ML022190282
| ML022190282 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 07/29/2002 |
| From: | Nazar M Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Security and Incident Response |
| References | |
| Download: ML022190282 (34) | |
Text
I SNMC Committed to Nuclear Excellence Mano K. Nazar Site Vice President Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC 1717 Wakonade Dr. East
- Welch MN 55089 July 29, 2002 US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 Docket Nos. 50-306 License Nos. DPR-60 Prairie Island Emergency Plan Implementing Procedures - F3 Emergency Response Plan Implementing Procedures Furnished with this letter are the Prairie Island Nuclear Generating Plant Emergency Plan Implementing Procedures F3. This revision includes the following procedures:
INDEXES: Emergency Plan Implementing Procedures TOC REVISIONS F3-19 Personnel & Equipment Monitoring & Decontamination Rev 7 F3-26.2 Radiation Monitor Data on ERCS Rev 7 F3-18 Thyroid Iodine Blocking Agent (Potassium Iodine) Rev 10 DELETIONS None TEMPORARY CHANGE ADDITIONS F3-2 2002-1369 Classification of Emergencies INSTRUCTIONS:
Please post changes in your copy of the Prairie Island Nuclear Generating Plant Emergency Plan Implementing Procedures. Procedures, which have been superseded or deleted, should be destroyed.
Please sign and return the acknowledgment of this update to Bruce Loesch, Prairie Island Nuclear Generating Plant, 1717 Wakonade Drive East, Welch, MN 55089.
A.
.- *4' If you have any questions, please contact Mel Agen at 651-388-1121 Extension 4240.
Mano K. Nazar Site Vice Presid t Prairie Island NVelear Generating Plant c: USNRC - Steve Orth, Region 111 (2 copies)
NRC Resident Inspector (w/o attachment)
M Agen (w/o attachment)
Records Management (Doe Control Copy) (w/o attachment)
NL File (w/o attachment)
Mfst Num: 2002 - 0568 Date : 07/26/02 FROM : Bruce Loesch/Mary Gadient Loc : Prairie Island TO : UNDERWOOD, BETTY J Copy Num: 515 Holder : US NRC DOC CONTROL DESK SUBJECT : Revisions to CONTROLLED DOCUMENTS Procedure # Rev Title Revisions:
F3-19 7 PERSONNEL & EQUIPMENT MONITORING & DECONTA F3-26.2 7 RADIATION MONITOR DATA ON ERCS F3-18 10 THYROID IODINE BLOCKING AGENT (POTASSIUM I Temporary Change Additions:
2002 1369 F3-2 CLASSIFICATIONS OF EMERGENCIES UPDATING INSTRUCTIONS Place this material in your Prairie Island Controlled Manual or File. Remove revised or cancelled material and recycle it. Sign and date this letter in the space provided below within ten working days and return to Bruce Loesch or Mary Gadient, Prairie Island Nuclear Plant, 1717 Wakonade Drive E.,
Welch, MN 55089.
Contact Bruce Loesch (ext 4664) or Mary Gadient (ext 4478) if you have any questions.
Received the material stated above and complied with the updating instructions Date
PRAIRIE ISLAND NUCLEAR
Title:
GENERATING PLANT Emergency Plan Implementing Procedures TOC I Effective Date : 07/26/02 lApproved By:
3P Supf Document Title Rev F3-1 ONSITE EMERGENCY ORGANIZATION 19 F3-2 CLASSIFICATIONS OF EMERGENCIES 29 F3-3 RESPONSIBILITIES DURING A NOTIFICATION OF UNUSUAL 18 EVENT F3-4 RESPONSIBILITIES DURING AN ALERT, SITE AREA, 28 OR GENERAL EMERGENCY F3-5 EMERGENCY NOTIFICATIONS 20 F3-5.1 SWITCHBOARD OPERATOR DUTIES 8 F3-5.2 RESPONSE TO FALSE SIREN ACTIVATION 9 F3-5.3 RESPONSE TO RAILROAD GRADE CROSSING BLOCKAGE 8 F3-6 ACTIVATION & OPERATION OF TECHNICAL SUPPORT CENTER 16 F3-7 ACTIVATION & OPERATION OF OPERATIONAL SUPPORT 15 CENTER (OSC)
F3-8 RECOMMENDATIONS FOR OFFSITE PROTECTIVE ACTIONS 19 F3-8.1 RECOMMENDATIONS FOR OFFSITE PROTECTIVE ACTIONS FOR 12 THE ON SHIFT EMERGENCY DIRECTOR /SHIFT MANAGER F3-9 EMERGENCY EVACUATION 17 F3-10 PERSONNEL ACCOUNTABILITY 19 F3-11 SEARCH & RESCUE 8 F3-12 EMERGENCY EXPOSURE CONTROL 14 F3-13 OFFSITE DOSE CALCULATION 15 F3-13.3 MANUAL DOSE CALCULATIONS 11 F3-13.4 MIDAS METEOROLOGICAL DATA DISPLAY 7 F3-13.5 ALTERNATE METEOROLOGICAL DATA 4 Page I of 3
