ML20072K659
| ML20072K659 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 02/22/1983 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML113190871 | List: |
| References | |
| PROC-830222-01, NUDOCS 8303300685 | |
| Download: ML20072K659 (131) | |
Text
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- .-. Internal Corresoondence -
-Date February 18, 1983 e -
From G. D. Mathiasen Locanon Monticello - T* Special Distribution of Emergency Procedures tocan n Vari us Subject Revised Procedures for Emergency Procedures Book y Revisions to the Emergenc-f Procedures were reviewed in a recent Ooerations . Comittee Meeting. Listed below are the procedures superseded and revised. Other pages not revised my have been reprinted with the revised pages to
. facilitate updating the Book.
Superseded dages Procedure A.2-001 (Pages 1 through 28), Revision 4 Procedure A.2-101 (Pages-1 through 4), Revision 3 s O...j - Revised Pages P.rocedure A.2-00.1 (Pages 1 through 19), Revision 5 Procedure A.2-101 (Pages 1 through'46), Revision 4 ' h 4 lF Prepared by: Reviewed by: DdM ' Op. Com. Final Review: Meetih 1186 Date 2/17/83 Approved by: 4 // [ M Date 6;Z -/f-7.3
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<* oate February 18, 1983
-O G. D. Mathiasen .tocanon Monticello j rrom 7* Special Distribution of Frergency Procedures L can n Various
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suniect Revised Procedures for Fmergency Procedures Book Revisions to tile Baergency Procedures tere reviewed in a recent Ooerations Comittee Meeting. Listed below are the procedures superseded and revised. Other pages not revised my harp been reprinted with the revised pages to
. facilitate updating the Book.
Superseded Paces Procedure A.2-107, (Pages 1 through 12), Revision 4
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Prdcedure A.2-107 '(Pages 1 through 4), Revision 5 Prepared by: bdIlc (m e Reviewed by: MMM -- Op. Com. Final Review: Meeting # 1186 Date 2/17/83 Approved by: hkM
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. 4 m 3 Internal Corresoondence Jd' o t. February 18, 1983 no G. D. bbthiasen Location Monticello 7
Special Distribution of Emergency Procedures ' **"on Various sub i ect Revised Proce'd ures for Energency Procedures Book Revisions to the Emergency Procedures were reviewed in a recent Ocerations Connittee Meeting. Listed below are the procedures superseded and revised. Other pages not revised may have been reprinted with the revised pages to facilitate updating the Book. Superseded Pages None r he , s
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Revise ~d Pages~ ,
- l. Procedure A.2.-108, (Pages 1 through.11), Revision 0 -
l Procedtire A.2-209, (Pag'es 1 through 4), Revision. O Prepared by: bb hc k'w Reviewed by.: MMR -- Op.Com. Final'RevSew: Meet.ng.# i 1186 Date 2/17/83 Approved by: 'bdM6 Date 9 f 3
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INTERN,AL CORRESPONDENCE
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OATS Feb. 11, 1983 (']u N. P. Jepson '
. Loc ^rion Monticello J -
To Special Distribution of Energency Procedures LOCATION Various suweer . Revised Procedures for Energency Procedures Book Revisions to the Emergency Procedures were reviewed in a'recent Operaticns Committee Meeting. Listed below are the procedures superseded and revised. Other pages not revised may have been reprinted with the revised pages to facilitate updating the Book. d Superseded Pages , j 9 A.2 - 413, Pages 1 thro ~ ugh 6, Rev. O A.2 -'A14, Pages 1 through 13, Rev. O A 2 - MS, Pages 1 through 15, Rev. O A.2 416, Pages 1 through 6, Rev. O A.2 - 417, Pages 1 through 3, Rev. O Revised Pages
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A.2 - 413, Pages 1 through 6, Rev. 1 ' A.2 - 414, Pages 1 through 13, Rev. 1 A.2 - 415, Pages 1 through 5, Rev. 1 A.? C es - t iroug;1 Q,' lev. 2-- , .j es
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02/18/83 A.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES LIST OF CURRENT PAGES .
' . .. PROCEDURE PROCEDURE TITLE REVISION NUMBER l
000 Series Organization A.2-001 Emergency Organization . 5 100 Series Activation A.2-101 Classification of Emergencies 4 A.2-102 Notification of an Unusual Event 3 A.2-103 Alert 4 A.2-104 Site Area Emergency 3 - A.2-105 General Emergency , 3 A.2-106 Activation of Technical Support Center 3 A.2-107 Activation of Operations Support Center 5 A.2-108 Access Control During Emergencies 0 200 Series Assessment A.2-201 On-Site Monitoring and Protective Action Criteria 2 A.2-202 Off-Site Monitoring During an Emergency 1 A.2-203 Deleted 3-1-82 A.2-204 Off-Site Protective Action Recommendations 2 A.2-205 Personnel Accountability 1 A.2-206 Deleted'3-1-82 '
.A.2-207 Sampling Priorities During an Emergency 0 A.2-208 Core Damage Assessment 0 A.2-209 Responsibilities of Radiological Emergency Coordinator , 0
'N 300 Series Protective Actions
,,) A.2-301- Emergency Evacuation
- 1 A.2-302 Assembly Point Activation 2 A.2-303 Search and Rescue 2 i A.2-304 Thyroid Prophylaxis '
2
~400 Series. Radiological Surveillance and Control A.2-401 Emergency. Exposure. Control 2 A.2-402 Contamination Control 1 A.2-403 In-Plant Emergency Surveys- -
2 A.2-404 Airborne Iodine Sampling and Analysis 3 A.2-405 Release Rate Determination 2 A.2-406 Off-Site Dose-Projection 6 A.2-407 Personnel and Vehicle Monitoring 2 A.2-408- Sample Coordination During an Emergency 1 A.2-409 Self-Contained Breathing Apparatus (SCBA) Use During_An Emergency 0 A.2-410 Out-of-Plant Surveys 1 A.2-411 Establishment of Secondary Access Control 0 A.2-412 Deleted 1-6-83 ~ A.2-413 Small Volume Liquid Sample Obtained at the . Post Accident Sampling System 1 A.2-414 Large Volume Liquid Sample and/or Dissolved Gas Sample Obtained at Post Accident Sampling System 1 A.2-415 Containment Gas Sample Obtained at Post ./ 4, , Accident Sampling System E 1'
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02/18/83 A.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES LIST OF CURRENT PAGES ,
. , . PROCEDURE PROCEDURE TITLE REVISION NUMBER
' ~1 400 Series
'- / Radiolooical Surveillance and Control (Cont'd.)
A.2-416 Containment Iodine and Particulate Samples . Obtained at Post Accident Sampling System 1 . A.2-417 Draining the Trap, Sump and Collector of Post Accident Sampling System 1 A.2-418 Post Accident Sampling Station Demin Water Tank Fill Procedure 0 A.2-419 Liquid Radiochemical Analysis 0 A.2-420 Containment Atmosphere Radiochemical Analysis 0 A.2-421 Containment Atmosphere Iodine / Particulate Analysis 0 A.2-422 Stack Iodine / Particulate Sampling & Analysis 1 A.2-423 Reactor Building Vents Iodine / Particulate Sampling and Analysis 1 A.2-424 EOF Count Room Counting Procedure 0 A.2-425 Post-Accident Gas Sample Line Heat Trace 0 500 Series Communications and Documentation A.2-501 Communication During an Emergency 1 A.2-502 Recordkeeping During an Emergency 0 A.2-503 Emergency Reports and Documentation 0 600 Series Re-Entry and Recovery _ _ _ _ A.2-601 Re-Entry s 0 A.2-602 Deleted 11-19-81
?) A.2-603 Repair an" Corrective Action. ~1 700 Series A.2-702 Response to an Emergency at Prairie Island 2 A.2-703 Response to Off-Site Situation Involving Radioactive Materials 0 l
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Procedure A'.2-415 Revision 1 Page 1 of 6 Op. Com. Rev. Req'd. Yes X No
, Q.A. Review Reg'd.. Yes No X 3 ALARA Review Reg'd. Yes. X No
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, CONTAINMENT GAS SAMPLE OBTAINED AT POST ACCIDENT SAMPLING SYSTEM Procedure A.2-415 Prepared by: c 7-set _ ALARA Review: ON//lf -
Date 12 /J S Reviewed by: 7M,Maf/:'dV% Q.A. Review: Revision 0 Date 8/16/82 Operations Co:rmitIee Final Review: Meeting Number,: //f7 Date 2/v/G Approved by: d d SAA Date 1-QQ-23 Op. Com. Results Review: Not Requited Mtg. # 1100 Date 7/29/82 PURPO'SE The purpose of this procedure is to provide special instructions and precautions' for collection asd handling of containment gas samples during and following an ' emergency at Monticello Nuclear Generating Plant. ! CONDITIONS AND PREREQUISITES _, ' The Emergency Director / REC /CSL has requested analysis of torus, drywell or secondary containment (935') gas samples. Actual or potential radiological conditions are such that special methods and/or precautions are necessary in order to collect and analyze samples under conditions
.which may present a much greater than normal radiation hazard to individuals performing the sampling and analyses. Unless directed otherwise, this precedure should be used in lieu of. routine sampling and analysis procedures whensver an Alert or higher. emergency classification is declared. '
- .The torus and drywell. gas sample line h' eat tracing should be~on per' Procedure - '
A.2-425. If a Group 2 isolation signa 1 exists refer to Operations Manual Section B.4.1 for instructions to opening the samples valves in STEP 1 of this procedure. ORGANIZATION AND RESPONSIBILITIES Emergency Director - Overall responsibility REC /CSL - . Responsible for assigning sample priority and frequ'ncy e and results review. Chemistry Technicians Responsible for sample collection, analysis and results reporting. x PRECAUTIONS A. ~ Exposures of sampling and analysis personnel shall be in accordance with A.2-401, " Emergency Exposure Control". WP/kk X
e Procedure A.2-415 Revision 1 .- ' Page 2 bf 6 . PRECAUTIONS (Cont' Q B. Exposure to all personnel due to sampling and analysis operations should be maintained as low as is reasonably achieveable. Techniques such as temporary shielding, remote handling and sample dilution prior to analysis should be considered to. reduce exposure to personnel. C. When actual or potential radiation levels so warrant, high range portable survey instruments, and self-reading dosimeters shall be provided to sampling and analysis personnel to permit rapid assessment of high exposure rates and accumulated personnel exposure. Alarming dosimeters should also be considered. D. Appropriate extremity dosimeters should be provided and worn when handling
. samples which themselves represent high level radiation sources.
E. ' Calculations for exposure rates resulting from radiation within a few hours after a loss of Coolant Accident point out the desirability of spending mini-mum amount of time that is necessary near the surface of the sample enclosure. Most of the operation of the Post Accident Sampling System located at 951' of Turbine Building can be performed from the control panel. With the control panel located ten or more feet' away from the sample enclosure the dose rates at the control panel due to radiation from the sample enclosure will be below 100 MR/HR. The indicator for the area radiation detector RE-507 is on the PASS control panel and its reading should be noted whenever the presence of radiation is suspected. 3 g REMARKS ,
- 1. Prior to sampling notify the Control Room and advise Shift Supervisor of
, your intentions.
- 2. The Post. Accident Sampling Station is 1.ocated -on the south ' sideo ' f the 951 level of the Turbine Building. The most efficient route to the PASS
.is through access control and into the Turbine Building.. Move to the 951'
' level via the east stairway'.
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- 3. Two-man teams should be used to obtain a post-accident sample when possible.
, 4. Obtain controlled access key 33A from R.P. Coordinator and key #153 from I
, Shift Supervisor.
EQUIPMENT REQUIRED '
- 1. 15 ml sample vial .-
- 2. Gas vial positioner
- 3. Gas vial carrying cask
- 4. Needles
- 5. Neoprene cap l 6. Needle changing tool
- 7. Flashlight
- 8. Vial retainer ring crimper g
- 9. Aluminum retainer ring .s WP/kk m s w = wo*ew_ me
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Page 3 of 6
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Tt PROCEDURE , ,
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STEP 1 Call Control Room and request an operator open the following valves depending on the sample desired (the opening of these. valves shall be documented on the attached checklist): Sample Valves Control Panel Drywell ?- SV-4020A C259 (High) ,SV-4001A C259 SV-4004A. C259 .. , SV-4005A C259 Torus SV-4002A C259 SV-40'03A C259 SV-40028 C260 SV-4003B ; C260 SV-4004A C259 SV-4005A C259 - STEP 2 Open'the nitrogen supply and regulate the supply pressure to 100 psi. STEP 3 Turn on ventilation unit by depressing " START" button. Verify vacuum by feeling suction at one of the. gas ports. STEP 4 Set switch HC-600 to position A if not already done. With the " Sump - 3 Dra'in System Switch" (HC-715) in the off position place switch HC-700 . - (Liquid / Gas Selector) in the " Gas" position. STEP 5 Install the gas filter drawer into position. STEP 6 Place a standard 15 milliliter off gas vial with rubber septum into
.the gas vial positioner, slide 1the. positioner into the gas port.(the higher of the two ports) at the sample station and turn it to lock it' into place. Observe that the bottle status 1 Ajht changes from red to green. ,
STEP 7 Turn the " Gas Sample Selector Switch" (HC-723) to the desired sample location. In addition set switch HC-500 to the position correspond-ing to the sample desired.
, STEP 8 Turn the "15 ML Gas Sample Switch" (HC-705) to position 2 and " Circulate Gas" for a minimum period of 5 minutes. Be sure that there.is flow as read by the rotameter through the sample enclosure window (FI-725).
Record flow and. flush duration on the Containment Gas Sampling and Ar.alysis Checklist, Form #5790-415-1. ~ STEP 9 Turn HC-705 to position 3 and " Evacuate" the off gas vial. Record the pressure of the evacuated iTial (PI-708) on the checklist. (Make sure the vacuum in the gas vial _ reaches a stable minimum reading before recording pressure.) - STEP 10 Turn HC-705 to position 4 "Take Sample". Observe that the pressure m}
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reading on PI-708 does not change as such would indicate a system leak. WP/kk
P6:c: dure A.2-415 Revision 1 .- ~:
, Page 4 of 6 ,
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PROCEDURE (Cont'd.) , Q v/ STEP 11 Press the button to the left of HC-705 (HC-720 " Press for Sample") to obtain a sample. Keep this button depressed until a steady pressure is reached. This will require approximately 5 seconds. Record the final pressure of the sample (PI-708) on the checklist. This pressure corre-sponds to the actual pressure of the sample being obtained. Record ^- sample temperature (TI-724) on the checklist. STEP 12 . Turn HC-705 to position 5 " FLUSH SYSTEM" and flush for approximately 1 minute or until the area radiation monitor located on the sample l , station reaches a minimum. ' STEP 13
- Turn HC-705 through position 6, 7 and 8 and then straight up to "0FF". !
STEP 14 Turn to unlock and withdraw.the gas vial positioner. Keep the vial at a maximum distance and quickly insert the sample bottle into the gas vial cask. Close and latch the gas vial cask. Put the gas vial positioner back into the port in the sample statiorr. STEP 15 Perform the Drain, Sump and Collection procedure (Procedure A.2-417). STEP 16 Call Control Room and request that an operator close the valves that were opened in STEP 1 (the closing of these valves shall be documented on the attached checklist). s STEP 17 Turn ventilation of.f by depressing "STOP" button. ) y STEP 18 Transport the sample to the hot lab for dilution and counting per Containment Atmosphere Radiochemical Analysis, Procedure A.2-420, or for hydrogen, oxygen and nitrogen per Chemistry Procedure I.1.36. STEP 19 Calculate the sample v'olume'(see NOTE 1) at the sample pressure and temperature as recorded in STEP 11 and record on Containment Gas Sampling and Analysis Checklist. c . NOTE 1 Temperature and pressure values must be converted to units of
" Kelvin and atmospheres prior to calculating gas volume.
= atmosphere .
0 h*("F-32)+273.15=" Kelvin
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14.9 x P1 x 298.15 = actual sample volume (cc) b Where P1 = final sx pressure (atm)-absolute pressure of vial (atm) T1 = TI-724 (converted to " Kelvin) c
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nj) Form 5790-415-1 Revision 1, 02/18/83
-4 Example of '
s' Pape 1.of 2 CONTAINHENT GAS SAMPLING AND ANALYSIS CHECKLIST p, Sampling , Initial
- 1. Sample Source -
Date Time ' RPS
" , '2. Sample Identification No.
- 3. , Sample Flow .
FI-725 Flush Duration Min.
- 4. i qbsolutePressureof/ial PI-708 (psia)
- 5. Hnal Sample Pressure ~
- PI-708 (psia)
- 6. Sample Temperature -
TI-724 (F)
- 7. Calculated Sample Volume cc (As Calculated)
- w Open the following valves corresponding to the desired sample (STEP 1 of procedure). '
? . Valve Opened Verified - By By Sample Valves Control Panel (Operator) (RPS) Drysell SV-4020A C259 - q, ' (High) SV-4001A. C259 U. / SV-4004A C259 SV-4005A C259 _ . s
. Torus SV-4002A C259 ~.
SV-4003A C259 .
. SV-40028 C260' .
SV-4003B C260
. SV-4004A - C259 SV-4005A C259 s
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3 y 'rocedura \ A.2-415 P Revision 1 .' - 1 Page 6 of 6 . 4 Form 5790-415-1 Revision 1, 02/18/83. s ]4- , Page 2 of 2 \
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, Close the following valves corresponding to the desired sample (STEP 16 of procedure).
I' Valve Closed Verified Bp By Sample Valves Control Panel (Operator) (RPS) 1 Drywell SV-4020A C259 SV-4001A C259
- , SV-4004A C259
. SV-4005A C259 i Torus SV-4002A C259 i
SV-4003A C259 SV-4002B C260 SV-40038 C260.. SV-4004A C259 - s
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Analysis
- 1. Spectrum Ran (Oilution Factors x )
- 2. Spectrum Analyzed
- 3. -Activity Calculated 'pCi/cc '
j 4. .%H 2 .0 2 -N 2 (See Chemistry Procedure I.1'.36) '
- 5. Other analysis results as requested and comments:
( ~ . . . l Performed By: - Date: - Reviewed by: CSL or REC Date: NOTE: After this checklist is completed and is not required for immediate use, it shall be placed in the appropriate container provided for Emergency Records. z.g i
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Procedure A.2-416
- Revision 1 Page 1 of 8 Op. Com. Rev. Reg'd. Yes X No Q.A. Review Req'd. Yes No X
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ALARA Review Reg'd. Yes X No CONTAINMENT IODINE AND PARTICULATE SAMPLES OBTAINED AT POST ACCIDENT SAMPLING SYSTEM Procedure A.2-416 Prepared by: .h ALARA Review: ud d - Date Z[tz/.f} Reviewed by: M Meldf/f Q.A. Review: Revision 0 Date 8/4/82~ Operations Committee Final Review: Meeting Number: # 5'7 Date #D/fy Approved by: NdM Date # 20,S5 Op. Com. Results Review: Not Required Mtg. # 1100 Date 7/29/82 PURPOSE The purpose of this procedure is to provide special instructions and p'recautions for collection and handling of iodine and particulate samples during and follow-ing an emergency at Monticello Nuclear Generating Plant. CONDITIONS AND PREREQUISITES The Emergency Director / REC /CSL has requested iodine / particulate analysis of torus, drywell or secondary containment-{935') gas samples. Actual or potential radiological conditions are such that special. methods and/or precautions are necessary in order to collect and analyze samples under conditions which may present a much greater than normal radiation hazard to individuals performing the sampling and analyses. Unless directed otherwise, this procedure should be used in lieu of routine sampling and analysis procedures whenever an Alert or higher emergency classification is declared. The torus.and drywell gas sample line heat' tracing shoul'd be' on per Procedure A.2-425. If a Group 2 isolation signal exists refer to Operations Manual Section' B.4.1 for # instructions to opening the sample valves in STEP 1 of this procedure.
, ORGANIZATION AND RESPONSIBILITIES Emergency Director - Overall responsibility REC /CSL - Responsible for assigning sample priority and frequency and results review.
Chemistry Techni'cian - Responsible for sample collection, analysis and re$lts reporting.
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PRECAUTIONS
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A. Exposures of sampling and analysis personnel shall be in accordance with
] A.2-401, " Emergency Exposure Control".
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Procedure A.2-416 R: vision 1 . Page 2 of 8 PRECAUTIONS (Cont'd.) , B. Exposures to all personnel due to sampling and analysis operations should be maintained as low as is reasonably achieveable. Techniques such as temporary shielding, remote handling and sample dilution prior to analysis should be considered to reduce exposure to personnel. C. When actual or potential radiation levels so warrant, high range portable survey instruments, and self-reading dosimeters shall be provided to sampling and analysis personnel to permit rapid assessment of high exposure rates'and accumulated personnel exposure. Alarming dosimeters should also be considered. D. Appropriate extremity dosimeters should be provided and worn when handling samples which themselves represent high level radiation sources. E. Calculations for exposure rates resulting from radiation within a few hours . after a Loss of Coolant Accident point out the desirability of spending mini-mum amount of time that is necessary near the surface of the sample enclosure. Most of the operation of the Post Accident Sampling System located at 951' of Turbine Building can be performed from the control panel. With the control panel located ten or more feet away from the sample enclosure the dose rates at the control panel due to radiation from the sample enclosure will be below 100 MR/HR. The indicator for the area radiation detector RE-507 is on the PA_SS control panel and its reading should be noted.whenever the presence of radiation is suspected. REMARKS /
- 1. Prior to sampling notify the Control Room and advise Shift Supervisor of your intentions.
2.' The Post Accident Sampling Station is located on the south side of the 951' level of the Turbine Building. The most efficient route to the PASS is , through access control and into the Turbine Building. Hove to the 951'- l level via the e'ast stairway. l 3. Two-man teams should be used to obtain a post-accident sample when possible.
- 4. Obtain controlled access key 33A from R.P. Coordinator and key #153 from Shift Supervisor.
l l EQUIPMENT REQUIRED
- 1. ' Silver zeolite cartridges (4) .
- 2. Particulate" filters l 3. Sample carrying cask
- 4. Poly bag (medium)
- 5. Radector III or equivalent i
PROCEDURE STEP 1 Call the Control Room and request that an operator open the following valves depending on the sample desired (the opening of these valves shall be documented on the attached checklist): [ __.,. . . _ , , . . -,,i,
l . .. , Procedura A.2-416 Revision 1 Page 3 of 8
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PROCEDURE Sample Valves . Control Panel Drywell SV-4020A C259 (High) SV-4001A C259 SV-4004A ' C259 - SV-4005A C259 Torus SV-4002A C259 SV-4003A ' C259 SV-40028 C260 SV-40038 C260 SV-4004A C259 . SV-4005A C259 STEP 2 Open the nitrogen supply and regulate the supply pressure to 100 psi. STEP 3 Turn on ventilation unit by depressing " START" button. Verify vacuum by feeling suction at one of the two gas ports.
. STEP 4 Set switch HC-600 to position A if not already done. Set sw' itch HC-500 to the position corresponding to the sample desired.
STEP 5 Verify that the " Sump Drain System" (switch HC-715) is in the OFF position. Place switch HC-700 (Liquid / Gas Selector) in the Gas i position.
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NOTE 1 See Attachment 1 for a description of filter cartridge retainer.
