 11 Gamma Dose Calculation................ Semi-Infinite ,

12 Off-site Gamma Dose Adjustment Factor.l.00 13 Cff-site Iodine Adjustment Factor.....l.00 14 Active Release Points................ 1 15 Title Change......................#.... Dose Calc--All Manual 15-Min Data SELECT OPTIONS C -- Edit P -- Print ENTER OPTION SELECTION (E or P) 6

Pcge 1 of 4 Revision 7 O'7/17/84 EMERGENCY PLAN PROCEDURE INDEX

~

PROCEDURE REV.

NUMBER NO. TITLE DATE SIGNED DATE OF LAST EP-101 1 BY SUPER. PERIODIC REVIEW Classification of Emergencies 06/08/84 EP-102 3 Unusual Event Response i 06/08/84 EP-lD3 3 Alert Response 06/08/84 EP-104 3 Site Emergency Respor.se t 06/08/84 EP-105 3 General Emergency Response EP-106 07/09/84 1 Written Summary Notification 06/08/84

EP-110 2 Personnel Assembly and Accountability 06/08/84 EP-120 1 Site Emergency Coordinator EP-201 06/08/84 1 Tecnnical Support Center (TSC) Activation 06/08/84 EP-202 1 Operations Support Center (OSC) Act-ivation 06/08/84 EP-203 1 Emergency Operations Tacility (EOF) Activation 06/08/84 EP-208 2 Security Team Activation 06/08/84 EP-210 1 Dose Assessment Team 06/08/84 EP-220 CANCELLED EP-221 1 Personnel Dosimetry, Bioassay, and Respiratory Protection Droup 06/08/84 EP-222 2 Pield Survey Group EP-230 2 Ct.emistry Sampling and 07/17/84 Analysis Team Activation 06/08/84 EP-231 2 Operation of Post-Accident Sampling Systems ,

(PASS) 06/08/84 EP-232 CANCELLED EP-233 2 Retriev ng and Changing Sample Filters and 2

Cartridges from the Containment Leak Detector During Emergencies 06/08/84 i

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Page 2 of 4 Revision 7 07/17/84  !

' EMERGENCY PLAN PROCEDURE INDEX PROCEDURE REV.

NL*MBER NO. TITLE DATE SIGNED DATE OF LAST EP-234 BY SUPER. PERIODIC REVIEW 2 Obtaining Containment Gas Samples from the Containment Leak Detector During Emergencies 06/08/84 EP-235 2 Obtaining Reactor Water Samples from Sample Sinks Following EP-236 Accident Conditions 06/08/84 1 Obtaining Cooling Tower Blowdown Line Water

' Samples Following Radioactive Liquid 4

Release after Accident

" Conditions 06/08/84 EP-237 2 Ootaining the Iodine /

Particulate and/or Gas Samples from the North i

Vent Wide Range Gas Monitor (WRGM) 06/08/84 EP-238 2 Obtaining Liquid.Radwaste '

Samples from Radwaste Sample Sink Following Accident Conditions 06/08/84

EP-240 2 Obtaining Off-Gas i

Samples from the Air Ejector / Holdup Pipe Discharge Sample Station 06/08/84 SP-241 2 Sample Preparation and Handling of Highly Radioactive Liquid Samples EP-242 2 Sample Preparation and 06/08/84 Handling of Highly

  • Radioactive Particulate  !

Filters and Iodine Cartridges EP-243 2 Sample Preparation and -

06/08/84 Handling of Highly Radioactive Gas Samples EP-244 0 Offsite Analysis of 06/08/84 High Activity Samples

  • 06/08/84 EP-250 1 Personnel Safety Team Activation 06/08/84  ;

EP-251 1 Plant Survey Group i

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\., RGvision 7 07/17/84 EMERGENCY PLAN PROCEDURE INDEX PROCEDURE REV. -

DATE SIGNED DATE OF LAST 1 NUMBER NO. TITLE BY SUPER. PERIODIC REVIEW EP-252 1 Search and Rescue /First Aid 06/08/84 EP-254 1 Vehicle and Evacuee Control Group 06/08/84 EP-255 1 Vehicle Decontamination 06/08/84 2

EP-260 1 Fire and Damage Team Activation 06/08/84 EP-261 1 Damage Repair Group 06/08/84 EP-272 1 Philadelphia Electric Coqpany Officials 06/08/84 EP-273 1 Limerick Station Supervision Call List 06/08/84 EP-275 CANCELLED EP-276 1 Fire and Damage Team Phone List

~ 06/08/84 EP-277 .1 Personnel SaTety Team Phone List 06/08/84 EP-278 0 Security Team Phone List 12/27/83 EP-279 1 Emergency Operations Facility (EOF) Group Phone List 06/08/84 EP-280 1 Technical Support Center Phone List 06/08/84 EP-282 1 Government and Emergency Management Agencies 06/08/84 EP-284 1 Company Consultants and Contractors 06/08/84 EP-287 1 Nearby Public and ,

Industrial Users of Downstream Water 06/08/84 EP-291 1 Staffing Augmentation J 06/08/84 EP-292 1 Chemistry Sampling and ~ ~ ~ '

Analysis Team Phone List 06/08/84 EP-294 1 Dose Assessment Team Phone List -

06/08/84 EP-301 0 Operating the Evacuation '

Alarm and River Warning System 11/11/83 EP-303 2 Local Evacuation 04/02/84 l

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PROCEDURE REV.

  • NUMBER NO.