PRAIRIE ISLAND NUCLEAR Title : Emergency Plan Implementing Procedures TOC GENERATING PLANT Effective Date : 07/26/02 Document # Title Rev F3-13.6 WEATHER FORECASTING INFORMATION 1i F3-14.1 ONSITE RADIOLOGICAL MONITORING F3-14.2 OPERATIONS EMERGENCY SURVEYS 9 F3-15 RESPONSIBILITIES OF THE RADIATION SURVEY TEAMS 22 DURING A RADIOACTIVE AIRBORNE RELEASE F3 -16 RESPONSIBILITIES OF THE RADIATION SURVEY TEAMS 17 DURING A RADIOACTIVE LIQUID RELEASE F3-17 CORE DAMAGE ASSESSMENT 9 F3-18 THYROID IODINE BLOCKING AGENT (POTASSIUM IODIDE) 10 F3-19 PERSONNEL & EQUIPMENT MONITORING & DECONTAMINATION 7 F3-20 DETERMINATION OF RADIOACTIVE RELEASE 17 CONCENTRATIONS F3-20.1 DETERMINATION OF STEAM LINE DOSE RATES 9 F3-20.2 DETERMINATION OF SHIELD BUILDING VENT STACK 9 DOSE RATES F3-21 ESTABLISHMENT OF A SECONDARY ACCESS CONTROL POINT 10 F3-22 PRAIRIE ISLAND RADIATION PROTECTION GROUP RESPONSE 16 TO A MONTICELLO EMERGENCY F3-23 EMERGENCY SAMPLING 18 F3-23 .1 EMERGENCY HOTCELL PROCEDURE 11 F3-24 RECORD KEEPING DURING AN EMERGENCY 7 F3-25 REENTRY 8 F3-26.1 OPERATION OF THE ERCS DISPLAY 7 F3-26.2 RADIATION MONITOR DATA ON ERCS 7 F3 -26.3 ERDS - NRC DATA LINK 1 F3-29 EMERGENCY SECURITY PROCEDURES 18 F3-30 TRANSITION TO RECOVERY 6 I
Page 2 of 3
PRAIRIE ISLAND NUCLEAR Title : Emergency Plan Implementing Procedures TOC GENERATING PLANT Effective Date : 07/26/02 Document # Title Rev F3-31 RESPONSE TO SECURITY RELATED THREATS 5 F3-32 REVIEW OF EMERGENCY PREPAREDNESS DURING OR AFTER 2 NATURAL DISASTER EVENTS Page 3 of 3
PINGP 1300, Rev. 5 TCN # Cý0OO)_ I S4jP Retention- 6 years Effective Date: 7 2/6 W 7 Document Type: 1.190 Expiration Date: 41e3 750/3O/
TEMPORARY CHANGE NOTICE Page 1 of Z (5AWI 1.5.10)
CHANGE #: #: /2" 2*-
REQUEST Procedure REQUEST CHANGE Procedure #: I'3 -2. Rev: - 29 Project ID #:
WO WO #:
Title:
C d Description of Change: Ca v,f -e-4 F3 -z A77 4r<y't*!,WT I c16 41,ai/ou' L ce-s4 4~ 4LFM2~ogy (e.g page #. step #, q &r-34, F£ L_Ii A.
summary/reason) (z) fveie-5 CE .I¶i- d- P44%rA' (37) Pf ,V4 4 2 6A. cIle-e4-ecj0d *Iit4 'I'4ice 378f5
(&j , s*(,* 2A-f , -4I",,,/ .A z7:. , -i-?lV s'fS1,J,*/4LS Is this an OC reviewed procedure/critical WO? Yes No[] E Is a permanent ore VIed?*-A No El If Yes, submit PINGP 43 Employee #: FJ#L61 Date: ,
II. INITIAL REVIEWS A. Is this a change in intent? Yes E] No J If No, go to II B
- 1. OC Review Initial/Date (if procedure is OC reviewed/critical WO):
B. 10 CFR 50.59 Review
- 1. Is this change or procedure exempt from 10CFR 50.59 screening per 5AWI 3.3.5, App. A or B? Yes
- No El If Yes, go to II.C
- 2. Complete 50.59 screening per 5AWI 3.3.5/PINGP 1229. Screening/Evaluation-# _
\ C. Does this change affect Special Reviews? Yes El No jIf Yes, document Special Review(s) in CHAMPS
/ D. Does this change affect plant operation or Tech Specs? Yes El No If Yes and work is in progress, SS notified by _ (initial)
E. Do controlled copies need to be updated? Yes ]K No E] If Yes, attach marked-up procedure pages to white copy F. All master/working copies updated? Yes JK NA El G. Is training on temporary change needed? Yes E] No If Yes, PINGP 1268 or PINGP 1224 (Ops Only) issued III. REVIEW AND APPROVAL Reviewer: Date:
Approver: Date: Y? 'lt O'0*-
Forward white Forward weCnito coin to~pro edu-l11 IV. POST REVIEWS (re'q.Aed for OC reviewed procedures/critical WO; leave blank if reviewed/approved in II.A)
OC Review Initial/Date: Procedure Approver: Date:
V. TEMPORARY CHANGE DELETION (leave blank if controlled copies not updated, refer to II.E)
A. Reviewer: Date:
(Unit Management Staff)
B. Approver. Date: _ _ '
(Unit Management Staff; SRO for OC reviewed procedures/critical WO)
Wlute Copy - Procedure Control Yellow Copy - Attach to procedure Form 17-5645 (4-02)
TCN LW "F3-2CLASSIFICATION OF EMERGENCIES REV. 29 ATTACHMENT 1 Page 36 of 60 Condition 11 : Fires 7ZTNz f',
6Feihtin ti plant orISFSl, lasting (EAL Ref Manual 11A)
Smiuts' I
FIRE: is combustion characterized by heat and light (flame). Sources of smoke such as slipping drive belts or overheated electrical equipment do not constitute fires. Observation of flame is preferred but is NOT required if large quantities of smoke and heat are observed.
