Text

Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 5 to EPIP-03 Re Notification of Unusual Event Implementing Actions & Rev 5 to EPIP-14A Re Release Rate Determination
	ML20127E139
Person / Time
Site:	Palo Verde
Issue date:	01/04/1985
From:	; ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	;
Shared Package
ML17298C132	List: ML20127E139;
References
	PROC-850104, NUDOCS 8505170485
	Download: ML20127E139 (110)
	v • d • e

{{#Wiki_filter:... EMERGENCY PLAN IMPLEMENTING PROCEDURE TRANSMITTAL s LIST I EPIP NO. INDEX/01/04/85 (#38 Rev. 4) DATE 01/04/85 ~- b A C V. Elish 6-8 Unit 1 Control Room 5-2B G. Fiorelli 8-1 Kris Oberdorf 5-6 l R. Selman 5-37 G. Olson 3-2 l M. A. Cates 5-103 Unit 1 Radwaste 5-43 l Compliance 5-17 OSC Coordinator 3-15 Leon Brown 5-33 A. Porter 3-3 i J. G. Sarver 5-102 T. Warren 5-21 V. Rhodes 1-1 l John Schlar 5-15 D l T. Exum 5-40 B. Rocers/TSC 5-94 DDC Library 1-2 John Cole 3-10 4 M. W. Lantz 5-35 TSC 3-5 l Penny Egebrecht 5-91 Les Barlow 3-8 l Harry Bieling 17-9 Steve Grove 3-4 I E. J. Hayes 5-34 Greg Roettger 5-99 J. Cederquist 5-20 Maintenance Manager 3-11 T. Shriver 5-8 TSC E Plan Anal 3-5A T. Barsuk 5-86 John Kirby 2-4 D. Best 5-88 Unit 2 Control Room 5-25 l R. Johnson 5-42 Sec Cpt 15-1 E E. Cullen 5-41 D. Fasnacht 19-1 EOF 17-1A M. Zimmerman 20-1 EOF 17-1B 'W. J. Stubblefield 14-47, i ) f EOF 17-lC F EOF 17-ID WRF/DDC 1-7 EOF (Room 12) 17-lE EOF 17-lF G I f Unit 2 Rad Protection 5-95 Bob Adney/ Unit 11 5-39 Jack Sims 17-2 l Mike Crusa 17-4 FOR NRC Bob Page 17-5 TAKE TO KARL GROSS ON R/A Jerry Self 5-79 Jack Martin /Adm. 8-8 l Marv Gerdes 13-12 Dennis Yows 5-36 Document Cont. Desk 8-9B Bill Knighton 15-2 Ray Fish /Gail Temple 8-5 l Russ Papworth 5-7 Perry Robinson 8-6 j Bruce Rash 13-18 [ Dan Phillips 13216 { B PROCEDURE GROUP J. M. Allen 5-31 Dennis Yows 5-36A thru 5-361 W. Fernow 5-14 Emergency Kits coordinate w/ J. Sims C. Anderson 6-7 Sim Obs Rm 5-89 C._R.,Dunaway 5-9 l D. Nelson 5-18 M. Whitaker 5-38 J. Tench 5-19 ) A. Perouthka 6-6 J. R. Evnum 5-22 B. Simmons 6-10 F. Ilicks 6-9 010 8505170485 850124 i PDR ADOCK 05000528 F PDR (

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EPIP-02 EMERGENCY CLASSIFICATION 02 840924 !. )' l I '850123 t I i I i lt ;y EPIP-03 NOTIFICATION OF UNUSUAL EVENT ' ' i '850924 Z L 841218 i t01 l 05, 1 i Y '851218 I IMPLEMENTING ACTION $ . i I} EPIP-04 ALERT' IMPLEMENTING ACTIONS { l 04 ; t j

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l ! { } i 1 t .} ) I EPIP-09 EMERGENCI COORDINATQR* 01 i 840716' T'i 1 v% TECNNICALSUPPORTCqNTER/SATELLfTE j l 0' 2 ;'!3 l840713, } fl8507" EPIP-11 850796 ,2 l,- tl t 3 iZ TSC ACTIVATION EPIP-12 OPERATIONS SUPPORT CENTER 02 840716 Y 850716 2 OEPIP-13 ACTIVATION EMERGENCY OPERATIONS FACILITY 02 840716 Y 85071$ Z 7"5 y P ACTIVATION