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STEP 6 Pull out the gas filter drawer and check th'e filter cartridges. If not already in place, put the 4 filter cartridges (numbered 1 through 3 4) into the cartridge retainer, and a particulate filter paper in the cap of the cartridge retainer. Then put the cartridge retainer into the gas fi.lter drawer and put the drawer into the sample station and
' verify that the drawer position' light is , green.
STEP 7 If a h.igh activity condition exists or is suspected a timed sample should be taken. For a timed sample set the timer KC-712 between the range of 0 to 30 seconds. Select a low enough time so that the l activity on the filter cartridge will not be unnecessarily high and cause special handling problems. It is suggested that 5 seconds be used for the first try. Observe the RE-704 reading to determine if there is a rapid activity buildup. (This reading will also include non-adsorbing gases.) If the activity level does not exceed a preset l value bf 10 mR/hr, another timed flow through the cartridges can be made. Record the selected time on the Iodine / Particulate Sampling and Analysis Checklist, Form #5790-416-1 or record that the sample is l untimed. Set the switch located to the left of the timer labeled
" Time Sample" on either yes or no as appropriate. If the activity
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Page 4 or_ 8 , PROCEDURE (Cont'd.) 9.J of the fi*st' filter is > 10 mR/hr the 2nd, 3rd or 4th filters may be xx esed for counting assuming previous filters are 99% efficient. s STEP 8 Turn the " Gas Sample Selector Switch" (HC-723) to the desired sample source. STEP 9 Turn the " Iodine Cartridge Sample Switch" (HC-712) to position 2 and
" Circulate Gas" for a minimum period of 5 minutes. Record the flush time on the checklist.
STEP 10 Observe flow as read by the rotameter which is visible through the window in the sample station enclosure. Record the flow (FI-725), temperature (TI-724) and pressure PI-726 and PI-727 on the checklist. The two pressure gauges (PI-726 and PI-727), as read through the window, should be the same.
.When the switch HC-712 is turned to position 3 the sample gas will start to flow throu>;h the filter cartridges. When the tpstream pressure (PI-727) is > 16 inches of Hg. and PI-726 is about 0 inches l of Hg, the flow will be " critical". Foi a short duration timed cycle it will be necessary to have,one technic.ian ready to read the down-i stream pressure gauge at the sample station while another turns the selector switch at the control panel in order-to verify that the flow is " critical". When ready, turn switch HC-712 to position 3. On the %
checklist record pressure PI-727, PI-726 and the sample time duration 'j in seconds. If flow is not critical record flow as indicated by FI-725. i STEP 11 After the timer has timed out for a timed sample or after'the appropriate ~ time has elapsed for a non-timed sample, turn selector switch HC-712 to
, position 4 to evacuate the filter' cartridge.
STEP 12 After approximately.10 'econds s turn swi.tch HC-712 to position 5.which will admit an' air.or nitrogen flush thrcugh the filter cartridge to
- remove Krypton and Xenon gases. This purge should last approximately 20 seconds or until RI-704 is stable. Read and record RI-704 on the checklist.
l STEP 13 Rotate HC-712 to its up and off position. Turn other switches off. Withdraw the filter drawer and remove'the cartridge retainer and put it into a plastic bag. Close the bag and tie or tape it closed. Put the filter drawer back into the sample . enclosure. CAUTION:. No shi'elding cask is provided for the cartridge retainer and fiiter(s). Survey the plastic bag which contains the sample and determine the dose rate. Use tongs to increase your distance from the sample. At the hot lab remove the filte'r cartridges. STEP 14 Perform the Orain of Trap, Sump and Collector Procedure (Procedure A. 2-417.) .
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Proc: dura A.2-416 Revision 1
, . Page 5 of 8
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PROCEDURE (Cort'd.) , STEP 15 Call Control Room and request that an operator close the valves that were opened in STEP 1 (the closing of these valves shall be documented on the attached checklist). STEP 16 Turn ventilation off by depressing "STOP" button. STEP 17 Transport the cartridge retainer to the hot lab for preparation for radiochemical analysis per Procedure A.2-421. STEP 18 Remove the filter cartridges and label 1, 2, 3 and 4. Install new particulate and silver zeolite cartridges into the cartridge retainer for the next s' ample. h
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' Revision 1
- Page 6 of 8 Attachment 1 O Page 1 of 1
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CUT AWAY VIEW OF FILTER CARTRIDGE NOTE: STAND ALONE
. NUMBERS ARE O-RlN G S.
PARTICULATE FILTERS & HOLDERS 1, ,
^ 2.
f A 3,
-CARTRIDGE 9 9 " 1 2. 3 h
%- 3 L/M l l
2
.:p .(( l.,-j l a2 OReiCE:
j (- [ FLOW FLOW FLOW FLOW - ^
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PART CULATE- ^I"
. - (4) SILVER ZEO' LITE -
(.003 INCH S.S. . FILTERS SCREEN) - FILTER PAPER a . e e
' NOTE: Place cartridge into sample drawer with orifice end to the fixed butting surface. -
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. Revision 1 Page 7 of 8
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Form #5790-416-1 . Example of '
]' Revision 1, 02/18/83 Page-1-o L2 IODINE / PARTICULATE SAMPLING AND ANALYSIS CHECKLIST SAMPLING
- 1. Sample Source Date Time RPS
- 2. Sample Identification No.
- 3. Time Sample YES or NO '
- 4. Flush Time in Minutes-
- 5. Sample Flow SCFM FI-725 (not through cartridge)
Temperature TI-724 ("F) Pressure PI-726 (psia) Pressure PI-727 (psia)
- 6. Pressure PI-726 (flow through cartridge)
Pressure PI-727 (flow through cartridge) If flow not critical, Sample Flow SCEM , FI-725 i If flow critical flow is 3 liters / min. , 7 Flow Duration Seconds Radiation
~
- 8. RI-704 (mR/hr)
Open the following valves corresponding to the desired sample (STEP 1 of Procedure):
~
j . Valve Opened Verified' by by [ Sample Valves Control Panel (Operator) (RPS)
'Drywell SV-4020A - C259-SV-4001A _ C259 SV-4004A -
C259 SV-4005A , C259 1 I Torus SV-4002A C259 s
.SV-4003A C259 -
SV-40028 C260 l l SV-40038 C260 l SV-4004A C259 l SV-4005A C259 1 , ,. . b
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Procedura A.2-416 Revision 1 -
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. Page 8.of 8 , .-
Form #5790-416-1 Revision 1, 02/18/83 r]s Page 2 of 2 , Close the following valves corresponding to the desired sample (STEP 15 of procedure): Valve Closed VerifiG~d'T " by by Sample Valves Control Panel (Operator) (RPS) Orywell SV-4020A C259 SV-4001A C259 SV-4004A C259
. SV-4005A C259' Torus SV-4002A C259 SV-4003A C259' SV-40028 C260 SV-4003B C260 SV-4004A C252 ,
SV-4005A C259 - ANALYSIS Initial
)
A. IODINE
- 1. Spectrum Collected
- 2. Spectrum Analyzed
. 3. Sampl.e Volune cc
- 4. Activity Calculated pCi/c'c
- 5. Filter Number Counted (1-4)
B. PARTICULATE
- 1. Spectrum Collected
- 2. Spectrum Analyzed
! 3. Sample Volume cc
- 4. Activity Calculated pCi/cc C. Other Analysis Results as Requested and Comments:
~
Performed by: Date Reviewed by: CSL or REC Date NOTE: After this checklist is completed and is not required for immediate use, it shall be placed in the appropriate container provided for Emergency Reco WP/kk
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4 - - \ 02/18/83 A.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES
/ LIST OF CURRENT PAGES
* ~
- PROCEDURE PROCEbuRETITLE -
REVISION NUMBER 000 Series Organization N A.2-001 Emergency Organization 5 - x
\ 100 Series Activation A.2-101 Classification of Emergencies 4 A.2-102 Notification of an Unusual Event 3
'A.2-103 Alert 4
, A.2-104 Site Area Emergency 3 A.2-105 General Emergency 3 A.2-106 Activation of Technical Support Center 3 . -
A.2-107 Activation of Operations Support Center 5 A.2-108 Access Control Ouring Emergencies 0 200 Series Assessment i A.2-201 On-Site Monitoring and Protective Action Criteria 2 A.2-202 Off-Site Monitoring During an Emergency 1
,_ A.2-203- Deleted 3-1-82 -
A.2-204 Off-Site Protective Action Recommendations 2 A.2-205 Personnel Accountability 1 A.2-206 Deleted 3-1-82 A.2-207 Samp~1ing Priorities During an Emergency 0 A'2-208
. Core. Damage Assessment 0 A.2-209 Responsibilities of Radiological Emergency Coordinator s 0 Q
v 300 Series A.2-301 Protective Actions Emergency Evacuation 1 A.2-302 Assembly Point Activation 2 A.2-303 Search and Rescue 2 - A.2-304 Thyroid Prophylaxis 2 400 Series Radiological Surveillance and Control
.A.2-401 Emergency Exposure Control 2 A.2-402 Contamination Control. 1 ,
. A.2-403 In-Plant Emergency Surveys . 2 A.2-404 Airborne Iodine Sampling and Analysis 3 A.2-405 Release Rate Determination -
2 l A.2-406 Off-Site Dose Projection 6 l A.2-407 Personnel and Vehicle Monitoring 2 A.2-408- Sample Coordination During an Emergency 1 l A.2-409 Self-Contained Breathing Apparatus (SCBA) Use l During An Emergency 0 A.2-410 Out-of-Plant Surveys 1 l A.2-411 Establishment of Secondary Access Control 0 .. l A.2-412 Deleted 1-6-83 l A.2-413 Small Volume Liquid Sample Obtained at the
- Post Accident Sampling System 1 l A.2-414 Large Volume Liquid Sample and/or Dissolved Gas Sample Obtained at Post Accident Sampling System 1 l A.2-415 Containment Gas Sample Obtained at Post (,
hf- Accident Sampling System ' 1 l l - i - 4 AAA056 y ~ '- v w w yr=- y. == r wr- w e---w-emw--------ww-- v--m-----*-+ - - - - ' '-- = -"T---'"'-'--- - - - - - + = - - - - - - - - - - + ' - - - - - - - -
02/18/83 A.2 EMERGENCY PLAN IMPLEMENTING PROCEDURES
, LIST OF CURRENT PAGES , <
PROCEDURE PROCEDURE TITLE , REVISION NUMBER O 400 Series A.2-416 Radieieoicei Survetiience end Centrei (Cont'd.) Containment Iodine and Particulate Samples Obtained at Post Accident. Sampling System 1 A.2-417 Draining the Trap, Sump and Collector of Post Accident Sampling System _ 1 A.2-418 ' Post Accident Sampling Station Demin Water Tank Fill Procedure 0 A.2-419 Liquid Radiochemical Analysis . 0 A.2-420_ Containment Atmosphere Radiochemical Analysis 0 A.2-421 Containment Atmosphere Iodine / Particulate Analysis . O A.2-422 Stack Iodine / Particulate Sampling & Analysis 1 A.2-423 Reactor Building Vents Iodine / Particulate Sampling and Analysis . 1 A.2-424 EOF Count Room Counting Procedure 0 A.2-425 Post-Accident Gas Sample Line Heat Trace 0 500 Series Communications and Documentation A.2-501 Communication During an Emergency 1 A.2-502 -Recordkeeping During an Emergency 0 A.2-503 -Emergency Reports and Documentation 0 600 Series Re-Entry and Recovery . A.2-601 Re-Entry 0 A.2-602 Deleted 11-19-81 A.2-603 Repair and Corrective Action 1 700 Series
- A.2-702 Response to an Emergency at Prairie Island 2
- A.2-703 Response to Off-Site Situation Involving Radioactive Materials 0 4 S 1
l . 1 . l 3
- ii -
AAA056 I I -
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s Procedure A.2-001 Revision 5 Page 1 of 19 s Op. Com. Rev. Reg'd. Yes X No Q. A. Review Req'd. -Yes No X Q ALARA Review Req'd. Yes No X
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EMERGENCY ~ ORGANIZATION A.2-001 REVIEW AND APPROVAL Prepared by: b3 ///a# A~ ALARA Review: G. D. Mathiasen Date 11/17/81 Reviewed by: Y$"M_ Q.A. Review: R. L: Scheinost Date 11/17/81 OperationsCommitteeFinaIReview: Meeting Number // Y G Date c2// ; /J3 Approved by: - 88[d ' Date o?-/3 if3 0p. Com. Results Review: Not Required Mtg. 1086 Date 5/27/82 ~ PURPOSE The purpose of this procedure is to describe the on-site Emergency Response Organization (ERO) and to provide an orderly method of staffing the positions of which the ERO is comprised. - PRECAUTIONS NoMonticelloNuclearGeneratingPlantpeSsonnelshallmakeanyinformation releases to members of the news media or the general public during an emergency
,') unless cleared through the Emergency Manager, if established, or Emergency Director. Direct all inquiries to the Communications Department at NSP Head-quarters or at the EOF. -
DISCUSSION A. Although.it is not practical to. develop detailed procedures e_ncompassing every conceivable emergency situation, advance planning should create a high order of preparedness and ensure an orderly and timely decision-mancing
' body. Advance planning of the' Emergency Organization en'sures that during an emergency the duties of the plant staff members, who are required to direct the emergency effort, are defined. (See Figure.1)
B. The Emergency Organization is herein described. The duties and responsi-bilities of.the individual Emergency Organization members are defined. C. The Tag Boards are used to make speedy personnel duty assignments during the initial stage of an emergency, to insure that qualified personnel fill the positions in the ERO, and insure that the more important positioryi in
.the ERO ard~ filled first. '
The Main Tag Board consists of a board with a layout of the Emergency Response l Organization. Under each position on the board is a list of the individuals who are qualified to fill that position, and a tag with the necessary instruc-tion for filling that position. There is also a sign-in sheet that serves to indicate who has taken a specific tag from the Tag Board.
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Procedure A.2-001 Revision 5 - ~"
,_ Page 2 of 19 The Main Tag Board is located outside the Supt. of Operations office. The /N RP Tag Board is at acc'ess control. All personnel who are riismbers (.f the ERO ../
have the responsibility of checking the Tag Boards when it is annoJnced that ERO personnel are to report to their duty stations. ' The Tag Board system is designed to wark as follows: When an announcement is made to activate the ERO duty assignments, ERO personnel should pass by the appropriate Tag Boards (see below lists). If
, an individual's name is on one of the lists for a position in the ERO, and the tag for that position has not been removed, he should remove that tag, read the instructions on the tag, and sign the sign-in sheet indicating ,
the position in the ERO that is being filled. If an individuals name / appears on more than one list the individual must determine which of the " positions should be filled first and remove the appropriate tag. (If you have a question as to the priority of filling positions contact the Emer-gency Plan Coordinator.) ' If an individual arrives at the Tag Board and. finds the tag is removed for a position they are qualified to fill, the person should check the sign-in sheet and determine if they are higher on the order of succession than the person performing that job. If so they should relieve that individual. Main Tag Board RP Tag Board Emergency Director RPS' Personnel Radiological Emergency Coord. -
-)
Group Leaders
~ '
STA's
- > SEC's ~
( D. It is the Emergency Director's' responsibility.to ensure 24-hour. coverage of key positions in the emergency organization. He must consider that the emergency may continue for some time and " pace". the utilization of personnel, resources (e.g. , ' ensure rotation of hers~onnel to allow ti'me for eating and l-l sleepirig). E. While the qualification criter'ia listed in this procedure will be used to determine who may be qualified to fill a given emergency organization position, it is not intended that a person who is not qualified may not be l assigned to that position. The goal should be to have several people I qualified to fill each position, but if there is no one available from the
- qualified list, the most qualified person available should be selected.
l Req'ualification, when applicable, will be required on an annual (1 3 3onths)' - basis. This procedure will be reviewed quarterly, and revised if necessary. '
. F. In the periods between revisions.of this procedure, personnel who become qualified may be used to staff these positions.
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, Page 3 cf 19 QUALIFICATION. ORDER OF SUCCESSION ANO DUTIES C '
I. Coordinationand'0(rectionGroup N x N .A. Emergency Director
- 1. Qualifications .
- a. Fivs years experience at Montiicello Nuclear Generating Plant NOTE: This requirement does not apply during initial phase of emergency when the Duty Shift Supervisor is Emer-gency Director.
- b. Experience as Plant Manager Designee t'
NOTE: This requirement does not apply during initial phase of emergency when the Duty Shift Supervisor is Emer-
. gency Director.
, c. Knowledgeable or qualified in following areas: ,
- Corporate Emergency Plan
- Monticello Emergency Plan
- Emergency Implementing Procedures:
( A.2 - 001 (. A.2 - 101 A.2 - 303 A.2 - 102 A.2 - 304 A.2 - 103 A.2 - 401 A.2 - 104 A.2 - 501 A.2 - 105 A.2 - 502 A.2 - 204 A.2 - 503 ' A.2 205 ' A.2 - 601 A.2 - 301 A.2 - 603
~
- Safeguards Contingency Plan. Implementing Procedures SCPIP - 1 SCPIP - 8 SCPIP - 2 SCPIP - 12 SCPIP - 4
- 2. Qualified Personnel in Order of Succession DELETED l
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Procedure A.2-001 .. Revisien 5 - Page 4 of 19
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- 3. Duties
- a. Coordinates the response of the plant emergency organization;
- b. Evaluates plant and radiological conditions;
- c. Ensures assessment-of offsite radioactivity releases;
- d. Recommends offsite protective actions;
- e. Determines emergency classification; l f. Calls in additional plant personnel; .
- g. Assumes control of Technical Support Center personnel and activities;
- h. Makes decisions regarding habitability of emergency response
. centers and location of assembly areas;
,i. Approves radiation exposures in excess of normal limits;
- j. Ensures all injured personnel receive medical assistance; and
- k. Ensures 24-hour coverage for key positions of plant emer-gency organization. -
- 8. Shift Technical Advisor (.
j 1. Qualifications
~
Qualified per 4 AWI-4.7.1
- 2. Qualified Personnel ..
l l ' DELETED i l
- 3. Responsibility' Provide technical operational advice to the Shift Supervisor.
C. Shift _ Emergency Communicator
- 1. - Qualifications
- a. Six months experience at Monticello - -
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~* Procedure A.2-001 Revision 5
, Page 5 of 19
. b. Ability to communicate verbally in clear, concise manner C. c. Knowledgeable or qualified in following areas:
- Emergency Implementing Procedures:
A.2 - 101 A.2 - 105 . A.2 - 102 A.2 - 106 A.2 - 103 A.2 - 501 A.2 - 104 A.2 - 502
- Emergency Plan (Knowledgeable to degree necessary to be able to direct others in use of procedures)
- d. Other administrative qualifications as determined by Plant Management.
- 2. Qualified Personnel i
DELETED l i_ . 3
- 3. Duties
- a. Assists Emergency Director in emergency classification;'
- b. Conducts initial and followup notification in accordance with proceduresf
~
- c. . Coordinates all incoming and outgoing communications;
-d . Ensures proper logging and recording of communications.
- 4. Assist Emergency Organization in use of procedures. -
II. Operations Group A. Operations Group Leader
- 1. Qualifications f
- a. Current SRO License for Monticello WP/kk -
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- Precedure A.2-001. ..
" Revision 5 Page 6 of 19
- b. Demonstrated ability 16 supervisory skills.
- c. Knowledgeable or qualified in following areas:
('
- Monticello Emergency Plan
- Emergency Implementing Procedures:
A.2 - 101 A.2 - 205 A.2 - 102 A.2 - 301
~
A.2 - 103 A.2 - 502 A.2 - 104 A.2 - 105 A.2 - 107
- 2. Qualified Personnel in Order of Succession
,, DELETED l ,
- b. Senior Site Superintendent present, not.on duty shift
- c. Senior Shift Supervisor present, not on duty shift
- d. Outy Site Superintendent
- e. Duty Shift Supervisor
- 3. Duties
- a. Coordinates response of Operations Group;
- b. Evaluates plant and radiological conditions; s.
- c. Ensures Emergency Director is informed of plant status;
- d. Directs operation of the plant in compliance with all normaT plant procedures, directiv.es, technical.specifi '
~
cations and eme,rgency proce'dures;
- e. Monitors plant parameters and conditions. . .
- 8. Fire Brigade
- 1. Qualifications *
- a. Currently qualified in accordance with 4 AWI-3.13.2, -
including SCBA training and qualification. .
- b. Currently qualified in accordance with Appendix R,10CFR50:
1.) The Team Leader and #2'& #3 Team Members shall have . sufficient training in or knowledge of plant safety-related systems to understand the effects of fire and fire suppressants on safe shutdown capability. - 2.) The Team Leader shall be competent to assess the poten-WP/kk
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. . , Proc; dure A.2-001
- --
- Revision 5 Page 7 of 19
=
f- tial safety consequences of a fire and advise control room personnel. This shall be evidenced by-current SR0 or RO or current enrollment in license training program.
- c. Qualified physically in accordance with Tab 7 of the NSP Medical Policy and Procedure Manual (annual requirement).
- 2. Qualified Personnel
- a. Team Leader (Normally Site Superintendent or Shift Supervisor)
. DEL.ETED h
- b. Team Members #2 & #3 s ,l
(._ - DEL.ETED
- I
.' c. Team Members #4 & #5 DELETED III. Maintenance Group The Maintenance Group consists of.the Plant Superintendent, Operations and Maintenance; the Superintendent, Maintenance; the Maintenance Supervisors; all maintenance crew people; the plant electricians; plant helpers and the Instrument & Control Group including supervipors and coordinators.
A. Maintenance Group Leader
- 1. Qualifications a.
(, b. Five years experience at Monticello Nuclear Generating Plant Demonstrated ability in supervisory skills WP/kk
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_ _ _ . - ~ c - I . . Prec: dure A.2-001 .. R: vision 5 Page 8 of 19
- c. Knowledgeable or qualified in following areas: t' N
' (..'
- Emergency P1,an -
- Emergency Implementing Procedures:
A.2 - 001 A.2 - 106 l A.2 - 107 x . - A.2 - 603
- 2. Order of Succession
- a. ! /
- b. I
- DELETED .L
- e. [
- f.
- g. -
3
~
- B. OSC Coordinator
- 1. Qualifications - (Same as Maintenance Group Leader)
I
- 2. Order of Succession - (Same as Maintenance Group Leader)
C. Responsibilities - 3 1.- Maintenance Group primary responsibility for emergency repairs and corrective actions.
-3 2. Maintenance Group Leadar: .
. m. . .
~
- a. . Responsible for participating in d.iscussions regarding emergency response and for formulating specific tasks in the categories of. emergency r,epair aryd correc.tive action. .
- b. Responsible for implementing emergency repair and corrective action tasks by relaying task information to OSC Coordinator l and requesting that a team be' dispatched to accomplish task.
l
- c. Responsible for notifying Monitoring Section Leader of impending i
tasks.
- 3. OSC Coordinator:
Responsible for coordinating and assigning personnel to tasks desig-nated by TSC personnel, t IV. Engineering Group l The Engineering Group consists of the Superintendent, Technical Engineering and the Technical Engineering Group, plus the' Superintendent, Operations Engineering and the Operations Engineering Group. WP/kk' .
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, Page 9 of 19 '
A. Engineering Group Leader C 1. Qudlifications N a. y N
' Five years experience at Monticello Nuclear Generating Plant
- b. Demonstrated ability in' supervisory skills
- c. Knowledgeable or qualified in following, areas:
- Emergency Plan
- Emergency Implementing Procedures:
A.2 - 106 A.2 - 502
- 2. Order of Succession
- a. l.