Fire within the Reactor Bldg., Auxiliary Bldg., Turbine Bldg., Service Bldg., Rad Waste Bldg., Plant Screen House, D5/D6 Bldg., Cooling Tower Equip. House, Notification of Unusual Event Transformers, or on the surface of a loaded spent fuel cask in the ISFSI Area Credible notification of fire or fire detection alarm in the Control Room Fire not extinguished within 1 0-minutes I
The 10-minute time period begins with a report of a FIRE occurring or receipt of a fire detection system alarm. A fire alarm is assumed to be valid unless disproven within the 10-minute period by personnel dispatched to the scene.
(EAL Ref Manual 11 B)
I FIRE: is combustion characterized by heat and light (flame). Sources of smoke such as slipping drive belts or overheated electrical equipment do not constitute fires. Observation of flame is preferred but is NOT required iflarge quantities of smoke and heat are observed.
of afire that is observation Physical Physical observation of a fire that is affecting one train of a safety system Alert SS, SM, or ED opinion
1F3-2 CLASSIFICATION OF EMERGENCIES TCN 200;-.- I U.1 ATTACHMENT 1 REV. 29 Page 56 of 60 Condition 19 : Natural Events TeCN p,7e- 3 t,9-ei (EAL Ref Manual 19F)
Notification of River Intake Elevation > 686 ft Unusual Event (EAL Ref Manual 19G)
River Intake Elevation - 692 ft (USAR 2.4.3.5) - requires both units to > SAlert
- be shut down to Mode 2, 3, 4 or 5 I-o d"levels'exceeding-sg ev (EAL Ref Manual 19H)
-.4-p, l' o~nM~e~odSiton IdShudiui Mode 1, 2, 3, or 4 Site Area Emergency I
River Intake Elevation - Power 7698
> ft operation design level (highest level transformers will function)
TCN X( 9 F3-2 CLASSIFICATION OF EMERGENCIES REV. 29 ATTACHMENT 1 Page 59 of 60 Condition 20: Other GondttIons4hAfit .pWrrant incrdased_-.;,i
,stiff"Y,,4tea'o16-1 offsit-e (EAL Ref Manual 20A)
SM and SS concurrence that plant Notification of conditions warrant increased awareness I P
Unusual Event (EAL Ref Manual 20B)
Technical Specification LCO action statement ( .) not met Notification of Unusual Event requires plant shutdown or cooldown Reactor power reduction or cooldown requirements have been exceeded 1 ontIit~d~huitdo
[~i~ma (EAL Ref Manual 20C)
Reactor power reduction or cooldown has Notification of been initiated Unusual Event Emergency Safeguard Function equipment did NOT perform its function if required Cooldown rate exceeded Tech Spec Limit SS or SM opinion that lack of control of shutdown or cooldown warrants offsite agency notification
- "¢PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES NUMBER
THYROID IODINE BLOCKING AGENT F3-18 (POTASSIUM IODIDE) REV: 10 e Proceduresegments may be performed from memory.
- Use the procedure to verify segments are complete.
- Mark off steps within segment before continuing.
'Procedureshould be availableat the work location.
3.C. REVIEW DATE: OWNER:
-7"-- / 2-0-. M. Werner EFFECTIVE DATE Page.1 of 7
./
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES
.NUMBER:
STHYROID IODINE BLOCKING AGENT (POTASSIUM IODIDE)
REV: 10 1.0 PURPOSE This procedure provides instructions for the issuance of thyroid iodine blocking agent (Potassium Iodide Tablets).
2.0 APPLICABILITY This Instruction SHALL apply to all plant personnel involved in the emergency organization at Prairie Island. This procedure does NOT apply to members of the general public offsite.
3.0 PRECAUTIONS 3.1 Thyroid blocking agents are to be used in a radiation emergency only.
3.2 Use only as directed by the Emergency Director.
3.3 Potassium Iodide SHALL NOT be used by anyone who is allergic to iodine.
3.4 Follow the dosage instructions carefully. Potassium Iodide should be taken as soon as possible after authorization by the Emergency Director.
3.5 Do not take more than one dose every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and do not take for more than 10 days unless directed by the Emergency Director.
3.6 In case of an allergic reaction, stop taking Potassium Iodide immediately. Contact your supervisor and a physician immediately.
4.0 PREREQUISITES Dose assessment indicates a possible or actual thyroid exposure of 25 Rem CDE.
Page 2 of 7
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES SNUMBER:
THYROID IODINE BLOCKING AGENT F3-18 S(POTASSIUM IODIDE) REV 10 5.0 RESPONSIBILITIES 5.1- The Radiological Emergency Coordinatbr (REC) has the resp'onsibility to assess and recommend to the Emergency Director when Potassium Iodide should be used.
5.2 The Emergency Director has the responsibility to authorize using Potassium Iodide when recommended by REC.
6.0 PROCEDURE- - ' - ° "'
6.1 During emergency conditions, the Radiation Protection Group should sample areas of the plant where airborne iodine activity may exist.