1 pummEPIP-144 RELEASE RATE DETERMINATION 05 850101 Y

860101 Z f y EPIP-145 INITIAL DOSE ASSESSMENT 02 8409201 Y 850920 Z i EPIP-14C CONTINUING DOSC ASSES $MENY 00 840925 Y 850925 Z f PIP-14D DOSE ASSESSMENT SUMMATION-00 840924 Y 850924 2 y EPIP-15 PROTECTIVE ACTION GUIDELINES 02 840713 Y 850713 Z EPIP-16 INPLANT SURVETS AND SAMPLING 02 540726 Y 850726 2 EPIP-17 ONSITE/0FFSITE SURVEYS AND SAMPLING 02 840801 Y 850801 Z EPIP-18 ' EMERGENCY EXPOSURE GUIDELINES 02 840550 Y 850530 Z yOEPIP-19 ONSITE EVACUATION 02 840629 Y 850629 2 EPIP-20 PERSONNEL ASSEMBLY AND 02 840716 Y 850716 2 y ACCOUNTABILITY EPIP-21 SEARCN AND RESCUE 02 840716 Y 850716 2 EPIP-22 PERSONNEL INJURY 02-840530 Y 850530 Z y EPIP-23 FIRE FIGHTING 02 840530 Y 850530 Z EPIP-24 SECURITY 02 840716 Y 850716 ,Z EPIP-25 REENTRY FOR EMERGENCY OPERATIONS 02 840716 Y 850716 Z v EPIP-26 POTASSIUM IODINE (KIl 02 840716 Y 850716 Z ADMINISTRATION g EPIP-27 f POST ACCIDENT SAMPLING AND ANALYSIS 03 'p 841217 Y 851217 2

y EPIP-28 PERSONNEL MONITORING AND 02 840716 q

DECONTAMINATION i Y 850716 Z maq j EPIP-29 AREA / EQUIPMENT MONITORING AND 02 840716 .Y' ly i DECONTAMINATION 850716 Z f ' 'i i j l',!' l \\ EPIP-30I RADIOLOGICAL' EMERGENCY RESPONSE,! 06 ', ' 840716 i ji J i e 1 t l 8 l I \\ +850[16 Z T i VENICLE.0PERATIONS l i i y EPIP-31 REC 0VERY l ' j [,; 0FFSITE i 0 j 840530 l l. lY l 85053 Z J EPIP-33 l i i l l I N l fSSISTARCE d id l ! Xdsi'G EDidOPY i '0 i d40716 Y , 850714 Z Iifi! l{ j 'i ,i<

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hf EPIP-36 EMERGENCY PREPAREDNESS TRAINING 01 830325 Y 840325 Z EPIP-3FA EMERGENCY PREPAREDNESS DRILLS 01 830325 Y 840325 Z ( EPIP-378 EMERGENCY PREPAREDNESS EXERCISES 01 830325 Y 840325 Z EPIP-38 EMERGENCY EQUIPMENT AND SUPPLY 04 ~~ 850104 Y 860104 Z i LZ EPIP-39 INVENTORY (, EMERGENCY OPERATIONS DIRECTOR (EOD) 02 840716 Y 850716 Z q EPIP-4D ADMINISTRATIVE AND LOGISTICS 02 840530 Y 850530 t COORDINATOR (ALC) y EPIP-41 RADIOLCGICAL ASSESSMENT 02 840530 y 850530 Z COORDINATOR (RAC) LOEPIP-42 TECHNICAL ANALYSIS COORDINATOR 02 840530 Y 850530 Z (TAC) F EPIP-43 R(DI0 LOGICAL ASSESSMENT M 02 840530 Y 850530 t guma ymmm COMMUNICATOR (RACOM) EPIP-44 E EPIP-45 TSC LIAISON ENGINEER (TLE) - 0Z 840731 Y 850731 Z r b GOVERNMENT LIAISON ENGINEER (GLE) 02 840530 Y 850530 2 { EPIP-46 EOF CONTACT 02 840530 y 850530 Z L EPIP-47 LOGISTICS COMMUNICATOR p 02 840530 Y 850530 1 1 EPIP-48 SECURITY COORDINATOR 02 840530 v 850530 Z EPIP-49 DOSIMETRY CLERK 02 840530 Y 850530 Z L EPIP-50 STATUS BOARD KEEPER (SBK) 02 840530 y 850530 Z OEPIP-51 0FFSITE TECHNICAL REPRESENTATIVE 02 840530 .Y 850530 2 (OTR) L EPIP-52 JENC TECHNICAL ADVISOR 02 840530 Y 850530 Z l EPIP-53 GOVERNMENT STAFFING AT TSC 02 840530 Y 850530 I { EPIP-54 GOVERNMENT STAFFING AT EOF 02 840530