6.
- c. '
d. DELETED
- e. I
' I B. Group Responsibi11 ties The group shall have the responsibilities for providing technical '
support for emergency repairs and corrective actions. V. Health Physics Group (' The Health Physics Group consists of the Supt., Radiation Protection and all ( Members of the Radiation Protection Group. The group is divided into two sections: The Offsite Dose Assessment and Chemistry Section and the Monitoring Section. The group leader is the
. Radiolo,gical Emergency Coordinator (See Figure 2).
'A. Radiolog'ical Emergency Coordinator
- 1.- Qualifications ,
a. Five years experience at Monticello Nuclear-Plant;
, b. Demonstrated abtlity in supervisory skills;
- c. Knowledgeable or qualified in following areas:
- Health Physics
- Emergency Plan
- Emergency Plan Implementing Procedures:
A.2 - 101 A.2 - 301 A.2 - 405 . A.2 - 106 A.2 - 302 A.2 - 406 A.2 - 107 A.2 - 303 A.2 - 407 i A.2 - 201 A.2 - 304 A.2 - 409 A.2 - 202 A.2 - 401 A.2 - 410 A.2 - 204 A.2 - 403 A.2 - 502 A.2 - 205 A.2 - 404 A.2 - 702 A.2 - 207 WP/kk
. , Pr:c: dure A.2-Od1 ..
R: vision 5 Page 10 of,19
- 2. Order of Succession
- a. '
b: c DELETED 't
- d. .'
e. l l
- 3. Duties
- a. Coordinate assessment of radiological aspects o'f accident,
, including.offsite surveys prior to EOF activation,
- b. Formulate protective action recommendations
- c. Ensure radiological surveillance and control measures are implemented. .
- d. Advise Emergency Director on health physics matters
- 8. Offsite Dose Assessment and Chemistry Section Leader
- 1. Qualifications - . . .
- a. One year experience at Monticello Nuclear Generating Plant
- b. Knowledgeable or qualified in following areas: ,
- Chemistry and radiochemistry, including Monticello
, Chemistry Manual
.] - Emergency Plan Implementing Proedures:
A.2 - 207 A'.2 - 208 A.2 - 404 -- ' A.2 - 405 l- - l , A.2 - 406 l A.2 - 408 A. 2 - 412 - - A.2 - 502
- 2. Order of Succession 1
a.
- b. - - -
"(, DELETED
- 3. Duties
- a. Offsite dose projection L
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~~ ~ Proc dure A.2-001 Revision 5
, Page 11 of 19
- b. Release rate determination
- c. Sampling and analysis of reactor coolant, containment atmos-phere and plant effluents
- d. Sample coordination and recording C. Monitoring Sectio'n Leader
- 1. Qualifications
- a. One year experience at Monticello Nuclear Generating Plant
- b. Knowledgeable or qualified in following areas: *
- Monticello Radiation Safety Procedures
- Emergency Plan Implementing Procedures:
, A.2 - 107 A.2 - 403 A.2 - 201 A.2 - 404 A.2 - 202 A.2 - 407 A.2 - 301 -
A.2 - 409 A.2 - 302 A.2 - 410 A.2 - 303 A.2 - 411 - (' ( A.2 - 304 A.2 - 501 A.2 - 401 A.2 - 502 A.2 - 402 A.2 - 601 _~
- 2. Order of Succession
< a.
l b .' l [ DELETED.' e.
- 3. Duties
~
- a. Emergency exposure control
- b. Contamination Control l c. Emergency surveys .
- d. Personnel and vehicle monitoring l
, e. Personnel and equipment decontamination l VI. Support Group l
l The Support Group consists of all plant office personnel and all plant QA l personnel. WP/kk
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Proceduro A.2-001. .. Revision 5 Page 12 of 19 A. Support Group Leader
. 1. Qualifications
- a. One year experience at'Monticello Nuclear Generating Plant;
- b. Demonstrated ability in supervisory skills;
- c. Knowledgeable or qualified in following areas:
A.2 - 501 A.2 - 503 A.2 - 502 A.2 - 106
- 2. Order of Succession ~
~ ~
a.
- b. .
- c. S
. d. _
DELETED
, e.
- 3. Duties
- a. Assign group personnul-to provide administrati.ve support, document control and document retrieval;
- b. Assure that TSC is st'affed adequately.
{.. _
- c. Coordinate and provide personnel for logistics functions
~
1* ,
- d. Act as TSC Coordinator and'be responsible for conduct of
~ Procedure A.2-1.06', Activation of the Technical Support Center.
7,, B., Emergency. Document Con, trol Coordinator-
- 1. Qualifications .
~
- a. Thorough understanding of Monticelio document and record control system;
- b. Knowledge of physical , storage locations of plant documents and records; c., Knowledgeable or qualified in following areas: -
A.2 - 502 A.2 - 503 WP/kk .
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' - ' Pr:cedure A.2-001' Revision 5 Page 13 of 19
;- 2. Order of Succession
- a. *
- b. l
[,bELETED I e.
- 3. Duties
- a. Provide document retrieval support for TSC and OSC; l
- b. Assist Support Group Leader with records control in TSC area VII. Security Group The Security Group consists of all plant Security and Services personnel
, and the contract security force.
'A. Security Group Leader
- 1. Qualifications
- a. Two years experience at Monticello Nuclear Generating Plant
- b. Kn'owledgeable or qualified in following areas:
- Monticello Security Plan
, - Safeguards Contingency Plan & Implementing Procedures a - Emergency Plan Implementing Procedures:
4.. .
' A.2 - 206 '
A.2 - 301 A.2 .302
- 2. Order of Succession
' [, ~ DELETED' ,
. c.
- d. -
- 3. Duties .
- a. Carry out plant security and access control functions
- b. Maintain strict personnel accountability onsite.
VIII. Emergency Team Personnel If required by procedure or for other purposes, an Emergency Team w 'ill be { selected' from the list of available candidates. (In special cases, however, exceptions to this procedure may be authorized by the Emergency Director.) WP/kk x-
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Proceduro A.2-001 - R:; vision 5 Page 14 of.19 s A Qualifications ' N. .(
, N.1 Current Red Cross Multi-Media First Aid training (i.e. within m last three years).
- 2. Currently qualified under respiratory protection program,
- s. including training for use of SCBA equipment.
- 3. One year experience in current general. work classification.
- 8. ' Qualified Personnel Persdnnelwhoarequalifiedforemergencyteamareidentifiedwithan asterisk in the green section of the NUCLEAR EMERGENCY PREPAREDNESS TELEPHONE DIRECTORY. (NOTE: The second sort in the green section is .
more useful if. specific skills are being sought.) IX. Miscellaneous Positions . 4 A. Emergency Planning Coordinator
- 1. Qualiffc'ations
- a. Health physics background or health' physics expertise on staff.
- b. Five years experience at nuclear power plant.
- c. Two years experience at Monticello.
(
;;. 2. Designated-Emergency Planning Coordinator ,
1 .
~*
Mathiasen,.G.
., B. Emergency. Preparedness Instructors. * . . - -
- 1. Qual.ifications
- a. - Knowledgeable fri Plant and Corporate Plans and Implementing ,
Procedures. *
- b. Demonstrated ability in instructing methods.
- c. Thoroughly familiar with subject matter of instruction. !
l
- 2. Q'alified' u Personnel l l
Personnel approved by Monticello Training Superintendent C. Assemoly Point Coordinator
- 1. Qualtfications See Qualifications for Shift Emergency Communicator
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- Procedure A.2-001
- Revision 5- '
, Page 15 of 19
- 2. Qualified Personnel See Qualified Personnel for Shift Emergency, Communicator s N
- 3. Duties 'x
- a. Assume control of operational Assembly P.oint
- b. ~ Ensure proper radiological surveys are conducted
- c. Conduct accountability procedure as required
- d. Maintain communications between Assembly Point and TSC i
D. TSC Coordinator (See Support Group Leader) E. Radiat. ion Protection Coordinator
. 1. Qualifications - Experience as Radiation Protection Coordinator i during normal operation. I
- 2. Qualified Personnnl
- a. -
- b. . s
- c. DELETED [' .
C d: .
- 3. Duties
?,
Responsible for conduct of Procedure A.2-108, Access Control During Emergencies. .
. F. Technical. Communicator'
- 1 Qualifications 1 -
l
- a. Experience at Monticello
- b. Systems expertise
- 2. Qualified Personnel This position will be filled by designating the most qualified
. person from among available candidates. The Emergency Director will be responsible for assuring that this position is adequately staffed. '
- 3. Duties
- a. Continuously maintains an open telephone communications link between the Control Room, TSC, and EOF.
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- Procedura A.2-00L -
Rxvision 5 Page 16 of.,19
~. ..
- b. Communicate technical information between response centers.
- c. If located in TSC, post information on Status board. x X. Response Center Staffing '
A. TSC Staffing '
- 1. Emergency Director - In charge
. 2. Group Leaders
- a. Radiological Emergency Coordinator
- b. . Engineering Group Leader
- c. Operations Group Leader *
- d. Maintenance Group Leader
- e. Srpport Group Leader (TSC Coordinator)
- f. Security Group Leader If primary designate is not available, this individual may be required to stay in. Control Room.
- 3. Communicators
- a. Lead TSC Communicator
- b. Assistant TSC Communicator (offsite notification) (2)
- .I
- c. Technical Communicator (3-way to EOF and CR) d .. Assistant TSC Communicator (for Emergency Director) l
- 4. Auxiliary Staff
- a. Monitoring Secti'on Leader..
b. Offsit6 Dose Assessment and Chemistry Section Leader
- c. Engineering Assistant de Security Ass.isitant ' .
- e. Emergency Document Control Coordinator
- f. Recorder
- g. Off-Site ~ Survey Team Controller
- h. Oose Projection Communicator
, B. OSC Staffing
- 1. OSC Coordinator - In Charge 1
- 2. S.tandby Personnel -
- a. All unassigned RPS
- b. Extra Operators (i.e., not assigned to Control Room)
- c. I&CS Supervisor, Coordinator and Specialists
- d. Maintenance Supervisors, Chief Electrician, Station Electricians, Machinists, Welders, Repairmen, and Riggers.
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, Procidure A.2-001
'- . *. Revision 5 Page 17 of l'9
[s ' 3. Communicator (To be designated by OSC Coordinator if needed) s s C. Control Room Staffing
- 1. Site Superintendent - In Charge
- 2. Assistance
- a. Shift Supervisor
- b. Shift Operators
- c. Additional operators assigned to Control Room 3 d. STA -
. s x , _/ ,
s
-s 3. Technical Communicator (CR to TSC) -
~
- 4. Technical Support Center personnel as directed by Emergency Director
' x REFERENCES
- 1. Monticello Nuclear Generating Plant Emergency. Plan
- 2. Monticello Nuclear' Generating Plant Operations Manuals
- 3. NUREG-0654/ FEMA-REP-1, " Criteria fan Preparation and Evaluation of Radio-logical Emergency Response Plan and Prep' a redness in Support of Nuclear Power Plants". -
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- ommunicator .
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. iLid iol og ica l Support Security h Cr UP Group Emergency Group "8 Leader ! 1. cad e r con rill na t or Leasier ,
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3,,, 3 3 Q 4 Group Group Group a y E$ h s
. l Operations ' d Group M" I" L n a n c e g ,
Leader C'""P I.cader Shitt . Technical l l Advisor 1&C F.lectrical & 7 28 y Hechanical % .S. 8 Operations . Sec ticni Group Sectton
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Stpport . _ . _ _ _ B ergency , R Supervisor Coordinator H O y . 0 e l O Chemistry Militoring Sectica Taadm- Section Icador . Oose . Projection Ocmnunicator . Off-Site Dose Assess-
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Access Control 'O
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< Procedure A.2-101 Revision 4
_" Page 1 of 46 Op. Com. Rev. Req'd. Yes X No Q.A. Review Req'd. Yes No X Q-Lu . N s ALARA Review Reg'd. Yes No X N _ CLASSIFICATION OF EMERGENCIES A.2-101 Pr.epared by: 6M/fc b ALARA Review: Revision 0 Date 03/31/81 Reviewed by: N N _N Q.A. Review: Revision 0 Date 03/31/81 Operations Committee Final Review: Meeting Number //86, Date c7 /r 7// 3 Approved by: I /8 ///h [ Date 2-aft 3 Op. Com. Results Review: Not Required htg.# 46 Date 03/20/81 PURPOSE The purpose of thistprocedure is to specify conditio'ns or groups of conditions'that' indicate an emergency exists and the actions to be taken by the Shift Supervisor or
. Control Room Operators to verify and classify the type.of emergency condition.
CONDITIONS AND PREREQUISITES
~
An off-normal condition corresponding to one of the initiating events described i
, in the appendices of this procedure is occurring or has occurred. -
4 ' L' PRECAUTIONS A.* There are many indications of an emergency condition that may occur either individually, in group events or sequentially. The operator or Shift Supervisor must be careful not to. rely on any one indication as being absolutely' indicative
,of an emergency condition. Although the operator should believe indications and take action based on those indications, he shall attempt to verify indications by checking secondary or coincident indicators,. Continued surveill,ance and .
assessment'of plant conditions.is necessary to ensure that the emergency classi-fication is appropriately revised as conditions change, or as more definitive information is obtained. B. None of the actions specified in the EPIP's shall take precedence over the actions that are necessary to comply with Technical Specifications. ORGANIZATION A. Overall Responsibility - Emergency Director . B. In Charge Control Room - Shift Supervisor 6)
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Procedure A.2-101 Ravision 4 - Page 2 df 46
. u C. Assistance yESg Reactor Operator . W' -
Shift Technical Advisor when assigned Shift Emergency Communicator DISCUSSION' - A. Definitions
- 1. Emergency Condition - An occurrence, or combination of events and indica-l tions that fall into one of the following classifications:
- a. Notification of Unusual Event
. Unusual events are in process or have occurred which indicate a potential degradation of the level of safety of the plant. No releases of radioactive . material requiring off-site response or
~ monitoring are expected unless further, degradation of safety systems occurs.
- b. ALERT i
Events are in process or-have occurred which involve an actual or potential substantial degradation of the. level of safety of the
~
i pl an.t. Any rel. eases are expected to be limited to small fractions . of the EPA Protective Action Guideline exposure levels.
}
- c. SITE AREA EMERGENCY -
'l Events are in process or have occurred which involve actual or 101 . likely major failures _of plant functions needed for protection of ~
- 71 the public. Any releases a're not expected to exceed EPA Protective Action Guideline exposure levels except near site boundary.
t.
~ d. ' GENERAL EMERGENCY Events are in process or have occurred which involve actual or l -
imminent substantial' core degradation or melting with potential l for loss of containment integrity. Releases can be reasonably [ expected to exceed EPA Protective Action Guideline exposure levels ! off-site for more than the-immediate site area. Emergency Action Levels (EAL) - Numerical o'r qualitative values for
~
2. the operational or radiological parameters, (radiological dose.r.ptes; water' borne or surface deposited concentrations of radioactivity; - specific instrument indications or changes in_ indications) that may - be used as threshholds for initiating procedures or actions to assess
, and verify plant conditions and may require initiating specific emergency procedures as designated by a particular class of emergency.
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~ ~ ~ Procedure A.2-101
" . Revision 4 Page 3 of 46
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Recognition B) , Attached to this procedure is Attachment 2, Event Recognition Guidelines (1-28). i These guidelines identify the four emergency classifications, the possible initiating event (s), emergency action levels for each classification, and, where applicable, specific instruments and indications to be used to detect and classify an emergency. The identified instruments and alarms are a representative listing of various instruments that may be used to verify an emergency condition. There are many process variables referred to in the guidelines. The instruments, indications, or alarms listed for any particular event are not necessarily a complete list of all those that will show abnormal indications or be useful in classifying the event. There is typically more than one instru-ment or instrument channel that monitors a specific parameter. The redundant channels and coincident indicators should all be used to verify the emergency condition. ~ The emergency action levels specified in the guidelines do not necessitate initiation of any particular phase of the emergency plan but rather signify a need for assessment and classification of conditions. In many cases, the proper classification will be immediately apparent from in plant instrumentation. In others, further assessment is necessary to determine the applicable emergency classification. _ The plant operating staff should consider the effset that combinations of initiating events have, that if taken individually would constitute a loser (- emergency classification but collectively may exceed the criteria for a higher classification.
- i In the Unusual Event classification, numerous EALs are related to limiting conditions for operation (LCOs) as specified in Technical Specifications.
In these cases, the- EAL is not considered exc'eeded.and an emergency condition' does not exist ~.if the appro'priate corrective action for' exceeding the LCO is taken. The EAL'is exceeded and.an Unusual Event has occurred if the event r,esults in a forced shutdown by the LCO. .. . g .
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Procedure A.2-101 . j - Revisien 4 Page 4 of,46 RESPONSIBILITIFS
..1 , .A. Emergency Direc' tor (Shift Supervisor) l
- 1. Prior to EOF activation, the Emergency Director shall declare the appropriate emergency condition as soon as the event has been indicated and verified. - -
After EOF activation, the Emergency Director shall notify the Emergency Manager when change in classification is indicated and verified.
- 2. After the emergency condition has been declared, the Emergency Director
. is responsible for implementing the actions as specified in the follow-ing procedures:
- a. Notif-ication of an unusual Event, A.2-102
- b. Alert, A.2-103
- c. Site Area Emergency, A.2-104
- d. General Emergency, A.2-105 B. Control Room Operator
- 1. The control room operator shall immediately notify the Shift Supervisor of any events that may be classified as emergency conditions.
l
- 2. The operator shall attempt to verify any indications. -
- 3. The operator shall assist the Shift Supervisor in assessing the indicat O
, and determining the classification of emergency.
- 4. The operator shall take immediate actions as dictated by plant procedures
~
j' and Ms general kr.owledge to control the event and place the plant in a safe condition. C. Shift Technical Advisor The Shift Technical Advisor shall advise the Shift Supervisor in identifying the event.- - l . l 0. Shift Emergency Communicator The Shift Emergency Communicator shall assist the Shift Supervisor in event classification. - PROCEDURE , - STEP 1: Verify the initial indication by comparing the indication to redundant ' instrument channels or to related parameters, physical observations, and l , field reports, as applicable. If not already present, notify the STA and/or SEC as appropriate. Initiate Form 5790-101-1, EMERGENCY CLASSIFI-CATION CHECKLIST.(Attachment 3).
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Procedure A.2-101 Revision 4
, Page 5 of 46 SEC:
C l STEP 2: Use Attachment 1 to identify any Guidelines applicable to the initiating condition. STEP 3: Locate the applicable guideline sheets in Attachment 2. STEP 4: Determine the appropriate emergency classification by comparing the verified plant parameters to the EALs for each emergency condition. If more than one guideline is applicable to the initiating condition, use the guideline which indicates the most severe classification. - STEP 5 If the EOF is not activated, declare the appropriate emergency and
~
implement the corresponding response procedure. If the EOF is
, activated, contact the Emergency Manager for consultation on whether or not to change the emergency classification. If a change is to be made, implement the corresponding procedure.
(The Emergency Manager will declare the new classification.)
- a. Notification of Unusual Event, A.2-102
- b. Alert, A.2-103
- c. Site Area Emergency, A.2-104
- d. General Emergency, A.2-105 -
STEP 6: Continue to assess the events and, if necessary, the emergency classifi- [ cation, as more definitive information becomes available or if plant
\_ conditions change significantly.
REFERENCES
- 1. NSP Monticello Nuclear Generating Plant, Plant Emergency Plan
- 2. NUREG-0654/ FEMA-REP 1, " Criteria for Preparation and Evaluation of Radio-
, logical Emergency Response Plan .and Preparedness in -Supportof Nuclear Power Plants"
- 3. Title 10, Code of Federal, Regulation Part 50, Appendix E ATTACHMENTS
- 1. Attachment 1, List of Initating Condition Categories l 2. Attachment 2, Guidelines for Classification of Emergency Conditions
- 3. Example of' Emergency Classification Checklist 8S%
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Procedure A.2-101
.i Rivisicn 4 - -
. Page 6 'of 46 Nttachment 1 List of Initiating Condition Categories .
s N Initiating Condition ' Guideline Radioactive effluents-high release rate or unmonitored --- 1 Increase in plant radiation levels ----------------------- 2 Release or loss of control of radioactive material within plant ---------------------------------------------------- 2 Fue l ha nd l i ng acc i den t ----------------------------------- 2 Reacto r p re s s u re h i g h ------------------------------------ 3
'Reacto r coo l an t l e a k ------------------------------------- 4 Ma i n s team l i ne b rea k ------------------------------------ 5 Fuel cladding degradation -------------------------------- 6 High cool ant or off gas activi ty ------------------------- 6 FSAR transient (Control Rod Drop) ------------------------ 6 .
Safety relief valve failure ------------------------------ 7 ECCS initiation ---------------------- !!;---------------- 8
- Loss of primary containment ------------------------------ 10 -
Loss of ' engineered sa'fety or-fire protection features ---- 11 i' Failure of RPS to initiate or complete scram ------------- 12 '- Loss of plant shutdown or shutdown cooling capability ---- 13 Loss of indigators or alarms (annunciators) -------------- 14 Control room l evacuation ---------------------------------- 15 Toxic or flammable gas ---------------------------'------- 16 ! Security < compromise -------------------------------------- 17 Loss of C p ow e r ----- -- ------- ---- --- -- --- ---- -- ------ - - - 18 Lo s s o f DC powe r ----------------------------------------- 19 Tornado or sustained winds ------------------------------- 20 l i Fl ood o r l ow wate r --------------------------------------- 21 Earthquake ----------------------------------------------- 22
~ ~ '
Fire -----------,----------------------------------------- 23 Explosion ------------------------------------------------ 24 Aircraft or missiles ------------------------------------- 25 Train accident ------------------------------------------- 26 l b l WP/kk . g l .._ , m *
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i Procedura.A.2-101
' Rev.ision 4
- Page 7 of 46
- p. , -
Attachment 1 (Cont'd.) x
~"
List of Initiating Condition Categories Initiating Condition Guideline Contami nated i nj u ry -- ' d----------------------------- 26 Turbine failure ------------------------------------------ 26 General emergency ---------------------------------------- 28 Other plant conditions ----------------------------------- 29 . Spent fuel, major damage to ------------------------------ ,/ 30 4 . 6 1 s a
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Proc: dura A.2-101 R vision 4 -
-e Page 8 of 46 .
ATTACHMENT 2 -
' J Guideline 1 -
RADI0 ACTIVE EFFLUENT UNUSUAL EVENT Radiological effluent technical specification. limits exceeded. EAL's
- 1. Discharge Canal Monitor exceeds 20 cps.
~
(High alarm annunciated on C04-A-22, DISCHARGE CANAL RADIATION, and ~, recorded by C02-17.358) E
- 2. Unmonitored liquid release to river which exceeds 10CFR20 App. B limits.
E
- 3. Stack Effluent Monitor (Ch A or B) exceeds 90,000 pCi/sec.
(Hi-Hi alarm anrtunciated on C249-A-1, STACK EFFLUENT HI-HI RADIATION; recorded on C257 and C258 (RR 7858A and RR 7858B), STACK N0BLE GAS RELEASE RATE; and alarmed by computer point 0-061.) - E '
- 4. Reactor Building Vent Noble Gas Monitor exceeds 4500 pCi/sec.
l
.E.