- Since it is not feasible to conduct emergency operations with all emergencyorgaiiization personnel werinigi respiratory protection, the use of a thyroid blocking agent is 6.2 The Radiological Emergency Coordinator (REC) should recommend, to the Emergency Director, the use of Potassium Iodide WHEN:
6.2.1 Sample results indicate a possible thyroid exposure of 25 Rem CDE, using Figure 2 or Figure 3, OR 6.2.2 A large uncontrolled iodine release is imminent, AND the projected thyroid exposure could approach25 Rem CDE.
6.3 The Emergency Director should authorize the use-6f Potassium Iodide and order its distribution.
'Page 3-6f 7
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEME~nNG PROCEDURES NUuse of Potassium Iodide SHALL be strictly on a voluntary NOTE:4~v~basis.
6.4 The Coordinator at each of the emergency operating centers should complete the distribution of Potassium Iodide as follows:
6.4.1 Distribute supply of Potassium Iodide tablets and information that describes the use of the tablets (See Figure 1), to each individual in the emergency operating center.
6.4.2 List all individuals receiving Potassium Iodide on PINGP 651, Thryo-Block Distribution and forward to the Emergency Director.
6.4.3 Instruct each individual taking Potassium Iodide to read the informational on card. (See Figure 1).
6.4.4 Report any side effects to the Emergency Director so that a medical evaluation may be arranged.
6.5 Each individual should take the prescribed dosage of one tablet every twenty-four hours. This dosage should be taken for a maximum of ten days unless directed otherwise by the Emergency Director.
6.6 Conditions should be continually evaluated by the Radiological Emergency Coordinator to determine when the usage of Potassium Iodide may be terminated.
6.7 WHEN the need for Potassium Iodide no longer exists, THEN all emergency organization personnel issued Potassium Iodide should return all unused tablets to the Emergency Director or his designee.
6.8 Update records to verify that all unused Potassium Iodide tablets have been returned.
' Page 4 of 7
a-ir z
z c!,'
zg
.J jitl .00 D 0'1 05 0*
1 QZ4
.Iz.
I- h111 3
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES Figure 2 Frisker Count Rate vs. Thyroid Dose Rate Based on: - 25 Cubic Foot Air Sample
- Silver Zeolite Frisker Count Rate
Reference:
NSP Internal Correspondence, Wildenborg to Agen, Airborne Radioactive Versus Thyroid Dose, December 10, 1996.
I Page 6 of 7
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES
%,*'t I Figure 3,
- Iodine Concentration Vs. Exposure Time Resulting In 25 Rem CDE 7,
C C,
o0 0.
f.2 o)
IE-8 4 IE-1 1E+O I1E+1 - --, - , IE+2 IE+3 Exposure Time (hours)
Page 7 of 7
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES PERSONNEL AND EQUIPMENT MONITORING AND DECONTAMINATION
- Proceduresegments may be performed from memory.
- Use the procedure to verify segments are complete.
- Mark off steps within segment before continuing.
- Procedureshould be available at the work location.
O.C. REVIEW DATE: I OWNER:
Effective Date 01*to., 0 .2 . M. Werner
- iZ I
i i Page 1 of 7
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCYP LAN IMPLEMENTING PROCEDURES PERSONNEL AND EQUIPMENT I NUMBER:
MONITORING AND DECONTAMINATION 1.0 PURPOSE This procedure provides the guidance for contamination monitoring, contamination control, and decontamination procedures for personnel and equipment.
2.0 APPLICABILITY This instruction SHALL apply to all Emergency Directors (ED) and all members of the Radiation Protection Group (RPG).
3.0 PRECAUTIONS 3.1 All personnel decontamination should be supervised by the RPG.
3.2 The safety of personnel SHALL take precedence over the monitoring of personnel and vehicles for radiation/contamination control purposes. Monitoring of personnel and/or vehicles SHALL be terminated (or not implemented) if such monitoring is known or suspected to be increasing the hazard to personnel during evacuation.
3.3 If any personnel are suspected to have received a biologically significant dose (dose exceeds twice the NRC Annual 10CFR20 Occupational Dose Limits), refer directly to the F3-12, Emergency Exposure Control.
4.0 RESPONSIBILITIES 4.1 The RPG has the responsibility to monitor personnel and equipment to determine if contaminated. When personnel or equipment is found contaminated, the RPG has the responsibility to document contamination levels and to coordinate the decontamination of personnel or equipment.
4.2 The Radiological Emergency Coordinator (REC) has the responsibility to authorize use of elevated contamination levels as listed in Attachment 1 under Emergency Guidelines.
4.3 The ED has the overall responsibility to ensure that radioactive contamination monitoring, control, and decontamination is being conducted throughout the emergency.
Page 2 of 7
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES PERSONNEL AND EQUIPMENT NUMBER:
MONITORING AND F3-19 DECONTAMINATION, REV: 7 5.0 DISCUSSION During emergency' cdlaitiof-ilarge`daea~s o"'levte6d suffce cortamriunation levels are probable within the 15lant bourldleiesi. The-REC'sli'oul*Id evaluate the'contamination levels and determine if it would be beneficial to raise the contamination limits to the elevated guidelines in Attachment 1. The RPG should then control entry into theplant in accordance with these guidelines and monitor personnel and equipment exiting the plant per these guidelines., Decontamination of personnel and equipment to levels below these guidelines should be performed per applicable decontamination.procedures.