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m. [ A C V. Elish 6-8 Unit 1 Control Room 5-2B G. Fiorelli 8-1 Kris Oberdorf 6 R. Selman 5-37 C. Olson 3-2 M. A. Cates 5-103 Unit 1 Radwaste 5-43 Compliance 5-17 OSC Coordinator 3-15 Leon Brown 5-33 A. Porter 3-3 J. G. Sarver 5-102 T. Warren 5-21 ,V. Rhodes 1-1 John Seb ime 5-15 D T. Exum 5-40 B. Rogers /TSC 5-94 l DDC Library 1-2 John Cole 3-10 M. W. Lantz 5-35 TSC 3-5 Penny Egebrecht 5-91 Les Barlow 3-8 Harry Bieling 17-9 Steve Grove 3-4 i E. J. Hayes 5-34 Greg Roettger 5-99 J. Cederquist 5-20 Maintenance Manager 3-11 T. Shriver 5-8 TSC E Plan Anal 3-5A T. Barsuk 5-86 John Kirby 2-4 D. Best 5-88 Unit 2 Control Room 5-25 R. Johnson 5-42 -See Cpt 15-1 E E. Cullen 5-41 D. Fasnacht 19-1 EOF 17-1A M. Zimmerman 20-1 EOF 17-1B 'W. J. Stubblefield 14-47, f EOF 17-lC F EOF 17-lD WRF/DDC 1-7 . EOF.(Room 12) 17-lE EOF 17-lF G Unit 2 Rad Protection 5-95 Bob Adney/ Unit II 5-39 Jack Sims 17-2 Mike Crusa 17-4 FOR NRC Bob Page 17-5 TAKE TO KARL GROSS ON R/A { Jerry Self 5-79 Jack M retn/Adm. 8-8 Marv Gerdes 13-l' I I

Dennis Yows 5-36 ocument one.

~ Bill Knighton 15-2 Ray Fish 8-5 j Russ Papworth 5-7 Perry Rcbinson 8-6 l ( Bruce Rash 13-18 Dan-Phillips 13-16 i B PROCEDURE GROUP l J. M. Allen 5-31 Dennis Yows 5-36A thru 5-361 [ W. Fernow 5-14 Emergency Kits coordinate w/ J. Sims j ~ 'C. Anderson 6-7 Sim Obs Rm 5-89 [ C.,R. Dunaway 5-9 D. Nelson 5-18 i M. Whitaker 5-38 I O)k b:S N,* -~,. ) ' 0 Ob SM' ' 'M ; J. Tench 5-19 { A. Perouthka 6-6 J. R. Bvnum 5-22 B. Simmnns 6-10 ~ l. F. Hicks 6-9 i 010 3 __m_______

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2.0 REFERENCES

[ 2.1 Implementing References 1

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2.1.1 EPIP-02, " Emergency Classification" ~~ 2.1.2 EPIP-11, " Technical Support Center / Satellite TSC Activa [io2' 1; 2.1.3 EPIP-12, " Operations Support Center Activation" 2.1.4 71AC-9ZZ01, " Event Related Reporting" ~~ ' h ks [ N2.'c 2.2 Developmental References Oe L 2.2.1 NUREG-0654, Rev. 1, " Criteria for Preparation and Evaluation [ of Radiological Emergency Response Plans and Preparedness in i Support of Nuclear Power Plants".