3 .
'5. Unmonitored gaseous release to the atmosphere which is estimated or suspected.to exceed' Appendix I Tech. Spec. 1.imits.
- ALERT
~
j Radiological effluents greater than 10 times technical specification instan-taneous limits (an instantaneous rate which, if continued over 2 hours, would result in about 1 mR at the site boundary under average meteorological condi-tion,s). EAL's
- 1. DischaYge. Canal Monitor exceeds 200 cps.
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. Procedu'ra A.2-101 Revision 4 Page 9 of 46 -
ATTACHMENT 2 (Cont'd.) -
. Guideline 1 (Cont'd.) RADI0 ACTIVE EFFLUENT
- 2. Unmonitored liquid release to river which is 10 times the limits in 10CFR20 Appendix B.
E
- 3. Stack Effluent Monitor (Ch A or 8) exceeds 9.0E+5 pCi/sec.
E
- 4. Reactor Building Vent Noble Gas Monitor exceeds 45,000 pCi/sec.
E
- 5. Unmonitored gaseous release to the atmosphere which is estimated or expected to exceed 10 times Appendix I Tech Spec limits. l SITE AREA
- a. Effluent monitors detect levels corresponding to greater than 50 mR/hr for hour or greater than 500 mR/hr Whole Body for two minutes (or five times tiiese levels to the thyroid) at the site boundary for adverse-
_] meteorology, '
- b. These dose rates are projected based on other plant parameters (e.g.,
radiation level in containment with leak rate appropriate for existing containment pressure) or ari measured in the environs; or
- c. ~ EPA Protective Action Guidelin6s:are projected to be exceedsd outside the' Site. Boundary.
, , . EAL's ' ' '
- 1. Stagk Effluent Monitor (Ch A or B) exceeds 9.0E+5 pCi/sec for 30 minutes E
l 2. Stack Effluent Monitor (Ch A or B) exceeds 9.0E+6 pCi/sec for 2 minutes E
- 3. Stack' release rate of radioiodines exceeds 1.7E+4 pCi/sec for 3D~ minutes
( - E
- 4. Stack release rate of radioiadines exceeds 1.7E+5 pCi/sec for 2 minutes 3 g i
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- 5. RBV Noble Gas Monitor exceeds 2.1E+4 pCi/sec for 30 minutes WP/kk .
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a Procedure A.2-101
~ Revision 4 -
Page 10'of 46 ATTACH' MENT 2 (Cont'd.) Guideline 1 (Cont'd.) RADI0ACTIVEEFFLUENf 2E
- 6. RBV Noble Gas Monitor exceeds 2.1E+5 pCi/sec for 2 minutes.
2E
- 7. RBV release rate of radioiodines exceeds 2100 pCi/sec for 30 minutes EE
. 8. RBV release rate of radioiodines exceeds 2.1E+4 pCi/sec for 2 minutes EE
- 9. Whole body doses greater than 1 Rem or thyroid doses of greater than 5 Rem are projected beyond the site boundary.
SE
- 10. Containment Radiation Monitor reading indicates above the .01% curve when plotted versus time after shutdown on the graph shown in Figure 1. ' ,
OJI
- 11. Measured W.B. dose rates at site boundary or beyond exceed 50 mR/hr for 30 minutes or 500 mR/hr for 2 minutes 2E
- 12. Radiciodine concentrations measured'at. site boundary or beyond exceed 7.0E-8 pCi/cc for 30 minutes or 7.0E-7 'pci/cc for 2 minutes.
GENERAL - As specified in Guideline 28. ~ s
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Proce. dure A.2-101 Revision 4 Page 11 of 46 (q ' . FIGURE 1
. .J Percent of Fuel Inventory Airborne in the Contsizunent lo 100t Fuel Inventory = 1001 Noble Cases p- '
+ 25% Iodine 2 1 + lt particulates
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0.0018 O . le 10" 2 3 '4 h h%V1(f i .3 h h bhW10' ) $ kibisVicf.A i ihbnito' Time After Shutdoum (Hrs) . 4 Fuel ' Inventory Approximate Source and Damage Estimate Released , 100, 2006 TID-14444, 2004 fuel damage, potential core melt.
- 50. 50t TID noble gases, TMI source.
- 10. lot TID, 2004 NRC gap activity, total clad l failure, partial core uncovered.
- 3. 3% TID, 2004 WASH-1400 gap activity, major
, clad failure. .-
- 1. It TID, 10% NRC gap, Max. 10% clad failure.
;1 .11 TID, 18 NRC gap, 14 clad failure, local heating of 5-10 fuel assemblies.
.01 .011 TID, .14'NRC gap, clad failure of 3/4 fuel element (36 rods).
10-3 .01% NRC gap, clad failure of a few rods. 10-4 1004 coolant release with spiking. p 5x10-6 100% coolant inventory release. 10-6 Upper range of normal airborne noble gas activity in containment. l -
t
' " Procedure A.2-101
. RQvision 4 - -
Page 12 of 46 s ATTACHMENT 2 (Cont'd.) d
]
Guideline 2 IN-PLANT RADIATION LEVELS . N
\
UNUSUAL EVENT Not Applicable ALERT Severe degradation in control of radioactive materials. , EAL
- 1. Increase by factor of 1000 in plant radiation levels as ir.dicated by Area Radiation Monitoring System:
Panel Description Normal EAL C-11 A-1 Refuel Floor Low Range 2 Full scale C-11 A-2 Refuel Floor High Ra.nge 5 5000 C-11 A-3 Refuel Floor S.W. Stairway 1 1000
- - ~ ~
C-11 A-4. New Fuel Storage ' 20 Full scale C-11 A-5 Fuel Pool Skimmer Tk Area 20 Full scale - 3 C-11 A-6 1001'-Rx South 3 Full' scale j C-11 A-7 985' Sample Hood 5 Full scale C-11 A-8 Rx Cleanup System Access 0.25 250 C-11 A-9 962' Rx Tool St'orage. Area 0.8 800 A-10 East CRD Module Area
~ C-11 7 . Full scale C-11 :A.11 West CR6 Module Area 3 Full scale .
. C-11 A-12 TIP Orive Area 2 Full scale
~
C-11 A-13 TIP Cubicle ' 30 Full scale C-11 A-14 HPCI Turbine Area 2 Full scale C-11 A-15 Rx. Bldg Drain Tk Area 25 Full scale l C-11 A-16 RCIC Pump Area 1 1000 C-11 A-17 East C.S..and RHR Area 10 Full scale C-11 A-18 West C.S. and RHR Area 5 Full scal e C-11 A-19 Hot Lab 0.25 250 - C-11 A-20 Control Room Low Range 0.02 20
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' Procedura A.2-101 Revision 4 1
Page 13 of 46 )
.- . i f'7} . ATTACHMENT 2 (Cont'd.)
- s__ l Guideline 2 (Cont'd.) IN-PLANT RADIATION LEVEL ,
Panel Description Normal EAL C-11 A-21 Control Room High Range 3'~~ 3000 C-11 B-1 Turbine Operating Floor 20 Full scale C-11 B-2 Turbine Front Standard 10 Full scale C-11 8-3 Cond Demin Operating Area 1 1000 C-11 B-4 Mechanical Vacuum Pump Rm 9 Full scale .
. . C-11 8-5 Feedwater Pump Area 1 1000
~
C-11 C-1 Radwaste Control Room 0.2 200 C-11 C-2 Sample Tank Area 2 Full scale
; C-11 C-3 Conveyor Operating Area 0.2 200 -
C-11 0-1 Hot Machine Shop 0.2 200 C-252 E-1 Recombiner In'trument s Room 2 Full scale C-252 E-2 Recombiner Pump Room __ 2 Full scale C-252 F-1 Offgas Storage Foyer 0.1 100
~; C-11 F-2 Offgas Storage Foyer.High Range' (100 100
~I
- C-257 & C-258 Containment Radiation Monitor 50 R/hr NOTE: Ehl's shown as FULLSCALE indicat'e that an increase by a factor
, of 1000 is beyond the range of the particular monitor. In these cases, a fu11 scale reading combined with_the Shift Supervisor's concurrence, shall meet the criteria for the ALERT classification.
g t i 2. Ofrect measurement of radiation levels cor. responding to an increase by a I factor of 1000. SITE AREA Not applicable GENERAL ,, i As specified in Guideline 28. t . y l
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, ATTACHMENT 2(bont'd.) .gj -
Guideline 3- REACTOR PRESSURE HIGH , UNUSUAL EVENT
- 1. Reactor Pressure exceeds safety limit (1335 psig).
Instrument Description EAL C05-FPR 6/97 Reactor Wide Range Pressure Recorder 1200 C05-6.90 A/B Reactor Pressure Indicators 1200 - Verify 1335 psig exceeded by checking pressure indicator PI 2-3-608 on C56. 4 ALERT Not Applicable SITE AREA EMERGENCY Not Applicable - GENERAL EMERGENCY . As specified in Guideline 28. 2 mt
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. Procedure A.2-101 Revision 4
. . Page 15 of 46
. ./] ATTACHMENT 2 (Cont'd.)
Guideline 4 - REACTOR COOLANT LEAK I UNUSUAL EVENT Primary system leak rate exceeds technical specification. EAL's
- 1. Unidentified leakage calculated from C4-FQ2543 or by computer point 0-122, Floor Drain Sump Rate of Change, exceeds 5 gpm 0_R
- 2. Identified leakage calculated from C4-FQ 2544 or from computer point D-120, Equipment Drain Sump Rate of Change, exceeds 20 gpm.
OR
- 3. Unidentified leakage rate increases 2 'gpm within a'ny 4 hour period as determined from Test #0381, CONTAINMENT COOLANT LEAKAGE LOG. ~
ALERT Primary coolant leak rate greater than 50 gpm. EAL
- 1. Total leakage calculated from C4-FQ2543 and FQ-2544 or from computer points D-120, Equipment Drain Sump Rate of Change, 0-122, Floor Drain Sump Rate of
~
- Change, excee'ds 50 gpm.
SITE AREA '
- Known loss of coolant accident greater than makeup pump capacity.
EAL's * *
- 1. Reactor water level (C05-2.3.85 A/B) decreasing below 1 foot above active fuel (-114 inches)
GENERAL As specified in Guideline 28. WP/kk s
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Procedure A.2-101 Revision 4 - - Page 16.'of 46 ATTACHMENT 2 '(Cont'd.) ] 1) Guideline 5
- MAIN STEAMLINE BREAK UNUSUAL EVENT Not Applicable ALERT Steamline break with MSIV malfunction causing leakage to secondary containment.
EAL's
- 1. Shift Supervisor's opinion that MSIV is malfunctioning or continuing steam flow with evidence that steam line break is outside of primary containment (e.g. visual observation, radiation or temperature),
and 2a. Annunciator alarms on MAIN STEAM LINE HIGH FLOW A/B (C05-A-25/26) and RX WATER LEVEL HI/LO (C05-B-24), _ . l or - \ 2b. Annunciator alarm MAIN STEAM TUNNEL HIGH TEMPERATURE A/8 (C05-A17/18) J l ! or l l 2c. Annunciator alarm MAIN STEAM LINE LEAKAGE (C05-B-32). SITE' AREA.
~ Main steam'line break .with failure of -MSIV's to isolate leak and- causing leakage outside of secondary containment.
EAL's l 1. Shift Supervisor's opinion that MSIV is malfunctioning or continuing steam ! flow with evidence that steam line break is outside of primary containment and 2a. Annunciator alarms on MAIN STEAM LINE HIGH FLOW A/B (C05-A-25/2'63 and RX - WATER LEVEL HI/LO (C05-8-24) or A U WP/kk
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Procedure A.2-101 Revision 4
, Page 17 of 46
\
p] ATTACHMENT 2 (Cont'd.)
~
Guideline 5 (Cont'd.) , MAIN STEAMLINE BREAK 2b. Annunciator alarm on MAIN STEAM TUNNEL HIGH TEMPERATURE (C-5-A-17/18) or 2c. Annunciator alarm on MIN STEAM LINE LEAKAGE (C05-B-32) and 3a. Annunciator alarm on TURBINE BUILDING HIGH. RADIATION ALARM (C04-A-21) ' or - 3b. High airborne radioactive material levels in Turbine Bldg. indicated by air monitors or direct measurement or 3c. Visual observation that blow-out panels between steam chase and turbine building have been ruptured. -
.s GENERAL ,
I
~ :/ As .specified in Guideline 28.
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\ Procedure A.2-101 Revision 4 - -
t Page 18'of 46 ATTACHMENT 2 (Cont'd.) Guideline'6 s FUEL CLADDING DEGRADATION UNUSUAL EVENT Fuel damage indication EAL's
- 1. Offgas Radiation Monitor exceeds 20,000 mR/hr or
- 2. OffgaTRadiation Monitor increases by 4060 mR/hr within 30 minutes at steady power or .
~
- 3. Reactor coolant I-131 dose equivalent exceeds 5 pCi/ gram,as determined by sample and analysis.
ALERT Severe loss of fuel cladding.
- a. High offgas at air ejector monitor (greater than 5 ci/sec; corresponding to 16 isotopes decayed 30 minutes) or -
- b. Very Iiigh coolant activity sample (e.g. , 300 pCi/cc equivalent of I-131)
EAL's
)v a
- 1. Offgas Radiation Monitor exceeds 200,000 mR/hr
_P. ~ '
- 2. Reactor coolant I-131 dose equivalent exceeds 300 pCi/gm as determined by sample and analysis.
or
- 3. ' Main 3Ieam Line monitor initiates trip due to high. radiation.-
NOTE: Resin intrusion may cause high radiation without fuel cla'dding. damage. SITE AREA - Degraded Core with possible loss of coolable geometry EAL's
- 1. More than 1/3 of core uncovered as indicated by reactor water level below
-174 inches and ..
- 2. a. Reactor coolant I-131 dose equivalent exceeds 3000 pCi/gm as determined by sample and analysis.
or l b. InabiTTty to insert control rods fully or
- c. InabiTTty to position SRM's or IRM's within core.
/ ,ecq GENERAL *- # -
'3%I As specified in Guideline 28.
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Prccedure A.2-101 Revision 4 s , Page 19 of 46 A ATTACHMENT 2 (Cont'd.) Guideline 7 . SAFETY RELIEF VALVE FAILURE UN!'5UAL EVENT ' Failure of a safety relief valve to close following reduction of applicable l pressure. EAL's . Auto Blowdown Relief Valve Leakage Alarm, C03-A-09
~
or SRV Open Alarm, C05-A-54 ALERT Not applicable -- O SITE AREA EMERGENCY
.)
- Not applicable GENERAL EMERGENCY
.As specified in Guideline 28.
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c s Procidure A.2-101
. Revision 4 -
Page 20'of 46
~
ATTACHMENT 2 (Cont'd.) . Guideline 8 u x , ECCS INITIATION UNUSUAL EVENT Emergency Core Cooling System (ECCS) initiated and discharge to vessel. EAL's Ia. RHR flow to reactor as indicated by RHR FLOW A/B Indicator, C03-10.139A/B or
. E lb. Core spray flow to reactor as indicated by CORE SPRAY FLOW A/B Indicator, C03-14.50A/B
. or Ic. HPCI flow to reactor as indicated by HPCI FLOW Indicator, C03-FIC 23-108 or s Id. APRS actuation as indicated by annunciator AUTO hl0WD0WN TIMERS AC IVATE ')
(3-A-25) and subsequent S/RV OPEN (5-A-54) annunciator ' and
- 2. Shift Supervisor's opinion that an emergency should be declared.
ALERT Not. Applicable , l l - SITE AREA EMER'GENCY
~
Not Applicable - l l l . GENERAL EMERGENCY l See Guideline 28. _ l _
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1 Pr:cedura A.2-101 Revision 4
. , . Page 21 of 46 fC ,
ATTACHMENT 2 (Cont'd.)
.._s -
Guideline 10 LOSS OF CONTAINMENT INTEGRITY
. UNUSUAL EVENT Loss of containment integrity requiring shutdown in accordance with ,
Technical Specifications. EAL's Plant shutdown is required by any one of the following limiting conditions for operation: a '. TS 3.7. A - Primary Containment; or
- i. b. TS 3.7.B - Standby Gas Treatment System; or
- c. TS 3.7.C - Secondary Containment; or
- d. TS 3.7.0 - Primary Containment Isolation Valves k
ALERT Not Applicable SITE AREA' EMERGENCY - Not Applicable - 3 GENERAL EMERGENCY As specified in Guideline 28. .. i r y e
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Procedure A.2-101 R: vision 4 -
. Page 22'of 46 ATTACHMENT 2 (Cont'd.)
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. Guideline 11 . LOSS OF ESF OR FIRE PROTECTION SYSTEM UNUSUAL EVENT
- 1. Loss of Engineered Safety Features (ESF)'or fire protection system requiring shutdown by Technical Specifications.' The following'is a list of operable ESF and fire protection subsystems necessary to l
meet LCO: Core Spray System
- Low Pressure Coolant Injection Subsystem I
Containment Cooling Capability (RHR Service Water System) High Pressure Coolant Injection System Automatic Pressure Relief ~
. Diesel Generator System -
Fire Protection System ' Standby Liquid Control System . ALERT Not Applicable l SITE AREA EMERGENCY - Not Applicable - l l GENERAL EMERGENCY l 1 As specified in Guideline 28. l s t
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Procedura A.2-101 Revision 4 [ Page 23 of 46 s ATTACHMENT 2 (Cont'd.) -
~
C0fdeline 12 REACTOR PROTECTION SYSTEM FAILURE UNUSUAL EVENT Not Applicable ALERT Failure of the reactor protection system to initiate and complete a scram which brings the reactor subcritical. EAL's Valid Scram Signal and
-Neutron count rate indicates reactor critical.
SITE AREA EMERGENCY -
'r Transient requiring operation of shutdown systems with failure to scram (continued power operation but no core damage immediately evident.)
EAL's Fa'ilure to bring reactor.subcritical with control rods
- L. . .
and - l Failure of the standby liquid control system i _ and l l Shift Supervisor's opinion that a transient is in progress l t and l No indication of core damage (if core damage indicated, call a general j emergency) ! GENERAL EMERGENCY As specified in Guideline 28.
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.l Procedure A.2-101 Revision 4 - -
1
.- Page 24 'of 46 ATTACHMENT 2 (Cont'd.) -
'h-Guideline 13
- D)
. LOSS OF PLANT SHUTOOWN OR SHUTOOWN COOLING CAPABILITY UNUSUAL EVENT Not Applicable . '
ALERT Complete loss of ability,to achieve or maintain cold shutdown.
~
EA L '. s
~
- 1. Loss of both RHR SW Loops or Loss of both RHR Systems Shutdown cooling mode of operation or l Loss of both RHR LPCI modes of operation and loss of both core spray l systems.
AND/OR f
- 2. Shift Supervisor's' opinio'n that plant cannot reach or maintain cold shutdown.
SITE AREA - l . . Complete loss of ability to achieve or maintain hot shutdown -- EAL's _ . .
- 1. 1 Inability to SCRAM and inoperable Standby Liquid Control System and
. 2. Loss of all safety relief valve capability '
or Inoperable RHR System or ' ' Inoperable RHR heat sink and
- 3. Loss of main condenser cooling or -
/
No makeup capability from either HPCI or RCIC systems. AND/0R
- 4. Shift Supervisor's opinion that plant cannot reach or maintain hot shutdown.
GENERAL EMERGENCY l As specified in Guideline 28. ./ 4 r_ - y I WP/kk .
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. Revision 4 i
. , Page' 25 of 46-
)
I g'] ~' ATTACHMENT 2 (Cont'd.) - Guideline 14 LOSS OF INSTRUMENTATION
\
Indication of alarm or instrumentation failure may be difficult to NOTE: determine. A failure of normally lighted indicators or the failure of certain alarms to annunciate during a surveillance procedure may provide an initial warning. A cause of annunciator failure, and thus an indication of failure, could be a loss of the uninterruptable MG set and no transfer to CKT Y10. UNUSUAL EVENT Indications or alarms on process or effluent parameters not functional in.the Control Room to an extent requiring plant shutdown. ALERT Loss of most or all annunciators (on panels C03, C04, COS, C08) sustained for
> 15 minutes with the plant not in cold shutdown.
. r i
SITE AREA EMERGENCY
- 1. Loss of most or all annunciators (on panels C03, C04, COS, C08) > 15 minutes .
and plant transient initiated or in progress. _ . I s GENERAL EMERGENCY. -
, As specified in Guideline 28. "
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,' Procedura A.2-101 .,
R2 vision 4 - - s . Page 26 ~of 46
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ATTACHMENT 2 (Cont'd. ) ( Guideline 15 - CONTROL ROOM EVACUATION UNUSUAL EVENT . Not Applicable ' ' ALERT ' , Evacuation of the Control Room is required or anticipated and control of shutdown systems has been established at local stations. (If local control has not been established in 15 minutes, go to SITE AREA.) f . ~ EAL As determined by on-duty Shift Supervisor. l
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SITE AREA EMERGENCY EvacuationofControlRoomandconhol'ofshutdown.systemsnotestablishedfrom local staticns in 15 minutes. -
)
EAL 4 As determined by on-duty Shift Supervisor.
^
GENERAL EMERGENCY As specifie'd in Guidelin~e'28. k +
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Pr:ceduro A.2-101 Revision 4
. Page 27 of 46 .
~
r ATTACHMENT 2 (Cont'd.) Guideline 16 T0XIC/ FLAMMABLE GASES UNUSUAL EVENT Near or onsite toxic or flammable gas release. EAL Gaseous hazards being experienced or projected onsite (out-cf plant) as indicated by visual observation, physical measurement or notification. ALERT A Entry into facility environs of uncontrolled toxic or flammable gases. EAL's Gaseous hazards being experienced or projected within the plant as indicated by measured concentrations equal te-or. greater than:
/a) 3 ppm chlorine; or *
, (b) explosive levels (as detected by explosive meter).
SITE AREA Entry of uncontrolled flammable gases into vital areas or entry of uncontrol_ led toxic gases in~to vital areas whereLlack,of access to the area constitutes a safety problem and plant is not in cold shutdown. EAL's
- 1. Gaseous hazards being experienced or projected within vital areas of the plant as indicated by measured concentration equal to or greater than:
i a) 3 ppm chlorine; or j b) explosive levels (as detected by explosive meter) and .
- 2. Plant not in cold shutdown.
GENERAL EMER'GENCY As specified in Guideline 28. WP/kk -
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Procedure A.2-101 Revision 4 - - Page 28 'of 46, ATTACHMENT 2 (Cont'd.) . Guideline 17 . SECURITY COMPROMISE UNUSUAL EVENT Security threat or attempted entry or attempted sabotage. EAL - Shift supervisor's opinion. ALERT Ongoing security compromise. EAL Security safeguards contingency event that results in adversaries commandeering an area of the plant, but not contcalling shutdown capability or any vital areas. '
.s SITE AREA
]
Imminent loss of physical control of the. plant. EAL , Physical attack on the plant. involving imminent occupancp of the control room, auxiliary shutdown panels, and any other vital areas. - GENERAL _ i Loss of physical control of the facility. EAL Physical attack on the plant has resulted in unauthorized personnel occupying the control' room or any other vital areas. 4 WP/kk . -
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. x Procedure A.2-101 Revision 4 Page 29 of 46'
(] ATTACHMENT ? (Cont'd.) Guideline 18 'N LOSS OF AC POWER UNUSUAL EVENT Loss of offsite power or loss of onsite AC power capability. EAL's
- 1. Loss of all offsite power as indicated by annunciators:
C08-B-7 No. IR Res Trans to No. 13 Bus Bkr Trip; and C08-C-08 No. IAR Res Trans to No. 15 Bus Bkr Trip; and C08-C-11 No. lAR Res Trans to No. 16 Bus Bkr Trip; and - C08-C-19 No. 14 4160V Bus to No. 16 Bus Bkr Trip and verified by zero voltage indicated on Bus 11, Bus 12, Bus 13, Bus 14, and 1AR Transformer voltage meters on panel C8.