DATE SIGNED DATE OF LAST TITLE BY SUPER. PERIODIC REVIEW EP-304 2 Partial Plant Evacuation 07/09/84 EP-305 1 Site Evacuation 06/08/84 EP-306 0 Evacuation of the Information Center 12/27/83 EP-307 1 Reception and Orientation of Support Personnel 06/08/84 EP-312 0 Radioactive Liquid Release -

11/30/83 EP-313 1 Distribution of Thyroid Blocking Tablets 06/08/84 EP-315 0 Calculation of Offsite Doses During a Radiological Emergency Using RMMS in the Manual Mode 07/17/84 EP-316 0 Cumulative Population and Near Real-Time Emergency Dose

' Calculations for Airborne Releases Manual Method 12/23/83 EP-317 0 Determination of Protective Action Recommendations 12/27/83 EP-318 0 Liquid Release Dose Calculations Method for Drinking Water 11/30/83 EP-319 0 Fish Ingestion Pathway Dose Calculation 11/30/83 EP-325 0 Use of Containment Radiation Monitors to ,

Estimate Release Source Term 12/29/83 EP-330 1 Emergency Response Facility Habitability J 06/08/84 EP-401 1 Entry for Emergency Repair and Operations 06/08/84 EP-410 1 Recovery Phase Implementation 06/08/84 EP-500 1 Review and Revision -

of Emergency Plan 06/08/84 l

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PHILADELPHIA ELECTRIC COMPANY ,

2301 M ARKET STREET I J

P.O. BOX 8699 PHILADELPHI A. PA,19101 SHIELDS L. DALTROFF '

Luc'recra N"c ion August 17, 1984 Re: Docket Nos. 50-352 50-353 Dr. Thomas E. Murley Region 1 Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen:

Enclosed are two copies of Limerick Generating Station Emergency Plan Implementing Procedures. These procedures are submitted per regulations in 10 CFR 50, Appendix E, Section V.

The procedures being submitted are the following:

EP-222, Rev. 2 EP-315, Rev. 0 ,

Pursuant to Section 2.790 of the Commission's regulations, it is hereby requested that Whe names and telephone numbers listed in procedures EP-222, page 5 and EP-315, pages 6, 8, 12, 16, 18 and 19 be withheld from public disclosure. An

. affidavit setting forth the grounds _in support of this request is attached hereto.

2"2 E""*23es ##

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.  ; ~- q Dr. Thomas E. Murley Page 2 Mr. A. Schwencer Two copies have been sent under separate cover to the Document Control Desk.

Very truly yours,

//

~/b ,f aq, '

Enclosure cc: Docimant Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 Site Inspector - LGS See Attached Service List J

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COMMONWEALTH OF PENNSYLVANIA :

ss.

COUNTY OF PHILADELPHIA  :

S. L. Daltrof f, being first duly sworn, deposes and states as follows:

1. He is Vice President of the Electric Production Department, of Philadelphia Electric Company (hereinafter referred to as the " Company"); he is authorized to execute this Affidavit on behalf of the Company; and he has reviewed:

EP-222, Rev. 2 EP-315, Rev. 0 (hereinaf ter referred to as "the Documents") , and knows the contente thereof.

2. The part of the Documents which is sought to be withheld from public disclosure is the listing of the names and home telephone numbers of employees of the Company, direct-line work telephone numbers of employees of,the Company which are not listed in public telephone direc' tories, names and home and work numbers of emergency response support personnel and organizations.
3. To the best of his knowledge, information and belief, the names and telephone numbers set forth in the a

Documents.have been treated as confidential information and have been withheld from public disclosure by the Company.

4. The names and home telephone numbers in the Documents should be considered by the Nuclear Regulatory Commission as confidential and proprietary information and be withheld from public disclosure on the grounds that disclosure of the names and home telephone numbers of the employees of the Company and emergency support personnel could constitute an unwarranted invasion of the personal privacy of the individuals involved, disclosure of the work telephone numbers of the ,

Company's employees and of the emergency response personnel and organizations could adversely affect the capability of prompt no t i fic e'. t .n. In the event of an emergency; such disclosure is not required in the public interest; and such disclosure could adversely affect the interests of the Company and its ability to effectively implement the notification requirements of the Emergency Plan Procedures.

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Subscribed and sworn to J

before me this day of Notary Public JUDITH Y, FRANKUN Notary Putlic. Phita., Phila. Co.

My Commission Expires July 29,1987 6

l cc: Judge Lawrence B'renner I Judge Richard F. Cole Troy B. Connor, Jr., Esquire 4

Ann P. Hodgdon, Esquire Mr. Frank R. Romano Mr.. Robert L. Anthony Charles W. Elliot, Esquire zori G. Ferkin, Esquire Mr. Thomas Gerusky Director, Pennsylvania. Emergency Management Agency Angus R. Love, Esquire David Wersan, Esquire Robert J. Sugarman, Esquire .

Spence W. Perry, Esquire Jay M. Gutierrez, Esquire

' Atomic Safety & Licensing Appeal Board Atomic Safety & Licensing Board Panel Docket & Service Section Martha W. Bush, Esquire Mr. James Wiggins Mr. Timothy R. S. Campbell Ms. Maureen Mulligan-Judge Peter A. Morris J

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- [' h, UNITED STATES

-[g '[h E NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 j September 14, 1984 k,, . . .

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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 publicl available.

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. M. Felton, Director  !

f Division of Rules and Records'g,/g Office of Administration

Attachment:

As stated 9

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