<: a 2.2.2 PVNGS Emergency Plan, Rev. 5

-O 2.2.3 ANSI N45.2.9-1974, " Requirements for Collection, Storagi,' and '#" " 9 ~ Maintenance of Quality Assurance Records for Nuclear Power. Plants". ~ ~ - - T - ~... ....-\\: 3.0 LIMITATIONS AND PRECAUTIONS i 3.1 Continued surveillance and assessment of plant conditions _are necessary to ensure that the emergency classification is ~ appropriately revised as conditions change or more definitive 7 _3: information is obtained. .: r. --:-. f I -y l l CONTROLLED DOCUMENT ~ ~ ~ l ~- - l e

.J.' ~ ~. ~ ' ~ ~ ~ ~ ~ t, !.~ CONTROLLED DOCUMENT I L ~ =I PVNGS EMERGENCY PLAN pesouns x; 3 ((~ IMPLEMENTING PROCEDURE EPIP-03 7 E E.' 7 y NOTIFICATION OF UN UAL ._ Y REVISION y EVENT IMPLEMEhTING ACTIONS 5 Page 5 of 26 ~~ ~ /-3 E E E 4.0 DETAILED PROCEDURE _T:7Tf 4.1._ Personnel Indoctrination / Responsibilities l j -a r. ... 3c .p .~.. available to take precautionary and constructive steps to prevent a more serious event and/or to mitigate any c= .c consequences that may occur. This event status places the [ plant in a readiness position for possible cessation of 2 : e.[ n routine activities and/or augmentation of onshift resources. l No releases of radioactive material requiring offsite

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' ' ' ~ ' ' ' ' ~ response are expected. Appropriate notification of NRC and f.. ..-st. ate / county authorities is made. ~ ~. E p ~~~~ The Shift Supervisor shall be responsible for initiating this

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.._ 4.1.2 ~ ~ procedure. The Emergency Coordinator shall be responsible E for completing the implementing actions of this procedure. iI 4.2 Prerequisites [r 4.2.1 The emergency has been classified per EPIP-02, " Emergency f . Classification." e, 4.3 Instructions i h 4.3.1 The affected unit Shift Supervisor shall perform the _( .. m _ following: NOTE th ~ Designated Unaffected Unit Shift Supervisor J to assume the role of the Emergency j __ Coordinator in the Onshift Emergency Organization are: 4 37 n . ~ ~- ~ Affected Unit Unaffected Unit Shift Supervisor ? ~ ~ ~ ~ Unit 1 Unit 2 7' J Unit 2 Unit 1 0 Unit 3 Unit 2 Entire Sito Unit 1 e 4.3.1.1 Notify the Shift Supervisor of the designated unaffected unit (or Shift Supervisor of an unaffected unit) to e J report to the C'ontrol Room of the affected unit and 6-assume the duties of the onshift Emergency Coordinator. For notification of unusual events, it will be at the I discretion of the affected unit Shift Supervisor if he } }- is to be relieved as Emergency Coordinator by the shift t CONTROtIED"DOCOMENT .... e s_. ,,. m.m

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__ _.. ~ ~ " - ~ EVENT HAS BEEN DECLARED. SATELLITE TECHNICAL SUPPORT CENTER AND OPERATIONS SUPPORT CENTER EMERGENCY PERSONNEL ~ ..__1.._.~_..~.._ ' ' _ I.E...~. '._.. '.,' ~ '..(.. __ OTER PERSONNEL ASSIGNED TO THE EERGENCY ORGANIZATION - .f __ FOR UNIT , REPORT 'ID YOUR EERGENCY STATION. . j . ' T. J :. . STANDBY. ALL OTER PERSONNEL CONTINUE WITH NORMAL ..-- --[ $ E..]'". " ROUTINE UNTIL FURTER NOTICE". . )S

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(Give a brief description of the event, if appropriate, _and repeat the announcement). ,.d ( . : _m. F. Protective Action recommendations ~ (Appendix F) are based on plant and l ~ ~ ~ - - - containment conditions and these .. g recommendations are made to offsite officials even when no release is in progress. .2..2 r 4.3.1.3 Direct the Satellite TSC Communicator to fill out Appendix C, " Initial Emergency Message Form", in I accordance with instructions provided in Appendix E.