6.0 PREREQUISITES The Prairie Island Nuclear.Generating.Plant has:declared an Emergency classification.
7.0 PROCEDURE .. " r7: . . . .
A'.....
7.1 'The RPG is r'esponsible for cbr'mininiatidn rmionitoring, control and decontamination.
7.1.1 All attempts should be made to maintain contamination levels below the normai.guidelines, as per Attachment 1.
7.1.2 During emergency conditions, elevated contamination limits may be authorized by the REC, as per Attachment 1.
7.2 Personnel Monitoring and Decontamination A . * , o1 7.2.1 Monitor personnel who evacuated directly out of the Radiological
.. .. -,Controlled Area first. .... ..- :, .
7.2.2, Survey and document results on PINGP 985, Personnel and Vehicle Survey Log:,..* -.
7.2.3 IF contamination is found, THEN initiate PINGP 915, Whole Body Survey Form.
7.2.4, Segregate monitored personnel into 3 groups using the following criteria.
Highly Contaminated > 5000 CCPM Contaminated > 100 CCPM NOT Contaminated < 100 CCPM Page 3 bf 7
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES PERSONNEL AND EQUIPMENT MONITORING AND DECONTAMINATION 7.2.5 Decontaminate Highly Contaminated personnel L> 5000 CCPM) first, followed by the Contaminated personnel LŽ 100 CCPM).
7.2.6 IF personnel contamination is found around the individual's mouth and nose THEN obtain a nasal smear.
7.2.7 IF the results are > 100 CCPM, THEN indicate Bioassay Required on PINGP 915, (See RPIP 1126, Contamination Monitor Alarm Response and Personnel Decontamination).
7.2.8 Attempt to reduce any contamination detected on an individual in accordance with RPIP 1126.
A. IF dose rates allow personnel habitability, THEN use Decon Showers at Access Control.
B. IF dose rates allow personnel habitability, THEN use old Admin Building shower facilities.
C. Use EOF Decon Shower at Prairie Island Training Center.
7.2.9 IF the Normal Guidelines are NOT achieved, THEN refer to the REC about using the Emergency Guidelines in Attachment 1.
7.2.10 IF contamination is coincident with injury, THEN follow procedures outlined in F4, Medical Support and Casualty Care.
7.2.11 Decontaminate personal clothing and shoes to Normal Guidelines.
7.2.12 IF Normal Guidelines CANNOT be obtained after reasonable efforts, THEN dispose of the items as contaminated waste OR the REC may authorize the use of Emergency Contamination Guidelines as specified in Attachment 1.
Page 4 of 7
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES PERSONNELAND EQUIPMENT NUMBER:
MONITORING AND F3-19 DECONTAMINATION REV: 7 7.3 Coordinated decontamination for Emergency Response personnel remaining onsite, and conducting emergency work activities.
7.4 Vehicles Monitoring and Decontamination -
34cl mnitoring and decontamination should "be perfo'rmed as time allows dep~ending on evacuation urgency.
ftýMAJOR VEHICLE CONTAMINATION MAY POSE A RADIATION HAZARD TO PERSONNEL CONDUCTING SURVEYS AND APPROPRIATE PRECAUTIONS SHOULD BE TAKEN OR SURVEYING SUSPENDED UNTIL LATER.
7.4.1 IF contamination is expected, THEN surveyyehicles prior to departing
-from the Assembly Aea 7.4.2 Survey each vehicle and document on PINGP 985.
A. See Attachment 1 for Guidelines.
B. Survey exterior and interior surfaces for fix contamination, paying special attention to the air filter, tires, and radiators.
C. IF fuel damage is suspected,' THEN smear areas where contamination is found with a cloth smear and save for alpha counting.
D. Smear 6xterior of the Vehicle using'two (2) masslins each covering 5 sq. ft.' from, hood,' roof, t-runk or pick-up bed.
E. IF smears are > 100 CCPM, THEN log'the vehicle as contaminated.
7.4.3 Initiate PINGP 986, Vehicle Survey Form, for vehicles found contaminated (See Error! Reference source not found.).
7.4.4 Tape the PINGP 986 to the inside of the windshield with any saved smears.
Page 5 of 7
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES PERSONNEL AND EQUIPMENT MONITORING AND DECONTAMINATION 7.4.5 Hold Contaminated vehicles in a designated area for later decontamination.
7.4.6 IF major vehicle contamination exists, THEN evacuate personnel as quickly as possible using vehicles that meet the Guidelines of Attachment 1. Outside assistance may be requested as necessary.
7.5 Upon termination of emergency condition, survey the exterior and interior surfaces of the vehicles. Paying special attention to the air filter, tires, radiators, etc.
Contamination levels SHALL be returned to the Normal Guidelines, using approved decontamination procedures as outlined in F2, Radiation Safety, and D-13, Decontamination.
Page 6 of 7
PRAIRIE ISLAND tiU&,LEAR GE=NERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES PERSONNEL AND EQUIPMENT MONITORING AND DECONTAMINATION -
Attachment 1 Contamination Limits S- CONTAMINATION LIMITS NORMAL GUIDELINES EMERGENCY GUIDELINES REMOVABLE, LOOSE -SURFACE DPM/1 00 cm 2 cm 2 By 100 DPM/100 cm 2- 5000 DPM/100cm 2 cc 10 DPM/100 cm2 500 DPM/100 cm2 FIXED 100 CPM 500 CPM Based on Manual of Protective Action Guides and Protective Actions for Nuclear Accidents, EPA 400-R-92-001, May 1992, Table 7-7. Frisker response: 1mR/hr = 5000 CPM Cs 137.