-C .
- 2. Loss of both Emergency Diesel Generators when-they are required to be s operable by Technical Specifications. *
)
> ALERT Loss of offsite power and loss ofall onsite AC power. (see Site Area Emergency for extended loss)
~
EAL's
- 1. Loss of;all offsite power as indicated by annunciators:
C08-B-7 No. 1R Res Trans to No. 13 Bus Bkr Trip; and C08-C-08 No. lAR-Res Trans to No. 15. Bus Bkr Trip; and C08-C-11 No. lAR Res Tras to No. 16 Bus Bkr Trip; and C08-C-19 No. 14 4160V Bus to No. 16 Bus Bkr Trip
' and verified by zero voltage indicated on Buss ll, Bus 12, Bus 13, Bus 14 and 1AR Transformer voltage meters on panel C8.
and ,,
- 2. Loss of both Emergency Diesel Generators when they are required to be operable by Technical Specifications.
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Proc: dure A.2-101 Revision 4 - .- I Page 30'of 46. ATTACHMENT 2 (Contid.).
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, . Guideline 18 (Cont'd.) LOSS OF AC POWER
- SITE AREA
*/
C.' , Loss of all offsite power and loss of onsite AC power for more than 15 minutes. EAL's
- 1. Loss of all offsite power as indicated by annunciators: /
C08-B-7 No. IR Res Trans to No. 13 Bus Bkr Trip; and . C08-C-08 No. lAR Res Trans to No. 15 Bus Bkr Trip; and C08-C-11 No. IAR Res Tras to No. 16 Bus Bkr Trip; and C08-C-19 No. 14 4160V Bus to No. 16 Bus Bkr Trip and verified by zero voltage indicated on Buss 11, Bus 12, B'us 13, Bus 14 and 1AR Transformer voltage meters on panel C8. and
- 2. Loss of both Emergency Diesel Generators when.they are required to be operable by Technical Specifications. -
g 4 and '
- 3. 15 minute time lapse.
- GENERAL EMERGENCY
, As specified in Guideline 28.
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i Procedurad.2-101
. Revision 4 Page 31 of 46 (3
y Guideline 19 ATTACHMENT 2 (Cont'd.) LOSS OF DC POWER N UNUSUAL EVENT- x Not applicable. ALERT Loss of all vital DC power. (See Site Area Emergency for extended loss.) EAL's Loss of both 125V DC power sources and loss of 250V DC power source as indi'c ated by: .
- 1. Annunciators C08-A-20 250V Bus Low Voltage; and C08-B-13 No. 12 125V DC Bus Low Voltage; and C08-C-13 No. 11 125V DC Bus Low Voltage AND .
~
- 2. Shift Supervisors opinion that all vital DC power is lost or degraded
,, voltages are measured at battery terminals. -
SITE AREA' Loss of all vital onsite DC power for more than 15 minutes. EAL's Loss of both 125V DC power sources.and loss of 2'50V DC power source as' indicated by:
~
- 1. Annunciatdrs C08-A-20 ,
250V Bus Low Voltage; and C08-B-13 No. 12 125V DC Bus Low Voltage; and C08-C-13 No. 11 125V DC Bus Low Voltage AND ' I
- 2. Shift Supervisors opinion that all vital DC power is lost or degraded j .
voltages are measured at battery terminals. , AND
- 3. Lapse of 15 minutes.
GENERAL EMERGENCY m: As specified in Guideline 28. WP/kk . x . _ -
. Procedure A.2-101
. Revision 4 c -
Page 32 of 46,
, ATTACHMENT 2 (Cont'd.) .
Guideline 20 TORNADO OR SUSTAINED WINOS UNUSUAL EVENT Any tornado on-site. EAL's , A tornado is observed to touch down within site boundary
- E Sustained winds $bove 75 mph for greater than 10 minutes at the site.
ALERT Tornado striking facility. .
/
EAL's s A tornado' strikes a vital plant structure E Sustained winds above 90 mph for greater than 10 minutes at the site. SITE AREA.
~
Sustained winds or tornadoes in excess of design 1evels. EAL's
- Tornado causes damage to vital plant equipment or structures E
Sustained winds above 100 mph for greater than 10 minutes at the site, . GENERAL EMERGENCY s As specified in Guideline 28. q-$,. WP/kk
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'- Revision 4 Page 33 of 46 <
(~] ATTACHMENT 2 (Cont'd.) , Guideline 21 RIVER WATER HI/ LOW UNUSUAL EVENT
- 1. River water level in excess of 918 Feet
- 2. River flow below 240 CFS (about 902.4 FT river level)
ALERT
. 1. River water level between 921 and 930 FT.
- 2. River flow below 220 CFS (about 902.3 FT).
SITE AREA EMERGENCY
- 1. River water level exceeds 930-FT.
., 2. River water level below 899 FT. '
t
- 3. Flood or low water causes damage to vital equipment.
. GENERAL EMERGENCY ~ .
As specified in. Guideline 28. l t l . l L , f 1. WP/kk l
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, Precedure A.2-101 Rsvision 4 - -
Page 34'of 46 ATTACHMENT 2 (Cont'd.) ,
, Guideline 22 , EARTHQUAKE UNUSUAL EVENT Any earthquake felt in plant or detected'on station seismic instrumentation, and subsequently confirmed by one or more off-site sources.
EAL's
- 1. Alarm C06-C-8, EARTHQUAKE g
. 2. Shift Supervisor's opinion. ,
ALERT - Confirmed earthquake greater than OBE levels. EAL - Alarm C06-C-13, OPERATIONAL BASIS EARTHQUAKE SITE AREA -
- 9) .
Confirmed earthquake greater than DBE levels and plant not in cold shutdown. EAL's Alarm C06-C-18, DESIGN BA, SIS EARTHQUAKE - and ,
. Plant not in cold shutdown.
GENERAL EMERGENCY As specified in Gudeline 28. , ep.
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Proc 1 dura A.2-101 Revision 4 Page 35,of 46 (~ . ATTACHMENT 2 (Cont'd.)
- Guideline 23 -
~FI RE -
UNUSUAL EVENT Fire within plant lasting more than 10 minutes after initiation of fire fightin'g. EAL Fire Brigade Leader's determination. ALERT Fire potentially affecting safety systems. EAL's - Observation that fire could affect safety system; , and
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./
Shift' Supervisor's opinion. SITE AREA Fire compromising the functions of safety systems. EAL's Observation of fire that affects safety systems or functions; t and l l Shift Supervisor's opinion. . GENEAL EMERGENCY l As specified in Guideline 28. l h, m/ WP/kk .
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s - Prccedure A.2-101 Rsvision 4 . .- Page 36'of 46 ATTACHMENT 2 (Cont'd.) -:q Guideline 24 N N. EXPLOSION O UNUSUAL EVENT 77" ,' Near or On-site explosion. EAL . Visual observation or notification received; j' , and . Shift Supervisor's opinion. s AL'ERT Known explosion damage to facility affecting plant operation. EAL .,
- Shift Supervisor's' opinion. @,
SITE AREA Severe damage to safe shutdown. equipment from explosion or missil_es.
' EAL's.
. +
r Plant not in cold shutdown and Shift Supervisor's opinion GENERAL EMERGENCY
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As specified in Guideline 28. ~ G WP/kk j
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] Procedure A.2-101 Revision 4 Page 37 of 46 !
f ATTACHMENT 2 (Cont'd.) Guideline 25 s AIRCRAFT & MISSILES
'N s
\
UNUSUAL EVENT
- 1. Aircraft crash onsite or suspicious aircraft activity over facili,ty.
$AL Visual observation or notification is received.
ALERT ~ Aircraft crash on the facility or missile impacts on facility. EAL Visual observation - SITE AREA
- a. Aircraft crash affecting. vital-structures by impact or fire.
.., b. Severe damage to safe shutdown equipment from missiles or explosion:
- EAL As determined by Shift Supervisor with plant not in cold shutdown.
GENERAL EMERGENCY As specified in Guideline 28.
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. ' Procedura A.2-101- -
. Revisicn 4 - -
. Page 38 'of 46 ATTACHMENT 2 (Cont'd.) f%
- ,2 Guideline 26 MISCELLANEOUS UNUSUAL EVENT
- a. Transportation of contaminated injured individual from site to offsite hospital. ~
- b. Train deraf1 ment on site.
- c. Turbine rotating component failure causing rapid plant" shutdown. .
EAL's
; 1. Visual observation .
or *
- 2. Shift Supervisor's opinion ALERT -
Turbine failure causing casing penetration. - 3 EAL's ,
- 1. Visual observation.
and. -
- 2. Shift Supervisor's op' inion
. SITE' AREA EMERGENCY - -
Not Applicable - GENERAL EMERGENCY As specified in Guideline 28. i l
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Procedure A.2-101 l Revision 4 Page 39 of 46
,c
, ATTACMENT 2 (Cont'd. )
~~# -
.. Guideline 28 ALL GUIDELINES - GENERAL EMERGENCY GENERAL EMERGENCY
- a. Effluent monitors detect levels corresponding to 1 rem /hr W.B. or -
5 rem /hr thyroid at the site boundary under actual meteorological conditions.
- b. These dose rates are projected based on other plant parameters (e.g. , radiation levels in containment with leak rate appropriate
, for existing containment pressure with some confirmation from effluent monitors) or are measured in the environs.
EAL's .
. 1. Stack Effluent Monitor (Ch. A or 8) exceeds:
1.3E+8 pCi/sec in stability class A 1.9E+8 pCi/sec in stability class B 1.0E+9 pCi/sec in stability class C 1.0E+9 pCi/sec in stability class D 1.0E+9 pCi/sec in stability. class E 1.0E+9 pCi/sec in stability class F -
../
- 2. RBV Effluent Monitor exceeds:
9.6E+7 pCi/sec in stability class A 3.1E+7 pCf/.sec in stability class'B 1.5E+7.pCi/sec in stability' class C 7.1E+6 pCi/sec in stability class D -
.4.4E+6 pCi/sec in stability class E 2.'8E+6 pCi/sec in stability class F SI- . ,
- 3. Stack radiofodine release rate exceeds:
2.3E+6 pCi/sec in stability class A 2.6E+6 pCi/sec in stability class B 3.4E+6 pCi/sec in stability class C 4.9E+6 pCi/sec in stability class D .. 4.9E+6 pCi/sec in stability class E 5.9E+6 pCi/sec in stability class F
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' Procedure A.2-101 Revision 4 --
Page 40'of 46 ATTACHMENT 2 (Cont'd.) Qj
. Guideline 28,(Cont'd.) ALL GUIDELINES - GENERAL EMERGENCY
- 4. RBV radiciodine release rate exceeds:
1.9E+6 pCi/sec in stability class A
~6.0E+5 pCi/sec in stability class B 3.0E+5 pCi/sec in stability class C 1.4E+5 pCi/sec in stability class D 8.6E+4 pCi/sec in stability class E 5.6E+4 pCi/sec in stability class F or
- 5. Elease rate projection based on Containment Radiation Monitor exceeds any of the values in 1 or 2 above or
- 6. E se rates of 1 rem /hr W.B. are measured at the site boundary or beyond or
- 7. Edioiodine concentrations measured at the site boundary or beyond" exceed 7E-6 pCi/cc.
NOTE: Consider evacuation only within about 2 miles of the site boundary unless these levels are exceeded by a factor of 10 or projected to continue for 10 hours or EPA Protective Action Guidelina. exposure ~ levels are predicted to be exceeded at larger
- distances.
- j c. Loss of 2 of 3 fission product barriers With a p'otential loss of.
- 3rd barrier, (e.g. , loss of primary coolant boundary, clad failure and high potential for loss of containment).
l
~
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- EAL's- .
'1. '
Fa~ilure of- fuel cladding as evidenced by gap activity in reactor coolant (> 300 pCi/ gram I-131 dose equi ~ valent) or presence of gap activity in primary containment atmosphere. and - Failure of primary coolant boundary, as, evidenced by: 1 high drywell pressure; or ' high drywell temperature; or failure of MSIV's to isolate; or .. safety relief' valve stuck open; or gap activity in primary containment atmosphere and a M WP/kk l t _ , y- _ _ . - - ,.
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Procedura A 2-101
.. R::visien 4
. Page 41 of 46
. / - -
ATTACHMENT 2 (Cont'd.) Guideline 28 (Cont'd.) ALL GUIDELINES - GENERAL EMERGENCY
, Potential loss of containment as evidenced by:
containment temperature or pressure approaching design limits (281"F and 56 psig) and increasing; or loss of containment cooling; or Shift Supervisor's opinion that loss of containment is likely. NOTE 1: Failure of MSIV's to isolate constitutes a loss of bo'th primary coolant boundary and containment. When this is combined with cladding failure, all three barriers have been lost. NOTE 2: In situations of: a) Small or large LOCA with failure of ECCS to perform, or b) Loss of requisite decay heat removal systems (RHR and other heat sinks) following shutdown, loss of containment should be judged to be likely.
- 2. Failure of fuel cladding (per guideline 6) -
j and Fail'ure of containment as evidenced by all containment penetrations required for isolation not valved off or closed; or Shift Supervisors
, opinion that containment has failed and .
Potential loss of primary coolant boundary as ev'idenced by reacto'r l pressure near design limits and increasing or loss of ECCS.
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- 3. _ Failure of containment as evidenced by all containment penetrations required for isolation not valved off or closed or Shift Supervisor's opinion l .
and l Failure of primary coolant boundary as evidenced by high drywell ! pressure or temperature or failure of MSIV's to. isolate or stuck open safety relief valve and Potential for loss of cladding as evidenced by ECCS failure or reactor I .- water level low and decreasing. WP/kk j- .
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l , Pro'ccdure A.2-101 Revisicn 4 . - - Page 42 'of 46
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ATTACHMENT 2 (Cont'd.) , i N .l GtJIDELINE 28-(Cont'd.) ALL GUIDELINES - GENERAL EMERGENCY *
' _ _ NOTE: Consider 2 mile precautionary evacuation. If more than fuel . sgap act ii v ty released, extend this to 5 miles downwind.
- d. Loss of physical control of the plant. -
NOTE: Consider 2 mile precautionary evacuation.
- e. Other plant conditions exist, from whatever source, that make release of large amounts of radioactivity in a short time period possible, e.g., any core melt situation. See the example BWR sequences. -
NOTE: a. For core melt sequence.s where significant releases from containment are'not yet taking place and large amounts of fission products are not yet in the containment atmosphere, consider 2 mile precautionary evacuation. Consider 5 mile downwind evacuation (45 to 90 sector) if large amounts of fission products (greater than gap activity) are in the containment atmosphere. Recommend sheltering in other parts of the plume exposure Emergency Planning Zone under this circumstance (radius 10 miles). -
- b. For core melt sequences where significant releases are
..s) k not yet taking place and containment failure leading to a direct atmospheric release is likely in the sequence but not imminent and large amounts of fission products in addition to noble gases are in the-containment .
atmosphere, consider precautionary evacuation to - 5 miles and 10 mile
- downwind ev'acuation (45* to 90*
l sector). . . . .
- c. For core melt sequences where large amounts of fission products other than noble gases are in the containment
, atmosphere and containment failure is judged imminent, recommend shelter for those areas where evacuation cannot be completed before transport of activity to that location,
- d. As release information becomes available adjust these i
' ' ~ actions in accordance with dose projections, time available to evacuate and estimated evacuation't'i~mes given current conditions. { l l t
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~ _ , - Prccedura A.2-101 Revision 4 Page 43 of 46
/~') ATTACHMENT 2 (Cont'd.)
i x Guideline 28 (Cont'd.) ALL GUIDELINES - GENERAL EMERGENCY N Example BWR Sequences.
- 1. Transient (e.g., loss of off-site power) plus failure of requisite core shutdown systems (e.g., scram or standby liquid control system). Could lead to core melt in several hours with containment failure likely. More severe consequences if pump trip does not function.
- 2. 'Small'or large LOCA's with failure of ECCS to perform, leading to core degradation or melt in minutes to hours. Loss of containment integrity may be imminent.
- 3. Small or large LOCA occurs and containment performance is unsuccessful affecting longer term success of the ECCS. Could lead to core degradation or melt in several' hours without containment boundary.
- 4. Shutdown occurs bu't requisite decay heat removal systems (e.g., RHR) or non-safety systems heat removal means are rendered unavailable. Core degradation or melt could occur in about ten hours with subsequent containment failure. ---
- 5. Any major internal or ex'ternal events (e.g., fires, earthquakes, '
)-' substantially beyond design basis) which could cause massiveicommon
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damage to plant systems resulting in any of the above. b
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. Procedure A.2-101 R vision 4 . -
, Page 44 'of 46 ATTACHMENT 2 (Cont'd.) .-
. Guideline 29 'OTHER PLANT CONDI'TIONS
'N
'N UNUSUAL EVENT
- 1. Plant conditions exist that warrant increased awareness on the part of plant operating staff or State and/or local offsite' authorities.
- 2. Plant conditions exist that require shutdown under technical specifi-cation requirements.
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- 3. Plant conditions exist that involve other than normal controlled shutdown (e.g. cooldown rate exceeding technical specification limits or pipe cracking found during ope, ration).
ALERT Plant conditions exist that warrant precautionary activation of TSC and place-ment of EOF and other key emergency _. personnel on standby. SITE AREA EMERGENCY / Other plant conditions exist that warrant activation of emergency centers and monitoring teams or precautionary notification to nearsite public. l . g e e e 8 W 4 h a WP/kk
Procedure A.2-101 Revision 4
. Page 45 of 46
, . ATTACHMENT 2 (Cont'd.) .
Guideline 30 MAJOR' DAMAGE TO SPENT FUEL UNUSUAL EVENT s Not applicable ALERT Not app.licable SITE AREA Major damage to spent fuel in containment (e.g., large object damages fuel or water loss below fuel level). EAL's *
- 1. a. Decrease in fuel pool level below 36'.9" confirmed by LT-2787, Spent Fuel Pool Level Hi/Lo alarm Or ~~
- b. Dropping of heavy object onto spent fuel confirmed by direct -
observation and
- 2. Fuel Pool Radiation Monitor Ch A or B >50 mR/hr (Confirmed by annunciator 5-A-1 or 5-A-2) .
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' GENERAL As'specifidd in Guideline 28.
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Procedure A.2-101 Revisien 4 - Page 46 of 46 '
. ~ . ATTACHMENT 3 3, j Form 5790-101-1 Rev. 1, 10/20/81.
Page 1 of 1 j Example of EMERGENCY CLASSIFICATION CHECKLIST (For Use With Procedure A.2-101)
- 1. Initiating Condiiton:
ED Initials Time Date
- 2. Attachment 1 directs use of. Guideline Number (s): .
ED Initials Time Date
- 3. Attachment 2 classification: I
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; Declared:
-i ED Initials Time Date
- 4. Implemented Procedure A.2- .
' ED Initials Time Date
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. NOTE:- If reclassification becomes necessary, start a new Emeroency Classification Checklist.
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NOTE: After this checklist is completed and is not required for immediate use, it shall be placed in the appropriate container provided for , Emergency Records.
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Proce'ure d A.2-107 -
- ' Revision 5 Page 1 of 4 Op. Com. Rev. Reg'd, Yes X No
'Q. A. Review Req'd. Yes No X q ALARA Review Reg'd. Yes No X
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ACTIVATION OF THE OPERATIONAL SUPPORT CENTER (OSC) A.2-107 REVIEW AND APPROVAL Prepared by: Cdddc- ALARA Review Revision 0 Date 3/28/81 Reviewed by: t&Mdf/ Q. A. Review Revision 0 Date 3/28/81 Operations Committee Final R'e view: Meeting Number //8 C Date .#/////3 Approved by: br1_M Date d -af -d'A
'Op. Com. Results Review: Not Required Mtg.# 1056 Date 1/22/82 PURPOSE AND REQUIREMENTS This procedure provides specific information and instructions for the organiza-tion, activation, operation and de-activation of the Operational Support Center (OSC) in support of the Monticello Nuclear Generating Plant and NSP Emergency Plan. _,
CONDITIONSANDPREREQUISIT5S . An emergency condition corresponding to an Alert or a higher emergency classi-fication has been declared at the Monticello Nuclear Generating Plant as provided in the MNGP Emergency Plan. PRECAUTIONS The'0SC facilities'may be used for normal daily operations as well as for training and emergency' drills, provided that these activities do.not interfere with the
.. immediate1 activation of the OSC or the continuing OSC operations in the event of an accident. OSC facility use during normal operation shall be limited to activities that will not degrade.the level of OSC preparedness to react to accident situations and,will not reduce OSC reliability.
ORGANIZATION AND RESPONSIBILITIES A. . Emergency Director - Overall In-Charge -
- 8. Operational Support Center Coordinator - Responsible for implementation of this procedure. '-
DISCUSSION
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A. OSC FUNCTION . The OSC will be the onsite area separate from the Control Room where predesignated operations support personnel will assemble.
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. s Procedure A.2-107 Revision 5 - -
Page 2 of 4 . B. Location -
.q The OSC~ location will be the I&C Shop on the second level of the Administra-tion Building.
C. Communications
- 1. Two (2) plant telephone extensions PROCEDURE -
0 NOTE: The following is a list of procedural steps for which the OSC Coordinator is responsible. Each step which contains the word
" continually" means that the steps should be repeated regularly as needed while the OSC is in operation.
STEP 1 ' Ensure that communication links are continuously manned. Obtain the services of a Shift Emergency Communicator, if needed. NOTE: Extension 1224 is the published OSC number. STEP 2 Continuously maintain accountability for OSC personnel. Ensure that a list of all persons reporting to the OSC is prepared. Update the list as additional personnel report, -are dispatched, or relieved. STEP 3 If a plant evacuation is directed, ensure that OSC personnel insect their .' ID cards in the TSC card reader. Provide a list of OSC personnel (names and badge numbers), not currently present in the OSC, to the Security s Group Leader. i STEP 4 Continually hold briefings to update OSC personnel on plant status, i STEP 5 When a work request'is received'from the TSC:
- a. Form up a team for the job. Try to anticipate'the requisite skills,.
but do not over.-sta'ff. .
- b. Fill out a. Job Description, Form 5790-107-4 (Attachment 1). Direct 1
someone (not a team. member) to make two copies and deliver the i original to the RP' Coordinator at Access Control.
- c. Ensure that team members are instructed thoroughly and are prepared l to accomplish the task. Discuss types of tools and equipment needed, where or how to obtain tools and equipment, possible alternatives
{ for accomplishing tasks, etc. Also, ensure that the Team Leader has instructions on how and to whom to report problems or job completion. NOTE: An Emergency Document Control Coordinator should be available to assist in finding drawings, manuals, etc. If not, contact Support Group Leader in TSC for assistance in this matter. WP/kk
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Procedura A.2-107 Revision 5 Page 3 of 4
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.< PROCEDURE (Cont'd.)