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- : : : -- (/3'.1. 4 Notify the Control Rooms of the unaffected units. ~ 4.3.1.5 Ensure the actions of the appropriate Recovery procedures have been implemented. a 3 f.3.2 The Emergency Coordinator / Shift Supervisor shall perform the [' following: 4.3.2.1 Ens'ure actuation of the Satellite TSC in accordance with EPIP-11. " Technical Support Center / Satellite TSC } Activation". c 4.3.2.2 ImplementadditionakEmergencyPlanImplementing 3 Procedures according to the situation that resulted in the emergency being classified as a NOTIFICATION OF ....._ UNUSUAL EVENT. Procedures that shall be implemented and n -~~. ~~ ' others which may be appropriate are Idemt t rind in l ~ ' -~ Appendix H. I i ~ 4.3'.2.3 ~ ' Determine the need for any additiona.1 personnel. If ~,, needed, additional personnel should be requested by the 4, --existing on-shift organization. CONTROLLED DOCUMENT '= """" .-..a.

i l CONTROLLED DOCUMENT PVNGS EMERGENCY PLAN Q.caouRE -3'== -mz m ,n .:=w y ?. IMPLEMENTING PROCEDURE EPIP-03 ~ " ^ REVISION NOTIFICATION OF UNUSUAL .7 EVENT. IMPLEMENTING ACTIONS S Page 7 of 20 l - <4.3.2.A:: Direct the STSC Communicator to prepare Appendix D, " Follow-up Emergency Message Form" in accordance with instructions provided in Appendix E. {- _ - 3.- $ _; :.34.3.2i5 TR_eevaluate the emergency classification and perform ~ . - 7. ; _ - licensee actions as conditions change by implementing M: '- ' :- r.:'; .2 2 EPIP-02. 4.3 3.6 When the situation warrants downgrading / upgrading a NOTIFICATION OF UNUSUAL EVENT, proceed to appropriate implementing and notification procedures and direct the J, ~~ _ -. _ _...~~~~~~ Shift Supervisor to announce the reclassification over the public address system and inform the other Control Rooms. t .m 4.3.2.7 The Emergency Coordinator shall complete checklist, Appendix G. 4.3.3 PVNGS Security, after being notified by the Emergency Coordinator or STSC Communicator that a NOTIFICATION OF [ UNUSUAL EVENT is in progress or has occurred, shall complete [ Appendix B, " Emergency Notification Call List - PVNGS Security", and notify these individuals or departments of the situation. ,. ;3 4. 4 Emersency Situation Terminated ~ '4.3.4.1 The Shift Supervisor (or Emergency Coordinator) shall -_-._ sound the "All Clear" signal for approximately (1) . minute, silence the signal, and provide the following announcement over the plant wide telephone paging system: ~ ~' ~ " Attention all personnel, the emergency situation declared in Unit has now been terminated." (Provide special instructions as necessary). 4.3.4.2 Repeat signal and announcement once. n 4.3.4.3 Within 24 hours of closeout from the NOTIFICATION OF .,_ ~ . UNUSUAL EVENT classification provide a written summary to - ' offsite authorities, in accordance with 71AC-92Z01, " Event Related Reporting". ~ 4.3.5 Record Retention 4,3.5.1 Appendices A, B, C, D and G ihall be retained for the . life of the plant. CONTROLLED DOCUMENT ~ ~~ - - ~