- 1. Guidelines are based on using pancake probe.
- 2. By Portable survey instruments are located in all Emergency Centers and at both Assembly Points.
- 3. aX Portable survey instrument is located in the Hotcell Emergency locker.
Page 7 of 7
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES
- Proceduresegments may be performed from memory.
- Use the procedureto verify segments are complete.
- Mark off steps within segment before continuing.
- Procedureshould be availableat the work location.
EFFECTIVE DATE 1).C. REVIEW DATE:
ý- 73-6z_ 6C I UWNki: M. Werner I 7- 4-dZ-0..
i - II Page 1 of 10
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES 1.0 PURPOSE The purpose of this procedure is to describe the steps necessary to retrieve instantaneous Radiation Monitoring Data from the Emergency Response Computer System (ERCS).
2.0 APPLICABILITY This Instruction SHALL apply to Engineering Support in TSC & EOF and to the Radiological Emergency Coordinator (REC) & Radiation Protection Support Supervisor (RPSS).
3.0 PRECAUTIONS Contact the Prairie Island ERCS Computer Section if problems arise in operation of the ERCS Computer or Printer.
4.0 RESPONSIBILITIES 4.1 Engineering Support has the responsibility to operate ERCS in accordance with this procedure to obtain pre-selected Radiation Monitor Data as requested by REC or RPSS.
4.2 The REC or RPSS has responsibility to request particular Radiation Monitor Data from Engineering Support as necessary.
5.0 PREREQUISITES Plant staff has declared an Alert, or higher, emergency classification and has activated the Emergency Response Organization.
Page 2 of 10
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES 6.0 PROCEDURE 6.1 Accessig RADMON or-StIM-RAD gr6up dispay.
""RADMODN" group display provides a list of current radiation
,NO monitor readings. "STM-RAD" group display provides a list
. o~
of current steam release parameter readings.
6.1.1 At the TOC (Turn On Code);,,enter "GRPDIS RADMON" or "GRPDIS STM-RAD" to gain access to the RADMON group or STM-RAD group parameters, respectively.
6.1.2 The display will respond witha list of selected param6ters and their current values. Also, the prompt."Enter Update Rate in SEC (5-1800):"
'will I*eaf top'of the displý." nte"ideesired~fre quency of parameter reading update (30 sec or more) and dep'ress the <:RETURN> key.
6.1.3 The list of parameters may be printed using the terminal's local color printer. To print, press the <F12> key and wait several seconds.
2 6.1.4 To trend the selected points, depress the <F2>.'TREND" key.
A. Depress the up or down arrow key until the desired parameter points are displayed on the terminal screen.
B. Enter desired update rate (30 sec. or more).
6.1.5 Cancel the Group Display function by depressing' the <Esc> key.
Page'3 of 10i
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES 6.2 Terminating or Resetting the ERCS Steam Release Calculations When entering Point ID's, enter a 1 for Unit 1 or 2 for Unit 2, in place of the
- preceding the Point ID number.
ERCS starts totalizing the radiation released after a reactor trip AND if the control rod bank "B" step count >20 before the trip AND R51152 rad monitors > ERCS main steam NO E: ~ background radiation (Point IDs *R0051B & *R0052B).
"Possiblesteam flow paths are: Safety Relief Valves, PORVs, Steam Dump Valves and Turbine Driven Aux. Feedwater Pump.
6.2.1 The values of Point ID *KSRM may be used to control the radioactive steam release calculations as follows:
A. *KSRM set to 0 = Normal program operation (computation is enabled).
B. *KSRM set to 1 = Computation is inhibited, but accumulated release values are not altered.
C. *KSRM set to 2 = Computation is inhibited and accumulated release values are set to zero.
6.2.2 If steam release calculations need to be disabled or enabled, request an ERCS Engineer perform the change to *KSRM using TOC "SUB" to substitute the appropriate value (0, 1 or 2).
6.2.3 Alternately, you can use the turn-on-code "STM-RAD" to monitor the steam release computation and to inhibit, enable, and reset the calculations. This function is available from any ERCS terminal and can be performed by anyone. The function keys (F1 and F2) are used to allow the operator to inhibit, enable and reset.