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- d. When prepared, dispatch the team to Access Control for' final radio-logical preparations. Log the dispatch time on the Job Description form and update the accountability list.
STEP 6 Initiate and continuously maintain the.0SC Log in accordance with A.2-502. STEP 7 Keep the Mai,ntenance Group Leader informed on status and events in OSC. ehe 9
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L . Procsdure A.2-107 - Revision 5 - -
. . Page 4.of 4' .
Form 5790-107-4 Revision 0, 02/15/83 A ATTACHMENT 1 zgj Page 1 of 1 - Example of JOB DESCRIPTION JOB: LOCATION: ESTIMATED DURATION: _ Minutes TEAM: s
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TLD NO. NAME w s
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Team Dispatched:,From OSC From Access Control ._ NOTE: After this fo'rm is completed and is not required for immediate use, it shall be placed in the appropriate container provided for Emergency Records.
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Procedure A.2-108 Revision 0
. Page 1 of li
, . Op. Com. Rev. Reg'd. Yes < No
- .. Q. A. Review Req'd. Yes No 1 r~) j ALARA Review Reg'd. Yes 1 No ACCESS CONTROL DURING EMERGENCIES Procedure A.2-108 REVIEW AND APPROVAL Prepared by: 63//Mb ALARA Review Sd /4 b Date k/3 Reviewed by: 5)dfI d d d Q. A. Review // / (D Date J.//4/G T OperationsComEltteeFinalReview: Meeting Nu ber //8(c Date .2/////$
, Approved by: d $4t\ Date A - d 13 Op. Com. Results Review: e+ Noet u Mtg.# //.N Date .1//P/d"> PURPOSE AND REQUIREMENTS This procedure provides specific information and instructions for the organization, activation, operation and de-activation of Access Control during emergenc.ies. CONDITIONS AND PREREQUISITES
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An emergency condition corresponding to an Alert or a higher emergency classi-fication has been declared at the Monticello Nuclear Generating Plant as provided T in the MNGP Emergency Plan. ' ORGANIZATION AND RESPONSIBILITIES A. Overall In-Charge - Emergency Diret: tor
- 8. Conduct of Procedure 'R.'P. Coordi'nator C. Direct Supervision - Radiological Emergency Coordinator / Monitoring Section Leader D. Assistance - Assistant Coordinator / Communicator RP Specialists assigned to exposure control and surveys DISCUSSION 4
A. Access Control Function * ' The function of Access Control during emergencies is similar to the fuoction during normal operation, except that positive control is established over entries to the affected area.
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B. Location s The primary location for access control is the location used during normal
- r. operation. If conditions dictate, access control will be relocated according s
to Procedure A.2-411, Establishment of Secondary Access Control. WP/kk
s Pr:c: dure A.2-108 Revision 0 - Page 2 of'11 . C. Data and Information Resources . ,- The following are maintained at Access Control:
- 1. A complete set of up-to-date radiological survey maps.
- 2. Plant Emergency Procedures
- 3. Bechtel Accident Dose Rate Maps D. Communications
- 1. Intercom for communication wit'h TSC
- 2. Rad Survey Portable Radios (4)
- 3. Plant Extensions (2)
- 4. Radio Console (capable of communicating with Rad Survey and Operations portable radios)
E. Equipment and Facili. ties (Primary Location) /
- 1. GDE Terminal-for exposure control
- 2. BBA System
- 3. Count Room equipment '
- a. Automatic Smear Counter
- b. GeLi Counting System
- 4. Status Board --
- 5. Radiological Survey Maps s
- 6. Procedure Forms .
- 7. Portable CAM
- 8. Portal Monitor ]'.'
- 9. First Aid Kits and Stretcher
- 10. Decon Facilities
- 11. Friskers
- 12. Respiratory Protection Equipment '
. 13. Fire Fighting Equipment: -
14'. Protective Clothing
- 15. Signs and chains for use in positively maintaining plant access control.
PROCEDURE PART I - ACTIVATION
, STEP 1 Direct o'r perform radiological survey in Access Control and SAS.
l Forward result to REC.- The REC will be responsible for ensuring routine, surveys of the area and for evaluation of the results. STEP 2 Position portable CAM in area outside of BBA Room and place in .. l operattiin. STEP 3 Verify Automatic Smear Counter and GeLi Detector systems in _ operation.
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STEP 4 Obtain 4 portable radios on the OPERATIOFS net, plus a gang charger, for use at Access Control. Establish radio contact with the REC. l WP/kk
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, Procedur6Al2-108
. Revision 0 Page 3 of 11 q;
1q STEP 5 Direct the removal of non-essential personnel, interferring equipme9t, y etc. from t! e area. STEP 6 Initiate the Access Control Log in accordance with A.2-502. s STEP 7 Obtain a copy of the most current exposure information for active . personnel. If personnel are available, process any dosimeter cards - and update the master exposure file. _ s 4 PART II - OPERATION - Note: The following is a list of procedural steps for which the R.P. Coordi- ' nator is responsible. Each step which contains the word " continually" means that the steps should be repeated regularly as needed while the emergency Access Control is in operation. STEP 1' Continually update survey floor plans. This will require rev.iew of incoming survey results, and also review of ARM data (Form No. 5790-107-3, Emergency ARM Log (Attachment 3) may be used to record ARM data.). STEP 2 Continually maintain status board. , STEP 3 Ensure that communications are tontinuously attended. Obtain the services of a Shift Emergency Communicator, if~needed. 7
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}. NOTE: Use OPERATIONS radios for in plant communications.
Use RAD SURVEY radios for out-of plant activities. STEP 4 Keep the REC apprised of events and activities. STEP 5 Supervise personnel assigned to Access Control. 'All personnel should have dosimetry and current exposure info'rmation. l STEP 6 Deter:nine the need for special supplies,. equipment, etc. to support L Access Control operation. Any requests should be forwarded to Support i Group Leader. i l STEP 7' Support rMygency rescue, first aid, maintenance and survey teams by verify # 4; @eir preparedness to initiate their activities and by l cooremU g their movements in and out of the controlled area with tie v atr Room and TSC. Prepare emergency RWP's i.a.w. Attachment S 3 w. .e that adequate precautions have been taken. STEP 8 Maintain strict access control (signs should be used to aid in this process). Following specific direction
- from REC or MSL, all entries to Controlled Area shall be approved by REC or MSL. Request Security Personnel assistance in maintaining access control, if required.
l NOTE: The REC and/or MSL will canitor controlled area status and reactor health. Baced on the situation in the affected area, the MSL or REC may require that each entry to the affected area be approved.
? Specific directions will be relayed to Access Control in this event.
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, , . Page 4 of 11 .
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STEP 9 Coordinate the arrival and departure of offsite support services and q coordinate their standby status while on site. gj STEP 10 Make necessary preparations to. relocate access control (Procedure A.2-411) in the event that the primary access control point becomes uninhabitable. STEP 11 Continually maintain the Access Control Log. ~ STEP 12 Ensure that Radiation Protect ~ ion Procedures are followed. STEP 13 If and when directed to do so, ensure that all personnel in the Access Control area (including the SAS) insert their security badges into the
- accountability reader located near the portal monitor. Caution personnel to make sure they get a red light after . inserting cards. As part of the accounting process, prepare a list of names, initials and TLD numbers of any personnel.who are in the Controlled Area and not
, ~._ , available to use card reader. Forward the list to the TSC.
PART III - DE-ACTIVATION Upon termination of Emergency condition or when deemed by Emergency' Director that the emergency Access Control may be deactivated perform the following: STEP 1 InitiateSurveillanceTest#1105 STEP 2 Return Operations Radios to their storage location. STEP 3 Return Radiation Protection Radios to their storage location. REFERENCES
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- 1. Monticello Nuclea'r Generating Plant Emergency Plan
- 2. Mont.icello Nuclear' Generating Plant Operations Manual .
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- 3. NUREG-0654/ FEMA-REP-1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness'in support of Nuclear Power Plants."
ATTACHMENTS
- 1. Guidelines for Us~e of Emergency RWP Checklist
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l 2. Example of Einergency RWP Checklist -
- 3. Example of Emergency ARM Log R
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Procedure A.2-108 Revision 0
"_ Page 5 of 11
'O Page 1 of 3 s ATTACHMENT 1 j GuildeliHes for Use of Emergency RWP Checklist PURPOSE-purpose of this attachment is to detail the process of how emergency RWP's will be used to govern emergency work.
DEFINITIONS ' An emergency RWP is defined as.the process which ensures certain radiological precautions for emergency work are considered, and appropriate actions are - taken. The emergency RWP checklist (Form No. 5790-107-2, Attachment 3) is the instrument that documents which actions were taken. DISCUSSION In general, .the entire process as outlined below should be completed each time an emergency RWP is needed'. However, in urgent situations, completing the whole process may hamper the timely execution of certain corrective actions. On the other hand, hazardous radiological conditions that could be present during an accident may increase the importance of ensuring the necessary precautions are taken. Therefore, each circumstance-will dictate the extent to which an emergency RWP will be completed, and this procedure is intended to outline the philosophy.Wiich will be used to ensure the degree of control required by the-
; . emergency RWP is appropriate for the task at hand.
EMERGENCY RWP ISSUANCE PROCESS To the extent that is practical, the entire emergency RWP process as outlined below should be completed. One should be able to readily determine from the urgency'of,the situation how much job preplann'i'ng should be doneand.to what extent the emergency ~RWP process should be completed. For all emergency RWP's, an_ emergency.RWP checklist shall be completed, post job co.mpletion, if necessary, for' items a, b, c', e, h, i, & k. '
- a. Determine the urgency and verify the validity of the proposed emergency work.
Normally, this information will be supplied through normal channels from the - TSC (e.g. phone call from MSL or approved WRA). If it has not been supplied, contact the ED, REC, or MSL to obtain this information before allowing the work to commence. ~The only exception to this may be if it is learned that immediate actions are necessary to save a life. If the work has been ordered to begin immediately, do not spend time completing the checklist if it will hold up the start of the job. Prescribe appropria,te precautions, and ensure job begins ASAP. However, complete as much of checklist as possible while waiting for necessary precautionary steps to be taken (e.g. donning P.C.'s etc.).
- b. Assess the radiological conditions to be encountered during the job. Determine if the precautions contained in the existing extended RWP's are adequate, and l if they are, use the extended RWP, while still completing sections c, e, and m k of the process. If the extended RWPJ s are not adequate, complete the rest
]) of the process. '
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u . Procedure A.2-108 Revision 0 - Page 6 of 11_, Page 2 of 3 ATTACHMENT 1 - - m; 2.)
- c. For'all jobs, an accurate and complete description of work, work site location and the protective equipment and dosimetry to be used shall be determined. If thereisdoubtastotheexactnatureoftheworktobeperfEmE,orthelocation of the work, the workers supervisor should be consulted.
- d. If at all.possible, ensure an RPS is in attendance for the job.
- e. Log personnel'in and out by completing page 2 of.the emergency RWP checklist.
- f. The Bechtel' accident dose rate, maps should be used to determine the best route to the work site in order to keep doses ALARA.
- g. Ensure that all keys needed for access are obtained.
- h. Emergency workers should have completed form-4's and procedure A.2-401 shall be completed for exposures which are expected to result in the individuals quarterly accumulated dose to exceed plant administrative limits.
- i. For areas in which the dose rate is expected to be > 1R/hr, the expected time at the work site and the authorized individual doses for the job shall be determined (assume the current quarterly allowable, unless told otherwise). From this infor-mation, determine the highest working area dose rate which would result in the ,
limiting individual authorized dose being received, while also taking into acc': : any significant doses that may be received in route. Perform timekeeping during u)e job to ensure planned exposures are not exceeded. Continual radio contact should be available between emergency workers and Access Control to aid in such timekeep-ing. While the job'is in progress, if it is deterinined that planned exposures will be exceeded, contact the ED immediately for further instructions. In addition, a maximum travel route dose rate should be detiermined. T'his dose rate should be ~ 4 times higher than any expected to be encountered.enroute to the work area,' up to 1000 R/hr for the worst case. 'The purpose o'f thTs dose rate is - to serve as a caution flag to the RPS that means " Beware conditions are signifi-
' cantly different than or_iginally thought". Actions to be taken if this dose rate is reached or exceeded will be determined during the job briefing and will be dependent upon job importance, duration, and the exposure limits of the individuals doing the job.
- j. To increase personal safety, the buddy system should be employed in the following conditions:
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- 1) If the equipment needed'for the job is too much for one person, slowing the job down and resulting in non ALARA exposures.
- 2) If radiological conditions could change abruptly and drastically during the job, and one person is not available to watch a dose rate meter continuously.
- 3) If radio contact c;annot be maintained between Access Control and the emergency workers.z - -
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. Procedure A.2-108 Revision 0
. Page 7 of 11
,- k Page 3 of 3 ATTACHMENT 1
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- k. Prior to. dispatching personnel to perform emergency work, ensure adequate job planning has been performed and that emergency workers have been adequately briefed regarding the proper precautions which.should be exercised to maintain worker risk to an acceptable level. Since Access Control may be a very busy place, extra effort will have to be exercised to ensure this is effectively done. The higher the expected hazards, the mo e important this becomes.
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Procedure A.2-108 ' Revision 0 - - - Page 8 of*11 . Form 5790-107-2 ATTACHMENT 2 Revision 3', 02/14/83 g Page 1 of 2 - Example of Emergency RWP Checklist Date WRA No. Time
- a. Job must begin immediately. Yes No .
- b. Existing extended RWP.used. Yes # No
- c. Work location Work description
. Protective equipment and dosimetry used
[] Hood [ ] Rubber gloves [] TLD [] Front & Back [] Coveralls [ ] Canvas gloves [] 200 mR SRD [] Waterproof [ ] Rubbers [] 1 R SRD Outer Layer [ ] SCBA [] 10 R SRD [] Full Face [ ] Beta Protection [] 200 R SRD Part Resp for Eyes -[ ] Extremity TLD(s) [] Dose Rate Meter i
- d. RPS in attendance? Yes No (ifN0,requireDoseRateMeter$bove'
- e. Personnel logged in (Complete the backside of this form) l Initial
- f. ALARA routes specified? Yes No If yes, record route
- g. 'Any keys requ' ired? Yes No .
- h. A.2-401 completed? -
Yes No
- i. _ Expected time to be spent at work site (x) hrs i Limiting Authorized individual dose for job (y) mrem t ~
Highest allowable working area dose rate (z) mrem /hr (z = y + x) Highest expected travel route dose rate: mrem /hr Timekeeping ready? Yes No Radio contact available? Yes No ..
- j. Buddy syr employed? Yes No
- k. Briefing conuacted? Yes 'No ~
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Completed by: - RPS m
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Approved by: R. P. Coordinator l WP/kk
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Procedure A.2-108 Revision 0 Page 9 of 11 g Form 5790-107-2
; ,1 Revision 3, 02/14/83 Page 2 of 2 ATTACHMENT 2 Example of Emergency RWP Checklist 4 '
Time Dosimeters Authorized In Out 0-200 1R 10R r 200R Name Dose In Out In Out In:0ut l Inl0ut-I
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NOTE: - After this form is completed and is not required for immediate use, it shall be placed in the appropriate container provided for g] emergency records. WP/kk
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Proccdure A.2-109-
} Ravision 0 ij g, , Page 10 of 11
-j/ Form #5790-107-3 ATTACHMENT 3 - 1 : Revision 1, 02/14/83
} Page 1 of 2 Exainple of
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.i, ) .i EMERGENCY ARM LOG Date l{ Normal Max. Current Reading (record time in top box) il ARM No. Area Description Reading . Reading i 15 lj A-1 Refuel Floor Low Range 2 1000 l A-2 Refuel F'loor High Range 5 10000
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A-3 Refuel Floor Stairway - 1 1000
- A-4 New Fuel Vault (1001 North) 7 1000
- 4 3
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A-5 Fuel Pool Pump Room 9 1000 A-6 Contaminated Storage Area - (1001 South) 2 1000 l A-7 985 Sx Hood 5 1000 - A-8 962 N.W. 0.25 1000 . A-9 962 Tool Crib '0.65 1000 I j A-10 East CRD Mod Area 7 1000 ' Ii A-11 West CRD Mod Area 5 1000 TIP Drive Area A-12 2 1000 A-13 TIP Cubicle 30 10000 l
; A-14 HPCI Turbine Area 0.25 1000 t -
A-15 896 Radwaste Orain Tk Room 25: 1000
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} A-16 RCIC Pump Area '1 1000 .
A-17 A-RHR Room (East) 10 1000 l i A-18 B-RHR Room (West) 10 1000' A-19 Chemistry Hot Lab 0.26' 1000 , A-20 Control lloom Low Range ;0.02 100 A-21 Control Room High Range 3 10000 ,
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() t' Rsvisicn 0 '- '19 ' N\ Page 11 of 11 i Form #5790-107-3 ATTACHMENT 3 . Revision 1, 02/14/83 Page&of2 Example of ' EMERGENCY ARM LOG Normal Max Current Reading (record time in top box)
- ARM No. Area Description Reading Reading 1 B-1 Operating Floor - 951 20 10000 B-2 T. G. Fr'nt o Standard 10 1000 .
B-3 Cond Demin Operating Area 'l 1000 B-4 MVP Room 9' 10'00 B-5 FW, Pump Area 1 1000 C-1 R.W. Control Area O.2 1000 C-2 Sample Tank Area - 947 3- 1000 \
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C-3 Conveyor Operating Aisle 0.2- 1000 Machine Shop (Hot) D-1 2 0.2 1000 - E-1 Recombiner Instrument Room 1 1000 I
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E-2 Recombiner Pump Room 3 1000 i F-1 Off-Gas Foyer .2 1000 F-2 Off-Gas Foyer < 100 - 1000 R
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Proceduro A.2-209 Revision 0 '
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Op. Com. Rev. Esq'd. Yes x No Q. A. Review Reg'd. Yes No X f . ALARA Review Req'd. Yes No x
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RESPONSIBILITIES OF RADIOLOGICAL EMERGENCY COORDINATOR A.2-209 REVIEW AND APPROVAL Prepared by: 63OEd<a ALARA Review Mhcd/I.e- Date M /f /J } Reviewed by: % d d d E MO Q. A. Review A/ C b f Date .p. / M / r 3 Operations Committee Final Review: Meeting Number /// G Date M//7 [J b Approved by: N d NA4 Date M - #2 -83 Op. Com. Results Review: rte 4-Mculv/ Mtg.# [l/ G Date 2//7/f3 u PURPOSE The purpose of this procedure is to provide a guide for the Radiological Emergency Cooroinator (REC), the use of which will ensure that the duties assigned to the Health Physics Group are not overlooked. CONDITIONS & PREREQUISITES ,
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s An emergency condition has been declared which requires the TSC to be activated. t ORGANIZATION AND RESPONSIBILITIES A. In Charge - Radiological Emergency Coordinator
- 8. .Assista.nce - Monitoring Section Leader . ,
Chemistry and Dose Assessment Section Leader - PROCEDURE . PART I - Initial Actions _ - STEP 1 Report to TSC and assume control of Health Physics Group. STEP 2 Determine current plant status. i-STEP 3 Ensure that the emergency access control is activated (Referen'ce A.2-108). Local evacuation and followup personnel accounting should be considered in order to increase effectiveness of access contr67 function (Reference A.2-301). STEP 4 Ensure that appropriate onsite monitoring is initiated (Reference A.2-201). -
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. Procedure A.2-209 Revision 0 - -
Page 2 of 4 ,
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STEP 5 Dispatch a qualified technician (RPS) to activate and operate the backup q countroom at the EOF. The technician should be instructed to report to ..y the RPSS (or Emergency. Manager, if RPSS not present) upon arrival at the . EOF. STEP 6 If significant. radioactive releases are occurring or if a Site Area Emergency has been declared, ensure that off-site monitoring is initiated (Referencc: A.2-202). STEP 7 Evaluate the Health Physics Group staffing. If the situation dictates, call in off-duty personnel, request assistance from Prairie Island, and/ or arrange for contract personnel to augment the staff. PART II - Continuino Actions NOTE: The REC CHECKLIST (see example in Attachment 1) should be used to coordinate these actions. . , STEP 1 Continuously evaluate habitability. a'. Direct surveys in manned centers - TSC, OSC, Control Room, Access Control, Assembly Point, CAS and SAS. (Don't forget Security Person , on pi' ant access road.)
- b. Post conditions on status board. ,
- c. Make evacuation recommendations as necessary (
Reference:
A.2-201, Attachment 2). ' NOTE: Surveys and posting may be assigned to Monitoring Sec. tion Leader. STEP 2 Continu'ou, sly assess.i ra'diological 'a'sp'ects of situation.
- a. If an airborne rel, ease'is occurring: , ,
Direct site and off-site surveys (
Reference:
A.2-202). i Approximate plume location (notify EOF if plume is located -
,, in EOF Sector).
Verify dose projection numbers. . Chart and record survey results.
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, " NOTE: Surveys, plume' tracking, verification and results t - charting / recording may be assigned to Monitoring Section Leader.
- b. If an airborne release is occurring:
Project off-site doses and dose rates (
Reference:
A.2-406). g D s . WP/kk
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Procedure A.2-209 Revision 0 Page 3 of,4 _ Provide copies of dose projection reports to Monitoring Section s
] Leader and Radiological Emergency Coordinator.
Post dose projection results on status board. NOTE: Dose projection activities may be assigned--to Chemistry Section- Leader.
- c. If a liquid release is occurring, direct surveys of river as
. appropriate (
Reference:
A.2-202). NOTE: Survey may be assigned to Monitoring Section Leader.
- d. Direct appropriate pr.ocess samples be obtained and analyzed
(
Reference:
A.2-207). Sample each release point. Ensure that radioiodine component of any release be sampled and analyzed as soon as possible. Assess core damage, as applicable (
Reference:
A.2-208).
- e. Formulate off-site protecti've action recommendations and forward to Emergency Director (
Reference:
A.2-204).
- f. Determine appropriate on-site protective action (
Reference:
A.2-201, Attachment 2). -
. ,) g- Review emergency classification (
Reference:
A.2-101), especially Guidelines-1, 2, 6 and 28. STEP 3 Ensure that co'ncerned personnel are kept informed of radiological status:
- a. Periodically update Emergency Director.
- b. Ensure that radiological status board'in TSC is maiiit'ined; a
- c. Ensure that Access Control is updated.
- d. Ensure that off-site survey teams are kept informed.
- e. Update Radiation Protection Support Supervisor in EOF.
- f. Until RPSS post is activ'ted, a ensure that FOLLOWUP MESSAGE is initiated and forwarded to Minnesota Health Department period-ically (at least every 30 minutes).