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..,_ S.-, ~ Fill in data required by steps 1 and 2 of Appendix C, k' Initial l 1.1 hae==ne y Message Form". Obtain authenticator from the confidential envelope marked on the outside with the appropriate - th and. drill sequence number (if it is a drill). I L? riht a 4 n fer= the Radiation Protection Monitor (onshift) data g. required to complete step 3 of Appendix C. 1.3 Circle appropriate wording of step 4 of Appehdix C. NOTE When the NAN ring button is pushed and it appears that all the receiving stations are on 3 line, or, the ring has stopped, the PVNGS 3.(.,dh ' 4 originating station shall initiate a roll call ~ in the order listed below. (Consider the time j' of day.) 1.4 By means of a single call on the Notification and Alert Net i. ..____.-__ _.. dadir atart telephone, contact the following State / County agencies: 1 _.DutyJIours (8:00 a.m. to 5:00 p.m. Monday-Friday) ~ i. ~ Maricopa County Sheriffs Office Maricopa County Department of Civil Defense and Emergency Services. Arizona Department of Public Safety ~ - ' - _. ~ Arizona Division of Emergency Services . ~_ Arizona Radiation Regulatory Agency l ~ ' - Off-Duty Hours (5:00 p.m. to 8:00 a.m., Monday-Friday, all day Y Saturday and Sunday and Holidays) - ~ - Maricopa County Sheriff's Office ___.._ __ _...._. Department of Public Safety g i ---.LS._ _When_ contact is made, the caller shall identify himself and i request that the individuals obtain a copy of the Appropriate . l~ ~ Emergency Message Form. j,,fL 1.6 When each individual has obtained a copy, rr,1 the completed Emergency Massage Form verbatim and reques.v HCSO to read back verbatim. 1.7 Offer to repeat information and reiterate as necessary. ~~^~ CONTROLLED DOCUMENT 1 t

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12. Within 24 hours of closecut from the NOTIFICATION OF

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2.0 REFERENCES

-..4 - - -.. - p LIMITATIONS AND PRECAUTIONS --4------- L' 4.0 DETAILED PROCEDURE 5 -- - - - 4.1 Personnel Indoctrination / Responsibilities -5 - 4. 2 ---Prerequisites-5 4.3 Instructions 6 y APPEhTICES - Appendix A -Release Rate Determination From an Effluent 11 Release Point Appendix B - Effective Age Correction Factors For the 13 - Effluent Monitors a Appendix--C - -Noble-Gas-and Iodine Radiological Data 14. -Appendix--D - Release-Rate Determination from Main Steam System a 15 Appendix-E -Release-Rate Determination from an Isolated Containment Using Design Basis Leak Rates a and Area-Monitors or External Containment Radistion Monitor Appendix F - Correlation of In-Containment and 25 __..._.-Out-of-Containment Radiation Monitors 3. t e ~~""' CONTROLLED DOCUMENT mr

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2.0 REFERENCES

>Y ~ 2.1 Implementing References 2.1.1 EPIP-14B, " Initial Dose Assessment" 2.1.2 78AC-0ZZ06, " Document and Record Turnover Control" ~~ ~ 2.1.3 74CH-9ZZ47, " Core Damage Assessment" ] 1 2.2 Developmental References { 2.2.1 PVNGS Emergency Plan, Rev. 5 2.2.2 FSAR, Chapter 11. " Process and Effluent Radiological Monitoring and Sampling Systems", Section 11.5, Augu_st 1981. I 2.2.3 NUREG-0737, " Clarification of TMI Action Plan Requirements", October 1980. 2.2.4 EPA-520/1-75-001, " Manual of Protective Action Guides and Protective Actions for Nuclear Incidents," Rev. 6/80. 2.2.5 'CE System 80 CESSAR, Standard PWR NSSS 2.2.6 Steam Tables; Table 1, ASME, 1967 2.2.7 ANPP: Radiation Design Guide, SYS 80-PE-RG, Rev. 2 2.2.8 " Reactor Shielding Design Manual," T. Rockwell, III, editor. D. Van Nostand, Princeton NJ 2.2.9 " Radiological Health Handbook," US DNEW, 1970, National Technical Information Service 3 M 3.0 LIMITATIONS AND PRECAUTIONS 3.1 The accuracy of plant vent monitors is 125% and the accuracy of containment area monitors is 120%. Therefore, release rate calculations may be limited to two significant figures. ~ ~ ~ " CONTROLLED DOCUMENT 4 i