7.0 LIST OF TABLES AND ATTACHMENTS 7.1 Table 1 - Unit 1 Rad Monitors 7.2 Table 2 - Unit 2 Rad Monitors 7.3 Table 3 - Unit 1 Steam Release Rad Parameters 7.4 Table 4 - Unit 2 Steam Release Rad Parameters Page 4 of 10
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES "Table1"' Unit1 Rad Monitors
-UNITI RADIATION MONITORS POINT ID DESCRIPTION 1ROO01A -'- ""CONTROL ROOM AREA R I
'°'" * " * "" e: 1* CNTM~ VSL AREA R 1 ROO02A
" -'.: ':,11/12/13"CHARG PMP AREA R 1ROO04A 1ROO07A "IN-CORE SEAL TABLE AREA R 1ROO09A - .RCLETDN LINE R UNIT 1 1RO011A * ., v'-l CNTM/SHLD BLDG VENT AIR PART 1 ROO12A 1 CNTM/SHLD BLDG 4EN'T GAS R 1R0015A ."CDSRAIR EJCTR GAS RADIOACTIVITY 1 R0019A STM GEN BDLIQUID RADIOACTIVITY 1 R0021A *CIRC WTR DISCH R "SHIELD -G VENT GAS R 1 R0022A 2.SHIELD BLDG VENT GASR 2R0022A 1 R0025A SPENT FUEL POOL AIR R-MONITOR 1R0026A "". * " "11/21 RHR CUBICLE AIR R 1 R0027A 12/22 RH CUBICLE AIR R 1 R0030A AUX BLDG VENT GAS R MONITOR B 1Roo31A "SPINT FUEL POOL AIR'R MONITOR B 1 R0037A "UNIT1 AUX BLDG VENT GAS R 1R0039A I*NIT 1'COMP COOLING LIQUID R 1R0048A 1 HIGH RANGE CNTM AREA MONITOR B 1R0049A 1 HIGH RANGE CNTM AREA MONITOR A 1 R0050A SHIELD BLDG STACK RAD HIGH RNG
.5J.
1 R0051A A STM LINE RAD LVL 1R0051U1 STEAM RAD RELEASE RATE 33 1 R0052A B STM LINE'AD LVL 1 R0053A -"SI PUMP AREA RAD LVL Page'5 of 10
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES Table 1 Unit 1 Rad Monitors UNIT 1 RADIATION MONITORS 1R0054A CS PUMP AREA RAD LVL 1R0055A AUX BLDG 695 EAST AREA RAD LVL 1R0056A AUX BLDG 695 WEST AREA RAD LVL 1R0057A AUX BLDG 715 EAST AREA RAD LVL 1R0058A AUX BLDG 715 WEST REA RAD LVL 1R0059A AUX BLDG 715 PENET/LTDN AREA RAD 1R0060A AUX BLDG 735 NORTH AREA RAD LVL 1R0061A A STM LINE AREA RAD LVL 1R0062A AUX BLDG 755 EAST AREA RAD LVL 1R0063A AUX BLDG 755 WEST AREA RAD LVL 1R0064A TURB BLDG 735 NORTH AREA RAD LVL 1R0065A OPER SUPPORT CENTER RAD LVL 1R0066A D1 DSL GEN ROOM RAD LVL 2R0067A INSTR AND CONT SHOP RAD LVL 2R0068A TECH SUPPORT CENTER RAD LVL 2R0069A GUARDHOUSE RAD LVL 1R0070A RCS HOT LEG LOOP A AREA RAD LVL 1R0071A RCS HOT LEG LOOP A AREA RAD LVL Page 6 of 10
PRAIRIE ISLAND Nt13CLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES Table 2 i Unit 2 Rad.Monitors UNIT 2 RADIATION MONITORS POINT ID 1h 'ZI x DESCRIPTION 2R0002A 2 CNTM VSL AREA R 2R0007A "IN-CORESEAL TABLE AREA R 2R0011A ".' 2 CNTM/SHLD BLDG VENT AIR PART 2R0012A 2 CNTM/SHLD BLDG VENT GAS R 2R0015A CDSR AIR EJCTR GAS RADIOACTIVITY 2R0019A STM GEN BD LIQUID RADIOACTIVITY 1R0022A I'JSHIELD BLDG VENT GAS R 2R0022A -2 SHIELD BLDG VENT GAS R 1 R0025A SPENT FUEL POOL AIR R-MONITOR 16 SPENT FUEL POOL AIR R-MONITOR B 1R0031A
'" :2 HIGH RANGE CNTM AREA MONITOR A 2R0048A 2R0049A S,2 HIGH RANGE CNTM AREA MONITOR B 2R0050A SHIELD BLDG STACK RAD HIGH RNG 2R0051 A A STM LINE RAD LVL 2R0051U1 .,'STEAM RELEASE RATE 2R0052A B STM LINE RAD LVL 2R0053A SI PUMP AREA RAD LVL 2R0054A CS PUMP AREA RAD LVL 2R0055A AUX BLDG 695 WEST AREA RAD LVL 2R0056A AUX BLDG 695 EAST AREA RAD LVL 2R0057A AUX BLDG 715 WEST AREA RAD LVL 2R0058A AUX BLDG 715 EAST AREA RAD LVL 2R0059A AUX BLDG 715 PENELTDN AREA RAD 2R0060A AUX BLDG 735 NORTH AREA RAD LVL 2R0061A A STM LINE AREA RAD LVL 2R0062A AUX BLDG 755 WEST AREA RAD LVL 2R0063A AUX BLDG 755 EAST AREA RAD LVL 2R0064A TURB BLDG 735 NORTH AREA RAD LVL 1 R0065A OSC RAD LEVEL 1 R0066A D1 DSL GEN ROOM RAD LVL 2R0067A INSTR AND CONT SHOP RAD LVL 2R0068A TECH SUPPORT CENTER RAD LVL 2R0069A GUARDHOUSE RAD LVL 2R0070A RCS HOT LEG LOOP A AREA RAD LVL 2R0071A RCS HOT LEG LOOP B AREA RAD LVL 2R0072A D6 CABLE SPREADING RM RAD LVL Page 7 of 10