STEP 4 Acknowledge the HPN phone if it rings. Provide information as requested. Responsibility for manning HPN line may be transferred ' to RPSS when EOF is fully activated. WP/kk e ee'v* -
Procedura A.2-209 Revision 0 - -
", _ Page 4 of 4 -
Form 5790-209-1 o. Revision 0, 02/15/83. N Page 1 of 1 x x ATTACHMENT 1 V-Example of p_ - - REC CHECKLIST Habitability: TSC i 1 l l l l l .I I OSC l l l l l l l- 1 I Access Control ,/ l l l l l l l l l Control Room I i i l l l l l l CAS I i l l l I l l l SAS I [ l l I l l l l Assembly Point , I l l l- l I I I l Assessment: - Dose Projection l l l l l l l l l I:NG Ratio I i l l l l l l l Process. Sampler I I l i i i ! l i Plume Location l l l l l l l l -y Dose Projection Verification i I l l l 'l l l l Protective Action Recommendations l l l l l l l l l Emergency Classificati.on I i 1 l l l l l l Updates:
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Emergency Director - 1 I l l l l l l 1 Status Board 'l l l l l l l l I Access Control. I I I l l l l l l Off-site Survey Teams l I I l l l 1 I I RPSS I l l l 1 -l i l l
. Minnesota Health Department l l l l l l l~ l l a
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s Procedura A.2-413 Revision 1 Page 1 of 6 Op. Com. Rev. Reg'd. Yes X No Q.A. Review Req'd. Yes No X ALARA Review Reg'd. Yes X No
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SMALL VOLUME LIQUID SAMPLE OBTAINED AT THE POST ACCIDENT SAMPLING SYSTEM Procedure A.2-413 Prepared by: 2 .% ALARA Review: CdOkl .- Date 2Mj3 Reviewed by: N//[/[f/g/4 - Q.A., Review: Revision 0 Date 8/16/82 Operations Committee Final Review: Meeting Number: //73 Date .2//c/f3 Approved by: Nkbk Date O-//- 83 0p. Com. Results Review: Not Required Mtg. # 11)0 Date 7/29/82 PURPOSE . The purpose of this procedure is to provide special instructions and precautions for collection and handling of small volume liquid samples obtained from the Post Accident Sampling System during and following an emergency at Monticello Nuclear Generating Plant. CONDITIONS AND PREREQUISITES , The Emergency Director / REC /CSL has requested analysis of RHR or Jet Pump liquid samples. Actual or potential radiological conditions are such that special methods and/or precautions are necessary in order to collect and analyze samples under conditions which may present a much greater than normal radiation hazard to individuals performing the. sampling and analyses. Unless directed otherwise, this procedure should be used in lieu of routine sampling and analysis procedures whenever an Alert or higher emergency classification is declared.
.0RGANfZATION AND RESPONSIBILITIES '
l . . Emergency Director - Overall responsibility REC /CSL - Responsible for assigning sample priority and frequency and results review. Chemistry Technicians - Responsible for sample collection, analysis and results I reporting. PRECAUTIONS - A. Exposures of sampling and analysis personnel shall be in accordance with A.2-401, " Emergency Exposure Control". - B. Exposures to all personnel due,to sampling and analysis operati~ons should be maintained as low as is reasonably achieveable. Techniques such as
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Procedure A.2-413 ~'~
, Revision 1 Page 2 of 6-temporary shielding, remote handling and sample dilution prior to analysis 9 should be considered to reduce exposure to personnel. d C. When actual or potential radiation levels so warrant, high range portable survey instruments, and scif-reading dosimeters shall be provided to sampling and analysis personnel to permit rapid assessment of high exposure rates and accumulated personnel exposure. Alarming dosimeters should also be considered.
D. Appropriate extremity dosimeters should be provided and worn when handling samples which themselves represent high-level radiation sources. E. Calculations for exposure rates resulting from radiation within a few hours after a Loss of Coolant Accident point out the desirability of spending - minimum amount of time that is necessary near the surface of the sample enclosure. Most of the operation of the Post Accident Sampling System located at 951' of Turbine Building can be performed from the control panel. With the control panel located ten or more feet away from the sample enclosure the dose rates at th'e control
- panel due to radiation from the sample' enclosure will be below 100 MR/HR. The indicator for the area radiation detector RE-507 is on the PASS control panel and .its reading should be noted whenever the presence of radiation is suspected.
REMARKS ~- ,
- 1. The Post Accident Sampling S,tation is located on the south side of the 951' level of the turbine ~ building. The most efficient route to the PASS is- .-)
through access-control and into the turbine building. Move to the 951'. v level via the east stairway.
- 2. Two RPS should be used to obtain a post-accident sample When applicable and possibje. ,
- 3. Obtain controlled access key 33A from R J. Coordinator and key #153 from Shi.ft Si;pervisor. ,, ,
EQUIPMENT REQUIRED ,
- 1. 20 ml. sample vial -
- 2. Small volume cask
- 3. pH paper .
- 4. Flashlight ,
- 5. 1 liter demin water
- 6. Syringe ,
- 7. Neoprene ca.ps --
- 8. A10minum retainer rings
- 9. Needles 10.' Vial retainer ring crimper
- 11. Needle changing tool
- 12. Radector III or equivalent WP/kk
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Procedure A.2-413 Revision 1 Page 3 of 6 3 PROCEDURE
"' STEP 1 Before traveling to the samp. ling station advise Shift Supervisor and call control. room, to determine whether A or B RHR is operating. Determine from Control Room if RBCCW pumps are operating. Also advise Control Room that jet pump A flow transmitter, FT 2-3-64W or jet pump B flow transmitter FT 2-3-64M may be affected during primary-coolant sampling.
NOTE 1 If neither RHR loop is operating, the position of the Liquid Return Selection Switch is immaterial. STEP 2 Confirm that the demineralized water t'ank level is above the minimum mark on the sight glass level indicator (if not, perform Procedure A.2-418). . STEP 3 Open the nitrogen supply and regulate the supply pressure to 100 psi. STEP 4 Turn on ventilation anit by depressing " START" button. Verify vacuum by feeling suction at one of the gas ports. STEP 5 Set switch HC-600'to position A. STEP 6 If determination of pH is desired place a pH indicator strip in a 20 ml sample bottle. __ STEP 7 Check the condition of the needles on the right to verify that they-are not bent. .(They should be slightly angled inward toward one another.) Replace bent or dama*ged needles using needle changing tool. , STEP 8 Move the small volume cask positioner into place below the sample l , station. STEP 9 Put. the small volume cask into. the cask positioner. STEP 10 Remove the. stopper and carrying handle from the small volume cask .by tanscrewing it. ~ STEP 11 Slide the lead shielding drawer out so that the needles under the sample station enclosure are exposed. STEP 12 Swing the cask into position under the sample station and attach the chain to the cask holder. l STEP 13 Put the 20 mi sample bottle with an outer aluminum retainer ring and I neoprene cap into the small volume cask. Check that the bottle,, lift-ing lever is free to move up and down. STEP 14 Turn HC-700 to " liquid" mode.
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Procedure A.2-413 Revision 1 ' y , , Page 4 'of 6 PROCEDURE (Cont'd.) A N s d
' STEP 15 Turn HC-626, LIQUID SAMPLE SOURCE SELECTOR, switch to position 2' (Jet Pump) or position 4 (RHR) as determined by the Emergency Director or his designee.
STEP 16 Raise the sample bottle into position on the needles by lifting the lever on the side of the cask. The bottle position status light on the control panel will change from red to green when the bottle is in position. (If the bottle position status light does not change to green do not continue to the next step until the problem is' corrected.) STEP 17' Turn the liquid sample source selector switch HC-626 to position 1 for
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Jet Pump Bypass Line or to position 5 for Residual Heat Removal (RHR) Bypass Line. STEP 18 Set switch HC-500 to the position corresponding to the sample desired. Set the Liquid Return Selection Switch to A or B corresponding to the
, operating RHR loop'(see NOTE 1).
NOTE 2 PCV-627 should be adjusted slowly in the following steps to avoid closing system excess flow check valves. STEP 19 Adjust PCV-627 slowly so that-the flow through FCV-627 is about 1 gpm' as verified on FI-664. Continue this flow for a minimum time of 5 , minutes. Record the flow and flush time on the Small Volume Liquid - Sampiing and Analysis Checklist.
]_.-
STEP 20 After the flush is completed, turn switch HC-626 to position 2 if the sampling valves were set in STEP 18 above for Jet Pump sample or to position 4 if the sampling valves were set for an RHR sample. l STEP 21' Note that the fl'ow per indicator FI-664 is reduced. With PCV-627 adjust valve FCV-627 for a flow of about 0.3'gpm. i ' STEP 22 Rscord th'e follosing'on the Sma'll Vol6me Liquid Sa'mpling and Analysis
. Checklist: Flow per FI-664, pressure per PI-661, Temperature per II-660, Conductivity per GI-663 and Radiation per RI-665.
STEP 23 Turn the small volume liquid sample selector switch HC-616-1 to the .
"take sample" position. Valve CV-616 will rotate and carry the sample l into alignment with the line to the sample bottle. The valve is l energized in 10 seconds as indicated on mimic board.
STEP 24 Verify that the flow per FI-664 is zero. NOTE 3 If pH is being determined the syringe in STEP 25 shall be filled , with air rather than water. STEP 25 Load a syringe with 10 cc of demin water. WP/kk
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Procsdura A.2-413 Revision 1
, . Page,5 of 6 ^
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egg PROCEDURE (Cont'd.)
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STEP 26 Connect the syringe onto the line provided for it on the top-right side of the sample station. Open the two manual valves and press on the syringe and inject all of the 10 cc of water (air) into the line. STEP 27 Close the manual valves. STEP 28 Remove ~ the syringe and fill it with air. STEP 29 Re-attach the syringe and open the two manual valves and inject the air. STEP 30 Turn the switch'HC-616-1 back to the OFF position. STEP 31 If pH is being determined repeat STEP 23 through 30 three times to assure that enough sample has been blown into the sample bottle to moisten the pH paper. STEP 32 Close the two manual valves and remove the syringe. STEP 33 Turn HC-500 SAMPLE SOURCE SELECTION SWITCH to position 9 if a jet pump sample was taken or position 6 if a RHR sample was taken. STEP 34 Turn the switch HC-616-1 to the FLUSH position. Flush for 2 minutes
^; or until RI-665 reaches a minimum.
..]
STEP 35 When the flush is finished turn' switch HC-626 to 0FF, then HC-616-1 to 0FF. STEP 36 Turn PCV-627 fully counterclockwise.
. STEP 37 Perform the Drain:of Trap, Sump and Collector procedure (Procedure
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A.2-417). STEP 38 Turn ventilation off by depressing "STOP" button. STEP 39 IfpHisbeingdeEerminedremovethesamplebottleandcomparethe color of the pH indicator strip to that of the comparator strips and record results on the Small Volume Liquid Sampling and Analysis Checklist. STEP 40 Transport sample to hot lab using the small volume liquid cask for analysis per Procedure A.2-419. ._
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Procedure A.2-413 Revision 1 '- Page 6 6f 6. Form 5790-413-1 - Revision 0, 05/26/82 Example of k-Page 1 of 1 SMALL VOLUME LIQUID SAMPLING AND ANALYSIS CHECKL'IST s Sampling
- 1. Sample Source Date Time
. RPS
- 2. Sample Identification No.
3 , 3. Bypass Flow FI-664 (gpm)
- 4. Flush Time Minutes
- 5. Sample Flow FI-664 (gpm)
,6. Pressure PI-661 (psia)
- 7. Temperature TI-660 ( F)
- 8. Conductivity Meter pmhos/cm Scale CI-663
- 9. Radiation RI-665
' Analysis - - - .
Initial l
- 1. Spectrum collected (dilution fact. ors x ) ']
j 2, Analyze spectrum ~'
- 3. Activity calculated (pCi/cc)
- 4. pH .
- 5. ppb Ch4 ride (From Chemistry Procedure I.1.'3)
- 6. ppm Boron,(From Chemistry Procedure I.1.40)
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- 7. Other analyse's resdits as requeste'd and commints:
l l
- Performed by
- Date l Reviewed by: CSL or REC Date ._
NOTE: After this checklist is completed and is not required for immediate use, it shall be placed in the appropriate container provided for Emergency Records.
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; Procedure A.2-414 Revision 1 Page 1 of 13
. 0p. Com. Rev. Reg'd. Yes X No Q.A. Review Req'd.
Yes No X
] ALARA Review Req'd. Yes X No V
x LARGE VOLUME LIQUID SAMPLE AND/0R DISSOLVED - N GAS SAMPLE OBTAINED AT POST ACCIDENT SAMPLING SYSTEM Procedure A.2-414 Prepared by: ALARA Review: $d/N - -- Date 2/G /n Reviewed by:[/A/7/h/MI"A _ Q.A. Review: Revision 0 Date 8/16/82 OperationsCommi[teeFinalReviN: Meeting Number: //f3 Date ple/53 Approved'by: N 'k M Date D-Il-? S
.Op. Com. Results Review: Not Required Mtg. # 1500 Date 7/24/82 PURPOSE The purpose of this procedure is to provide special instructions and precautions for collection and handling of large volume liquid and dissolved gas samples during and following an emergency at Monticello Nuclear Generating Plant.
CONDITIONS AND PREREQUISITES
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The Emergency Director / REC /CSL has requested a dissolved gas analysis of RHR or Jet Pump liquid samples. A.large volume liquid sample may be obtained if . requ'ested for offsite analysis and for onsite analysis if coolant activity is low enough that a large volume sample (10 mls.) can be handled in the hot lab without undue exposure to technicians. Actual or potential radiological conditions are such that special methods and/or precautions are necessary in order to collect and analyze samples under conditions which may present a much greater than normal radiation hazard to individuals performing the sampling and analyses. Unless directed otherwise, this procedurs should be used in lieu of routine sampling and analysis procedures whenever an Alert.or higher emergency classification is declared. ORGANIZATION AND RESPONSIBILITIES Emergency Director - Overall responsibility REC /CSL - Responsible for assigning sample priority and frequency and results review. Chemistry Technicians - Responsible for sample collection, analysis and results reporting. ~~ PRECAUTIONS A. Exposures of sampling and analysis personnel shall be in accordance with A.2-401, " Emergency Exposure Control". B. Exposures to all personnel due to sampling and analysis operations should
@d-be maintained as low as is reasonably achieveable. Techniques such as i temporary shielding, remote handling and sample dilution prior to analysis l should be considered to reduce exposure to personnel.
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j , Procedure A.2-414
- Revision 1 - '
Page 2'of 13 PRECAUTIONS (Cont'd.) C. W When actual or potential radiation levels so warrant, high range portable survey instruments, and self-reading dosimeters shall be provided to sampling and analysis personnel to permit rapid assessment of high exposure rates and accumulated personnel exposure. Alarming dosimeters should also be considered. D. Appropriate extremity dosimeters should be provided and worn when handling samples which themselves represent high level radiation sources. E. Calculations for exposure rates resulting from radiation within a few hours-after a Loss of Coolant Accident point out the desirability of spending the minimum amount of time that is necessary near the surface of the sample enclosure. Most of the operation of the Post Accident Sampling System located at 951' of Turbine Building.can be performed from the control panel. With the control panel located ten or inore feet away from the sample enclosure the dose rates at the control panel due to radiation from the sample enclosure
. will be below 100 MR/HR. The indicator for the area radiation detector RE-507 is on the PASS control panel and its reading should be noted whenever the i presence of radiation is suspected.
REMARKS i 1. The Post Accident Sampling Station-is-located on the south side of the 951' level of the Turbine Building. The most efficient route to the PASS is through access control and into the Turbine Building. Move to the 951' - .m level via the east stairway. *)
- 2. Two-man teams should be used to obtain a post-accident sample when possible.
l 3. Obtain controlled access key 33A from R.P. Coordinator and key #153 from Shift Supervisor. . EQUIPMENT REQUIRED - -
- 1. 15 ml. sample vial 9. Vial retainer ring crimper
- 2. Large volume cask -
- 10. Needles
- 3. Rubber septums 11. Needle changing tool
- 4. Flashlight 12. Rubber, stopper
- 5. Gas vial cask 13. Gas vial carrying cask
- 6. Gas vial positioner 14. 20 ml gas vial
- 7. Neoprene cap 15. .Large volume liquid cask
- 8. Aluminum retainer ring 16. Jumper cable I
. PROCEDURE l
NOTE 1 Use Form #5790-414-1 when obtaining a large volume liquid sample and Form #5790-414-2 when sampling dissolved gas. STEP 1 Before traveling to the PASS Station call control room to advise the Shift Supervisor of your intentions and determine whether A or 8 RHR L l is operating. , Determine if RBCCW pumps are operating. Also advise contr.qy Q
' room that Jet Pump A flow transmitter, FT 2-3-64W or Jet Pump B flow transmitter, FT 2-3-64M may be affected during sampling.
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}# ' . . Proceduro A.2-414 Revision 1
.Page 3 of 13
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.) .
NOTE 2 If neither RHR loop is operating, the position of the Liquid Return Selection Switch is immaterial. STEP 2 Co'nfirm that the demineralized water tank level is above the minimum mark on the sight glass level indicator (if not, perform Procedure A.2-418). STEP 3 Open the nitrogen supply and regulate the supply pressure to 100 psi. STEP 4 Set switch HC-600 to position A. STEP 5 Check that Krypton Tracer gas at approximately 5 psig is available and that valve PAS-57-10 is open. STEP 6 Turn on ventilation unit by depressing START button. Verify vacuum by feeling suction at one of the two gas ports. STEP 7 Slide the lead shield drawer out so that the needles under the sample station enclosure are exposed. Inspect the needles. Replace bent or damaged needles using needle changing tool. (The needles should be slightly angled inward toward-one.another. ) STEP 8 Remove the lead stopper from the large volume cask and put a 20 ml.-
, sample bottle with an outer aluminum retainer ring and a neoprene cap into the large cask. With the cask in the fully lowered position, roll the cask into the position under the sample station.
STEP 9 Turn HC-700 switch to "Ifquid" mode. STEP 10 With the handle on th'e hydraulic pump of the large volume cask start raising the cask. Look for possible misalignment (by removing the lead shield drawer and looking into' the drawer slot the needle area can be seen). If the cask'is positioned correctly'underneath the ' sample enclosure the top part of the cask will fit into the bottom opening in the sample station. Stop pumping when the top cask ring is inside and the large volume cask is just touching the bottom of the sample station. STEP 11 Turn HC-626, LIQUID SAMPLE SOURCE SELECTOR, switch to position 2 (Jet Pump) or position 4 (RHR) as determined by the. Emergency Director or his designee. STEP 12 Push the cask plunger down that causes the sample bottle to be raised out of the cask and up and onto the two needles. When the bottle is up and correctly onto the needles the " Bottle In" lights on the control panel will change from red to green. (If the bottle position status light does not change to green, do not continue to the next step until the problem is corrected.) WP/kk
Procedure A.2-414 ~ Rsvision 1
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Page 4 of 13 PROCEDURE (Con'.'d. ) O
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STEP 13 If a dissolved gas samplex is to be obtained place a\15 ml gas vial with a septum and cap into the gas vial positioner and slide the positioner into the dissolved gas port (lower of two ports) and turn it to lock it into place. Observe that the bottle status light changes from red to green. STEP 14 Turn the liquid sample source selector switch HC-626 to position 1 for Jet Pump Bypass Line or to ' position 5 for Residual Heat Removal
. Bypass (RHR) line corresponding to the sample source.
STEP 15 Verify HC-616-1, SMALL V'0 LUME SAMPLE, switch is off. STEP 16 Set switch HC-500.to the position corresponding to the sample desired. Set Liquid Return Selection Switch to A or B corresponding to the operating RHR Loop (see STEP 1 and NOTE 2). NOTE 3 PCV-627 should be adjusted slowly in the following steps to avoid closing system excess flow check valves. STEP 17 Adjust PCV-627 so that the flow through FCV-627 is about 1 gpm
~
as verified on FI-654. Continue- this flow for a minimum time of 5 minutes. Record the flow from FI-664 and the flush time on the appropriate checklist. ~ '
)
STEP 18 ' After the flush is comple'ed, t turn the Liquid Sample Source selector -' l , switch HC-626 to position 2 f f switch HC-500 was previously positioned for a Jet Pump sample or to position 4 if switch HC-500 was positioned-
. for an RHR sample. Note that the flow per indicator FI-664 is reduced.
1 N - With PCV-627 adjus.t valve FCV-627 for a flow of about 0.3. gpm. STEP 19 'Open secondary contain mne t return line valve by jumpering TBS-1 to TBS-27 (you shculd obtain a red status. light for position 5 of.HC-500).
. NOTE 4 The sample system lines and valves are probably filled with quite a .
bit of air and by going through the complete cycle (HC-601 positions 1 through 11) about 3 times without taking a' sample, the air is effectively purged from the system. During the first three cycles turn through positions 5 and 10 quickly. Observe the pressure on l
. PI-662 when in position 9. The readings will be highest on the first cycle and should be repeatable on the last two cycles.
STEP 20 Turn liC-601 through positions 1 through 11 three times allowing 2 or 3 seconds per position except positions 5 and 10 (see NOTE 4). STEP 21 Turn the Dissolved Gas and Liquid Sample System switch HC-601 to position 1 and observe that P-701 starts and valve CV-622 rotates.
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- x Procedure A.2-414 Revision 1
., Page 5 of 13 l q PROCEDURE (Cont'd.) ,
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STEP 22 Turn switch HC-601 to position 2 and observe that P-601 starts. Record the following on the appropriate checklist. Flow per FI-664, STEP 23 Pressure per PI-662, Temperature per TI-660, Conductivity per CI-663 and Radiation per RI-665. STEP 24 Turn switch HC-601 to position 3 to isolate the sample and start the dissolved gas separation. Leave in this position for approximately 10 seconds. STEP 25 Turn to position 4 to inject tracer gas into valve CV-615. Leave in this position for approximately'10 seconds. Read and record the tracer gas supply system pressure. NOTE 5 If it is desirable not to introduce tracer gas into the loop, turn switch HC-601 through position 5 very quickly and valve CV-615 will not be rotated. STEP 26 Turn to position 5 to put the tracer gas into the loop (see NOTE 5). STEP 27 Read the initial pressure of the- dissolved gas sample bottle at this time from PI-662 and record as P, on the appropriate checklist. . 3 NOTE 6 Water will evaporate until a saturated condition is reached. The
. slow' increase in pressure due to this evaporation may be observed on PI-662. Reaching a saturated condition takes about 30 seconds.
If you wait for this equilibrium, condensation will be present in the sampling vial. It is recommended that the switch HC-601 be left in position.6 for no more than 5 seconds.
. STEP 28 Turn to position 6 for 1 5 seconds (see' NOTE 6).
L STEP 29 Turntoposition7to'again'circulatethekiquid. int' hep-601 loop.~ ! Leave in this position approximately 10 seconds. STEP 30 Read PI-662 again and record its value as Py ' on the appropriate check-list. ,
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' STEP 31 Turn to position 8 for no more than 5 seconds. .