7- ",.,.. J : -- CONTROLLED DOCUMENT . T 3 F .. PVl4GS EMERGENCY PLAN PROCEDURE A l'MPLEMENTING PROCEDURE ..-i No. EPIP-14A ~ ~ REVISION 4.0 DETAILED PROCEDURE 1 4.1__fersonnel Indoctrination / Responsibilities ~ -z ' i.[1.1' ' MoniEo'r readings and monitor channel number should be ~ ~ ~f obtained from the communication console in the Control Room 4 [ or the console in the Radiation Protection office. 7 4.1.2 " Effective age" refers.to the time between core shutdown and { time of the release. Release rates will vary as a function l; of " effective age". 4.1.3" When selecting values from the appendices, data corresponding to 1*. failed fuel shall be used unless plant conditions .g ij indicate severe fuel cladding failure. When the effective age falls between two listed values, an effective age that yields the higher value shall be used. 4.1.4 The Radiation Protection Technician (affected unit) shall be responsible for the initial release rate determinations and off-site dose calculations (EPIPs-14A, 14B). ~ p !? 4.1.5, The Radiological Protection Coordinator shall be responsible fj for dose assessment when the TSC is activated-(EPIPs-14A, h ._14B, 14C). g a 4.1.6 If the CRAC System or IBM PC Dose Projection programs are to s be_ used, preceed directly to the CRAC System Operations D Procedure or the PVNGS Emergency Off-site Dose Calculation Computer Program, App. E, of EPIP 14B. a, 4.1.7 All release rate determination / projection documents shall be processed in accordance with 78AC-0ZZ06, " Document and Record Turnover Control". These documents may be in the form of the Data Tables in the appendices or computer printouts from CRACS or the IBM PC program. 4.2 Prerequisites l None ';y ______a CONTROLLED DOCUMENT ~

CONTROLLED DOCUMENT I ~~ r - ~ ,1 ~ . -PVNGS t:mt:Muhr.K;Y PLAN, yCEME j IMPLEMENTING PR'O.CEDURE ] EPIP-14A REVISION RELEASE. RATE DETERMINATION 5 Page 6 of 25 - - r Il n _H 4.3 Instructions - -- ~ L NOTE i Use Section 4.3.1 for actual releases through ~ -: the Plant Vent, Fuel Building Vent Exhaust I -2 t 3- ~~ and/or Condenser Air Removal System. If the ~ release is through the main steam lines only, b proceed to Section 4.3.2. If it is desired to l _: n cpredict release rates ~ from containment, proceed i! ( - to Section 4.3.3. l ~~ I l 4.3.1 Determination of Activity Release Rate From an Effluent ~~" Release Point (Appendix A) ' 4.3~.1.1 ' Complete Section A of Appendix A, " Release Rate Determination From an Effluent Release Point" and obtain fh RMS data and monitor channel number from RP office or I =F Control Room to determine the monitor correction factor from Appendix B. i 4.3.1.2 From the Control Room, determine which. fans are operating and complete Section B. If fan operating information~is not available, assume that all fans are running. Total i plant release rate is the sum of the individual pathway release rates. f. 4.3i1.3-Complete Section C using the Total Noble Gas Release Rate from Section B and the values listed in Appendix C. 4.3.1.4 If a release is in progress via the main steam lines, continue with Section 4.3.2; if not, perform offsite dose. projections in accordance with EPIP-14B, " Initial Dose Assessment". [. + m, o, ~~"~ CONTROLLED DOCUMENT T g ) . '.i