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTIVG PROCEDURES Table 2 Unit 2 Rad Monitors UNIT 2 RADIATION MONITORS POINT ID DESCRIPTION 2R0073A D6 BUS 26 SWGR RM RAD LVL 2R0074A D6 BU 221& 222 SWGR RM RAD LVL 1ROO01A CONTROL ROOM AREA R 2R0009A RC LETDN LINE R-UNIT 2 1R0026A 11/21 RHR CUBICLE AIR R 1R0027A 12/22 RHR CUBICLE AIR R 2R0030A 2 AUX BLDG VENT GAS R-MONITOR B 2R0037A UNIT 2 AUX BLDG VENT GAS R 2R0039A UNIT 2 COMP COOLING LIQUID R Page 8 of 10
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES Table 3 'Unit 1 Steam Release Rad Parameters POINT ID "DESCRIPTION 1R0051A STEAMWLINE RAD MONITOR A 1 R0052A STEA* LINE RAD MONITOR B 1 R0051B STEAM LINE RAfD MONITOR A - BACKGROUND 1 R0052B STEAM LINE RAD'MONITOR B - BACKGROUND 1 R0051 U RELEASE Curie -,
1R0051U1 STM RAI) RELEA8E RATE ,C/SEC 1Y1501D SAFETY'VALVE 1,TRAIN A 1Y1502D 'SAFETY VALVE 2 TRAIN A 1Y1503D SAFETY.VALVE 3 TRAIN A 1Y1504D SAFETY VALVE 4 TRAIN A 1Y1505D SAFETY VALVE 5 TRAIN A 1Y1521D SAFETY VALVE 1 TRAIN B 1Y1522D SAFETY VALVE 2 TRAIN B 1Y1523D SAFETY VALVE 3 TRAIN B K, 1Y1524D SAFETY VALVE 4 TRAIN B 1Y1525D SAFETY VALVE 5 TRAIN B 1Y1533D CROSS OVER VALVE A (1 = OPEN) 1Y1534D CROSS OVER VALVE B (1 = OPEN) 1Y1535D AUX FEEDWATER PUMP VALVE (1 = OPEN) 1Y2168D MSIV TRAIN A (1 = CLOSED) 1Y2936D MSIV TRAIN B (1 = CLOSED) 1U5036A STEAM LINE A PRESSURE - PSIA 1U5038A STEAM LINE B PRESSURE - PSIA 1Y1530A STEAM DUMP VALVE A-1 1Y1531A STEAM DUMP VALVE A-2 1Y1532A STEAM DUMP VALVE B-1 1Y1533A STEAM DUMP VALVE B-2 1Y1536A PORV A POSITION 1Y1538A PORV B POSITION 1 L0409A SG WR LEVEL LOOP A 1 L0429A SG WR LEVEL LOOP B 1Y1500A POST TRIP STM RELEASE 1U5202D REACTOR TRIP (1 =YES) 1UO050A ROD BANK B STEPS 1KSRM STM RELEASE RAD ENABLE (O=ENABLE) 2R0051U STM RAD RELEASE 2R0051U1 STM RAD RELEASE RATE Page'9 Of 10
PRAIRIE ISLAND NUCLEAR GENERATING PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURES Table 4 Unit 2 Steam Release Rad Parameters POINT ID DESCRIPTION 2R0051A STEAM LINE RAD MONITOR A 2R0052A STEAM LINE RAD MONITOR B 2RO051B STEAM LINE RAD MONITOR A - BACKGROUND 2R0052B STEAM LINE RAD MONITOR B - BACKGROUND 2RO051U RELEASE Curie 2R0051U1 RELEASE RATE iC/SEC 2Y1501 D SAFETY VALVE 1 TRAIN A 2Y1502D SAFETY VALVE 2 TRAIN A 2Y1503D SAFETY VALVE 3 TRAIN A 2Y1504D SAFETY VALVE 4 TRAIN A 2Y1505D SAFETY VALVE 5 TRAIN A 2Y1521D SAFETY VALVE 1 TRAIN B 2Y1522D SAFETY VALVE 2 TRAIN B 2Y1523D SAFETY VALVE 3 TRAIN B 2Y1524D SAFETY VALVE 4 TRAIN B 2Y1525D SAFETY VALVE 5 TRAIN B 2Y1533D CROSS OVER VALVE A (1 = OPEN) 2Y1534D CROSS OVER VALVE B (1 = OPEN) 2Y1535D AUX FEEDWATER PUMP VALVE (1 = OPEN) 2Y2168D MSIV TRAIN A (1 = CLOSED) 2Y2936D MSIV TRAIN B (1 = CLOSED) 2U5036A STEAM LINE A PRESSURE - PSIA 2U5038A STEAM LINE B PRESSURE - PSIA 2Y1530A STEAM DUMP VALVE A-1 2Y1531A STEAM DUMP VALVE A-2 2Y1532A STEAM DUMP VALVE B-1 2Y1533A STEAM DUMP VALVE B-2 2Y1536A PORV A POSITION 2YI538A PORV B POSITION 2L0409A SG WR LEVEL LOOP A 2Y1500A POST TRIP STM RELEASE 2L0429A SG WR LEVEL LOOP B 2U5202D REACTOR TRIP (1 = YES) 2U0050A ROD BANK B STEPS 2KSRM STM RELEASE ENABLE (0=ENABLE) I Page 10 of 10