STEP 32 ' Turn to position 9 to get ready to take the dissolved gas sample or ! to relieve the collection chamber pressure. Record PI-662 as P " the agipropriate checklist as this is the pressure of the liquid2 i sample loop at the time the sample is taken. t wg
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- Proc: dure A.2-414 Revision 1 -
[ .' Page 6 of 13 PROCEDURE (Cont'd.) CAUTION: There is a potential for having a higher gas pressure in the gas chamber' than can be safely handled in the dissolved gas sample vial. If the pressure observed (PI-662)' indicates an off-scale reading, relieve the pressure to near atmospheric pressure as described in STEP 35 prior to taking the sample as described in STEP 34. STEP 33 If only a liquid sample is to be obtained skip STEP 34. STEP 34 Turn switch HC-6s2 to " Gas Sample" and hold it there while watch-ing PI-662. After at least 10 seconds and when PI-662 is very steady, release HC-652 and it will spring back to its center pos-ition. Turn HC-652 again to " Gas Sample" to verify the equalized pressure and read PI-662. Record the steady PI-662 pressure as P reading on the appropriate checklist. 3 STEP 35 When a _ dissolved gas sample is not desired it is only necessary to
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relieve the gas pressure back to the'suppressiori pool by rotating switch HC-652 counterclockwise to the lower position and hold it . while watching PI-662. The pressures will equalize very rapidly. STEP 36 If a large volume liquid samole is desired, turn HC-601 to position * .s
- 10. Pushbutton HC-629-1 must be pushed and' held for liquid to be drawn into the sample bottle that was earlier positioned under the s) sample station. Hold the pushbutton for at least 10 seconds. If a liquid sample is not desired, turn the switch HC-601 to the OFF position very quickly.
STEP 37 Turn HC-601 to 0FF. STEP 38 Lower the liquid sample bottle into the large cask:by pulling up on the plunger handle. Do not turn plunger handle as twisting 'the - bottle while it is on the needles will bend the needles. STEP 39 Lower the cask on the cart by relieving the hydraulic oil pressure with the small petcock handle on the hydraulic cylinder. STEP 40 Slide the lead shield drawer back into the enclosure to cover the opening for the needles. STEP 41 Roll t.he cask out from under the sample station and quickly put.the - lead plug into the top of the cask. Be careful not to lean over the top of the cask where there will be a column of radiation before the plug is inserted. STEP 42 Roll the cask away from the sample station and prepare for off-site shipment or on-site analysis as directed. If a dissolved gas sample was not obtained go to STEP 45.
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s Rzvision 1
, Page 7 of 13 f~
T PROCEDURE (Cont'd.)
~.l TEP 43 3
Open and placesthe gas vial carrying cask near the sample station. Remove the gas vial positioner from the sample enclosure. Keep the yial at a maximum distance and quickly insert the sample bottle into the gas vial cask. Close and latch the gas vial cask. STEP 44 Place a rubber stopper into the port in the sample station from which the gas vial positioner was withdrawn. STEP 45 Turn HC-500 to position 9 if a jet pump sample was taken or position 6 if a RHR sample was taken. STEP 46 Turn the flush system switch HC-628-1 to position 2. Adjust PCV-672 for maximum flow per FI-664. ~ STEP 47 After RI-665 shows radiation has decreased significantly, turn switch HC-628-1 to position 3. Observe RI-665. STEP 48 When the radiation reaches a minimum turn switch HC-628-1 to position 4. Observe RI-665. . STEP 49 When the radiation reaches a-minimum turn switch HC-628-1 to position 5. Obserye RI-665. A change in RF 665 may not be observable. 3 STEP 50 When the radiation reaches a minimum turn switch HC-628-1 to position 6.
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1 The bypass will be open for this flush and the main flow will not be past RI-665 so run this flush for 2-3 minutes. STEP 51 Turn switch HC-628-1 to position 7. Observe RI-665. STEP 52 Repeat STEPS 47 through 51.
~ STEP 53 Turn HC-626 to off position. . Then turn HC-628-1 to off position.
t STEP 54 Turn PCV-627 fully counterclockwise. STEP 55 Close PAS-57-10 a5d krypton gas cylinder valve. STEP 56 Remove the jumper installed in STEP 19. STEP 57 Perform the Drain of Trap, Sump aad Collector per Procedure A.2-417. STEP 58 Turn ventilation off by depressing STOP button. STEP'59' Transport the gas sample to the hot lab for analysis using the s vial carrying cask. I i
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Procedure A.2-414 Revision 1 - Page 8 of 13. Form #5790-414-1 t]) Revision 0, 05/26/82 ' Page 1 of l' Example of LARGE VOLUME LIQUID SAMPLING AND ANALYSIS CHECKLIST Sampling '
- 1. Sample Source: Date Time RPS
- 2. Sample Identification No.
- 3. Bypass Flow FI-664 (gpm)
- 4. Flush Time Minutes
(
- 5. Sample Flow FI-664 (gpm)
- 6. Pressui e PI-661 (psia) l 7. Temperature TI-660 ( F) i ,
j 8. Conductivity Meter Scale CI-663
- 9. Radiation RI-665 (mR/hr)
- 10. Initial Pressure P, PI-662 (psia) l
- 11. Pressure P y - PI-662 (psia)
- 12. Stabilized Pressure P 2 PI-662 (psia) .
13.- Stabilized Pressure P 3 PI-662 (psia)'
. ,[y Analysis Initial
- 1. Spectrum Ran (Dilution Factors x )
- 2. Spectrum Analyzed .
- 3. Activity' Calculated pCi/cc
- 4. pH -
- 5. ppb Chloride (From Attachment Chemistry. Procedure I.1.3)
- 6. ppm Boron (From Attachment Chemistry Procedure I.1.40)
- 7. 'Other analyses results as requested and comments:
Performed by: Date Reviewed by: CSL or REC Date NOTE: After this checklist is completed and is not required for immediate use, it shall be placed in the appropriate container provided for Emergency Records.
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Procedura A.2-414 Revision 1
, Page 9 of 13 a Form #5790-414-2
~j Revision 0, 05/26/82 Page l'of 5 Example of DISSOLVED GAS SAMPLING AND ANALYSIS CHECKLIST Sampling
- 1. Sample Source Date Time RPS
- 2. Sample Identification No.
- 3. Bypass Flow FI-664 (gpm)
- 4. Flush Time Minutes
- 5. Sample Flow FI-664 (gpm)
- 6. Pr' essure PI-661 (psia)
- 7. Temperature TI-660 ( F)
- 8. Conductivity Meter Scale CI-663
- 9. Radiation RI-665 (mR/hr)
- 10. Tracer Gas Supply System Pressure (psia)
- 11. Initial Pressure, P O ~~ PI-662 (psia)
- 12. Pressure, P PI-662 (psia) 7 ,
N 13. Stabilized Pressure, P PI-662 (psia) 2
- 14. Stabilized Pressure, P PI-662 (psia) 3 o
Analysis Initial
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- 1. Spectrum ran (Dilution Factors x )'
- 2. Spectrum Analyzed l
- 3. Activity Calculated pCi/cc
! 4. Dissolved Gas Analysis (complete pages 2 through 5)
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- 5. Other analysis results as requested or comments:
l . Performed by: Date: - Reviewed by: CSL or REC Date: NOTE: After this checklist is completed and is not required for immediate use, it shall be placed in the appropriate container provided for Emergency Records. Occ. .
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Procedure A.2-414 ( -
* . Revision 1 - '
Page lo of 13 Form #5790-414-2 P N
. Revision 0, 05/26/82 s d Page 2 of 5 \ Example of N DISSOLVED GAS SAMPLING AND ANALYSIS CHECKLIST (Cont'd.)
DISSOLVED GAS CALCULATIONS FOR TOTAL INVENTORY OF H , 0 , AND N 2 ASSAMPLEDINTHEPOSTACCIDENTSAMPLESTAfION2 The volume of dissolved gas sample in sample vial is: (Temperature and pressure must be in units of ' Kelvin and atmospheres respectively.) V sx = 0.05 x'T3 xP3= cc "(See NOTE page 5) The volume of 20 ' N2 , N2 and Kr in vial is: V2 2=V GC 2xV sx = cc V2 N2=V gg "2 x V sx = cc V2 2=VGC"2xVsx N
= cc V Kr = y Kr xV = - cc -
2 g The volume of 0 and N in vial prior to sampling is: ' (Pressuremustbeunic$ofatmospheres.) V1 02=PO x 14.9 x 0.21'= ~ cc
. 1E7 _
N V1 2=PO x 14.9 x 0.78 =
- cc . 4 IT7 The volume of oxygen, hydrogen, nitrogen and krypton col'lected from isolated sample system is:
0 V3 2=V 2 2-V 2 y
= cc V3 H2=V 22N = cc N
V3 2=V 2 2-V y2 = cc Kr ,y Kr = cc 3 2
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Pr:c dure A.2-414 s Revisicn 1 Page 11 of 13,
-g Form 5790-414-2 i Revision 0, 05/26/02 Page 3 of 5 -
'N Example of DISSOLVED GAS SAMPLING AND ANALYS15 CHECKLIST (Cont'd.)
i , J The volume of injected tracer gas (Kr) is: Vg Kr = 0.022 x P Kr = cc . The concentration of 02 ' N2 and N2 in isolated sample system is: 0 0 C1 2 = (V 32/117.8) x (V gE"/V 3Kr) = cc/mi H 2O C1 H2 = (V32/117.8) N x WyKrjy ) = cc/ml H 2O 3 CyN2 = (V3 2 117.8) x (Vy Krjy h) = cc/ml H 2O - 3 The volume of 02 , H2and N gin the system being sampled (see Sample Sou'ce r on Page 1) is:
0 s
; C2 2=C y2xV = cc H s C2 N2=C 72xV = cc N s C2 2=C y2xV ,-
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Pr:c:duro A.2-414 RIvisien 1 *- i
. Page 12'of 13 ,
Form 5790-414-2 Revision 0, 05/26/82
/3 Page 4 of 5
- ExamplEof' DISSOLVED GAS SAMPLING AND ANALYSIS CHECKLIST (Cont'd. )
V sx
= v lume of dissolved gas sample in sample-vial (cc)
. P 3
= pressure of sample (item #14 on page 1) psia T, = temperature of sample (item #7 on page 1) psia V
GC 2= %0 determined by G.C. analysis in sample vial (Ch$mistry Procedure 1.1.36) V H= 2 %H determined by G.C. analysis in sample vial GC (Ch$mistry Procedure I.1.36) ' V N= 2 %N determined by G.C. analysis i'n sample vial GC (Ch$mistry Procedure I.1.36) s
.V GC Kr= % Kr determined by G.C. analysis in sample vial -
(Chemistry Procedure I.1.36)
.V 2
2= . volume of 20 in sample vial (cc) , N V 2 2= volume of H 2 in sample vial (cc), . V 2 2= volume of N 2 in sample vial (cc) . V2 Kr = volume of Kr.in sample vial (cc) - P O
= pres'sure of sample vial after evacuation (item #11 on page 1) psia 0
Vy 2= vbumeof0 2in sample vial prior to sampling (cc) i V1 "2 = volume of N 2 in sample vial prior to sampling (cc)
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r _ Pr ceduro A.2-414 Revision 1
. Page 13 of 13 Form 5790-414-2 S. Revision 0, 05/26/82. s
.' # N
- Page 5 of 5 . Example of DISSOLVED GAS' SAMPLING AND ANALYSIS CHECKLIST (Cont'd.)
V 3 2= the volume of 02 colle ted from the' isolated sample system N V 3 2= th,e volume of H 2 collected from the.fsolated sample system N V 3 2= the volume of N2 collected from the isolated sample system V Kr = the volume of Kr collected from the isolated sample system 3 P Kr. = pressure of tracer gas (Kr) (item #10 on page 1) Vy Kr = volume of injected tracer gas (Kr) C 1 2= concentration of 02in isolated-sample system H
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C 7 2= concentration of H2 in isolated sample system j N Cy 2= concentration of N2 in isolated sample system 1 S V = volu'me 'of water in system being sampled Use either 1.76E8 mis. for reactor coolant or
. 1.93E9 mis. for torus. .
C 2 2= the volume of 02in system being sampled l N C 2 2= the volume of H2in system being sampled C 2 2= the volume of N2in system being sampled
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NOTE: The following conversion factors will be required: , atmospheres =h
' Kelvin =hx('F-32)+273.15
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Procedure A.2-417-Rsvision 1 Page 1 of 3 Op. Com. Rev. Req'd. 'Yes X No
. Q.A. Review Req'd. Yes No X 3 ALARA Review Req'd. Yes X No DRAINING THE TRAP. SUMP AND COLLECTOR OF POST ACCIDENT SAMPLING SYSTEM Procedure A.2-417 Prepared by: e ALARA Review: 6d/I/d b Date Jh /83 Reviewed by: Mc / h 8P//6 A Q.A. Review: Revision 0 Date 7/28/82 Operations CommittIe Final Review: Meeting Number: // T3 Date DJe/J V Approved by: d Nhi Date S-lt 93
,0p. Com. Results Review: Not Required Mtg. # 1100 Date 7/29/82 PURPOSE The purpose of ,this procedure is.to provide special instructions and precautions for draining the trap, sump and collector of the PASS.
CONDITIONS AND PREREQUISITES A sample has been obtained at the PASS.__. ORGANIZATION AND RESP 0NSIBILITIES , Emergency Director - Overall responsibility , REC /CSL - Responsible for requesting a sample be obtained at the PASS. Chemistry Technician - Re'ponsible s for draining the trap, sump and collector.
-PREC'AUTIONS A. Exposures of. sampling personnel shall.be in-accordance with A.2-401,
" Emergency Exposure Control". '
B. Exposures to all persohnel due to sampling operations should be maintained as low as is reasonably achieveable. C. . When actual or fotential radiation levels so warrant, high. range portable
, survey instruments, and self-reading dosimeters shall be provided to sampling personnel to permit rapid assessment of high exposure rates and accumulated personnel exposure. Alarming dosimeters should also be considered. -
D. It is very important that the sump discharge to the suppression pool line be open before the drain and blow out operation is started, especially if valve FCV-627 is left open. If the discharge line is not open the 100 psi nitrogen used for discharging the collector tank V-715 will force the liquid into the liquid sample loop. Note that this may occur even if FCV-627 is N, closed since it is not a tight shut-off valve.
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x Procedure A.2-417 Revision 1 . - Page 2 of 3. PRECAUTIONS (Cont'd.)
.,-]
~ E. Calculations .for exposure rates resulting from radiation within a few hours af ter a Loss of Coolant Accident point out the desirability of spending mini-mum amount of time that is necessary near the surface of the sample enclosure. Most of the operation of the Post Accident Sampling System located at 951' of Turbine Building can be performed from the control panel. With the control panel located ten or more feet away from the sample enclosure the dose rates at the control panel due to radiation from the sample enclosure will be below 100 MR/HR. The indicator for the area radiation detector RE-507 is op the PASS control panel and its reading should be noted whenever the presence of radiation is suspected. REMARKS
- 1. . There f.s no automatic drain or blow down but'there is an alarm light to indicate that the level in the trap T-717 is high and .that the trap needs to be drained right away. This trap removes water from the gas sample lines.
If the liquid level becomes too high water will be sucked into an air pump and mechanical damage may result.
- 2. The drain and blow out sequence' will take precedence over any other operation.
Therefore the drain and blow out operation may be performed at any time by merely turning the Sump Drain System-Switch HC-715-1 to any position other than off. Any other operation sequence that may be occurring will immediately be stopped and when the Sump Drain System Switch HC-715-1 is return OFF position, interrupted, unless theother sample station switches operation were changed will return in the to the step previously d meantime.
- 3. The Post Accident Sampling Station is located on the south side of the 951' leve_1 of the turbine building. The most efficient route to the PASS is through access control and into the turbine bu'ilding. Move to the 951' level via the east stairway. -
4 .' Obtain controlled access key 33A from R.P. Coordinator and ' key #153 from Shi f t ' Supe'rvi sor. . PROCEDURE , NOTE 1 If neither RHR loop is operating, the position of the Liquid Return Selection Switch in STEP.1 is immaterial. STEP 1 Set switch HC-500 to position 9. Set the Liquid Return Selection Switch to A or B corresponding to the operating RHR Loop.
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STEP 2 Check'that the nitrogen tank supply valve and the corresponding valve PAS-57-11 or PAS-57-22 is open and that the pressure is set at 100 psig and verify that PASS Ventilation System is on. l v WP/kk
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Procedura A.2-417 Revision 1 Page 3 of.3
~'N PROCEDURE (Cont'd.)
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STEP 3 Check that the demineralized flush water tank levelxis above the minimum level mark on the site glass and is pressurized at 100 psig. (PI-4021) and that valves OM-136 and DM-137 are closed and DM-138 open and demin water iupply valve PAS-57-1 on PASS demin water tank is open. NOTE 2 If tank level is below minimum marking perform Procedure A.2-418 before proceeding. STEP 4 TurnahlcontrolpanelswitchesexceptHC-500upandoffandthenturn l the control panel power selector switch (HC-600) to "A". STEP 5 Turn the Liquid or Gas selector switch (HC-700) to Liquid. STEP 6 Turn HC-626 to position 2. STEP 7 Turn Flush System Switch.HC-628-1 counterclockwise to position 6. STEP 8 Use the knob' adjacent to .CV-627 gauge on the control panel.to obtain a flow per FI-664 of at least 0.4 gpm. STEP 9 Rotate HC-715 through positions 2 through 7 pausing about 5 seconds at each position. , l STEP 10 Turn HC-626 to 0FF. STEP 11 Turn HC-628 to 0FF. STEP 12 Turn HC-715'to 0FF position. . STEP 13 Turn HC-700 to 0FF. STEP 14' Turn PCV-627 fully countsrclockwise'. STEP 15 If this is the end of an operation, turn all switches to UP and 0FF position, turn Power Source Selector Switch (HC-600) to 0FF and secure nitrogen cylinder and associated valve PAS-57-21 or PAS-57-11. If the sampling operation is not complete, make only those changes consistent with the appropriate sampling procedure.
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o e . Procedurs A.2-425 1 .. Revision 0 Page i of 3 -
. Op. Com. Rev. Req'd. Yes x No -
..- Q.A. Review Req'd. Yes No X g3 .
ALARA Review Req'd. Yes v No
, POST ACCIDENT GAS SAMPLE LINE HEAT TRACE .
Procedure A.2-425 i Prepared by: p- ALARA Review: cal //dd.- Date.3/ /3 Reviewed by: 7/(I/d/f+'#-
' Q.A. Review: 'M 1 %.str.tr E e 2/7/s Operations Coamit[ee Final Review:' Meeting Number: '//13 Date' 3McA9 Approved by: d "M Date 214-P3 Op. Com. Results Review: Ac/ rema.e,/* Mtg. # Mf3 Date 2/o/f3
~ C l ' PURPOSE
' The purpose of this procedure is to provide special instructions and precautions for operating the post accident sampling systent gas sample line heat tracing. CONDITIONS AND PREREQUISITES 4 The Emergency Director / REC /CSL has requested t ' hat the gas sample line heat trace be turned on for possible sampling _of torus or drywell-atmosphere. , Actual or potential radiological conditions are such th'at special methods and/or
- , precautions are necessary to . minimize personnel exposure. Unless directed other- -
j wise,.this procedure should be used.in lieu of routine testing procedures whenever an Alert or higher emergency classification is declared. ORGANIZATION AND RESPONSIBILITIES
- Emergency. Director Overall
- responsibility *
{ REC /CSL .- Responsible fo'r requesting'tha't heat trace be turned on and off.
' ~
l Chem'isf.ry Technici5ns - Responsibl'e-for operating heat tracing for PAS gas lines. ., PRECAUTIONS A. Exposures of personnel shall be in accordance with A.2-401, " Emergency '
- Exposure Control". -
B. Exposures to all personnel operations should be maintained as low as is reasonably achieveable.
- C. When actual or potential radiation levels _ so warrant, high range portable survey instruments, and self-reading dosimeters shall be provided to sampling and analysis personnel to permit rapid assessipent of high exposure rates and accumulated personnel exposure. Alarming dosimeters should also be considered.
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" Rovision 0 - -
Page 2 of 3-REMARKS - A V
- 1. Once the heat tracing is turned on it will take about one hour for the temperature of the gas lines to reach the predetermined value. Therefore, the heat trace should be turned on as soon as it is anticipated that a drywell or torus atmosphere gas sample will be taken.
2; The heat trace controls are located in the MG Set Room in the Reactor Building. Proceed through the ventilation room on the third floor of the Administration Building to the MG Set Room. ,
- 3. Obtain CAP Key #1 from R.P. Coordinator and vital access key #211 from the Shift Supervisor.
- 4. Advise the Control Room, Security Shift Supervisor and the Radiation Protec-tion Coordinator of your intentions. .
EQUIPMENT REQUIRED
- Small standard screwdriver PROCEDURE PART I - Turn Heat Trace ON '
STEP 1 Open cabinet C283A. g STEP 2 Turn Silent / Reset Normal switch to Silent / Reset. STEP 3 Repeat STEPS 4 through 9 for each control module DW2, DW3, DW4, TR2,
, TR3, TR4 and TR5.
STEP 4 Turn Calibration control knob to 250'F. , \ . l STEP 5 Hold the CAL / READ switch on a control module in the CAL position. Using a screwdriver adjust the "SP" L.E.D. potentiometer until the
. green L.E.D. just-lights.
STEP 6 Hold the CAL / READ switch.on the same control module in the CAL position
. and verify that the "SP" L.E.D. comes on when the calibration control knob is rotated through 250'F i 3*F.
I STEP 7 Turn Calibr'ation control knob to 235'F. STEP 8 Hold the CAL / READ switch on the control module in the CAL posit 5n. Using a screwdriver adjust the "UT" potentiometer until the red L.E.D. Justlights. _ - STEP 9 Hold the CAL / READ switch on the same control module in the CAL position and verify that the "UT" L.E.D. comes on when the calibration control-knob is rotated through 235'F i 3'F. 7 m) STEP 10 Open cabinet C2838. ! WP/kk
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Procedure A.2-425
-Revision 0 Page 3 of 3
(, . l p PROCEDURE (Cont'd.)
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STEP 11 Turn Silent / Reset Normal switch to Silent / Reset. STEP 12 Repeat STEPS 4 through 9 for each control module DW1 and TRI. STEP 13 When the temperature indication from each module is greater than 235'F the Silent / Reset Normal Switch shall be turned to the Normal position. (The current-temperature for each module is determined by holding the CAL / READ switch for that module.in the READ position.) . NOTE 1 It will. require about one hour for.the heat trace to reach 250'F. To minimize radiation exposure leave the MG' Set Room and return to check the heat trace temperatures in about one hour. PART II - Turn Heat Trace OFF STEP 14 Open cabinet C283A STEP 15 TurnSilent/ResetNormalswitchtoSilent/ Reset. STEP 16 Repeat STEPS 17 through 22 for each' control' module DW2, DW3, DW4, TR2, TR3, TR4 and TRS. j STEP 17 Turn calibration control knob to 50"F.
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STEP 18 Hold the CAL / READ switch in the CAL position. Using a screwdriver adjust the "SP" L.E.D. potentiometer until the green L.E.D. just lights. i STEP 19 Hold the CAL / READ switch on the same control module in the CAL position and verify that the "SP" L.E.D. comes on when the calibration control knob, is rotated through 50'F i 3"F.-
, STEP 20 Turn calibration control knob to 40.'F. .
STEP 21 Hold the CAL / READ switch on the control module in the CAL position. Using a screwdriver adjust the "UT" potentiometer until the red L.E.D. justlights. L STEP 22 Hold the CAL / READ switch on the same control module in the CAL position and verify that the "UT" L.E.D. comes on when the calibration control knob is rotated through 40'F i 3'F. STEP 23 Turn the Silent / Reset Normal switch to Normal. l .. STEP 24 Open cabinet C2838.
' STEP 25 Turn Silent / Reset Normal switch to Silent / Reset.
STEP 26 Repeat STEPS 17 through 22 for each control module DW1 and TRI. ] Q STEP 27 Turn Silent / Reset Normal switch to Normal. WP/kk
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