l-r ^_. s.c: CONTROLLED DOCUMENT 1 PVNGS-EMERGEN. CY PLAN [RQCEDgE' 9 3.. o. IMPLEMENTING PROCEDURE ~ EP.IP-14A 2 - y: REVISION !{r RELEASE RATE DETERMINATION 'S Page 7 of 25'-- i 'l 4.3.2 Determination of Activity Release Rate From the Sain Steam ~~h Lines (Annendix D) l NOTE H 3'3 T Due to the low effective energy, Main Steam h ~~ Line Monitors will not detect a noble gas R -2 ~ release under maximum design operating k parameters (1*.' Failed Fuel; FSAR Chapter C 11). If Main Steam Line Monitor readings b; ~ ~ 2~' are above normal operating background levels !j then severe core degradation should be assumed and the higher source term values of ~ - ~ ' -~ total core inventory should be used for release rate and dose projection calculations. Notify the Shift Supervisor or Radiation Protection Coordinator (if ,gy ~ present) immediately. 'y ,l: .1 4.3.2.1 Complete Section A of Appendix D, " Release Rate Determination trom Main Steam System". 31 i l 4.3.2~.2 Enter the value of the higher reading monitor for the ii -affected steam generator in Section B of Appendix D, pg. 1. (Ex. If only one steam generator is exhibiting primary to secondary leakage, enter the higher value between the A & B channel for this steam generator. If both steam generators exhibit primary to secondary leaks i then the higher channel for both RU-139 and RU-140 shall 'J be entered and the releases added together.) i 1 4.3.2.3 Multiply the higher monitor reading from RU-139 A or B j and/cr RU-140 A or B by the Correction Factor shown below to cbtain Steam Line Concentration. Record in Section B j both Correction Factor used and Steam Line Concentration. N -l ] 'I 1 pp> m l II ii ~~"~' 1 CONTROLLED DOCUMENT

5 CONTROLLED DOCUMENT ~ ~ PVNGS EMERGENCY PLAN @%EWRE l' x _ IMPLEMENTING PROCEDURE EPIP-14A ~ REVISION RELEASE RATE DETERMINATION 5 -Page-8 -of--25 i .__.-.__1 r__.___..

Monitor Correction Factors (4.3.2.3)

~N ~{ Effective Monitor (hr-uCi) i _2 Age (HR) Correction Factor ( mr-cc) 0 .078 .5 .089 1.0 .11 -a 1.5 .13 2.0 .17 2.5 .24 '= 3.0 .28 3.5 .32 l 4 .44 5 1.3 O 6 1.8 (is!9 7 5.2 8 15.6 4.3.2.4 Record Noble Gas Concentration in microcuries per cubic ~ centimeter for each monitor used in Section B. NOTE Reactor Coolant System Temperature is ~ used as steam temperature for steam i ~ density compensation. j_ 4.3.2.5 Obtain from the Control Room the Reactor Coolant System j (RCS) temperature in degrees Fahrenheit and steam line flow rates in pounds par hour. Record flow rates in I 3' Section B. I i i~' s CONTRDLLED DOCUMENT ~ ~ ~A-c

, i.a_ _, L,.. r"c-CONTROLLED DOCUMENT k c ~ - -. - ~ u k' - -i PVH~Gs EMERGEN~CY PLAN [ROCEDURE 9 IMPLEMENTING PROCEDURE ~ EPIP-14A ~ REVISION

lI RELEASE RATE DETERMINATION

'S Pare 9 of 25 _ I 4.3.2.6 Using RCS temperature and pags 3 of Appendix D, select the appropriate Conversion Factor and record in Section B. 4.3.2.7. Complete Section B by multiplying Noble Gas Concentration

oy Conversion Factor and Steam Flow Fate.

7 4.3.2.8 Complete Section C using Total Noble Gas Release Rate from Section B and values listed in Appendix C (Total Core Inventory) for Total I/NG ratio and I-131/ Total I l l ratio for given effective age. 4.3.2.9 Add noble gas and I-131 release rates to those determined in Section 4.3.1, if applicable, and perform offsite dose projections in accordance with EPIP-14B. 4.3.3 Release Rate Projections From an Isolated Containmen't Using , 7' Design Basis Leak Rates and Area Monitors or External Containment Radiaiton Monitors (Appendix E) NOTE i This section is to be performed using informati~on from area monitors (RU-148 L or RU-149). Appendix E, pages 2 - 4 are F-default values based on hypothetical h source terms. Projections based on the l' use of these numbers should be verified as soon as possible utilizing field measurements and/or lab analysis. If the area monitors, RU-148 or RU-149, are inoperative proceed to section 4.3.4, use of external containment radiation monitors. 4.3.3.1 Complete Section A of Appendix E, page 1. Appendix E, page ~ 2, provides data for l'l; failed fuel and total core inventory. One percent Failed Fuel data should be used ~ unless there are indicaticns of core degradation, in which case Total Core Inventory data shall be used. 4.3.3.2 Record the highest monitor reading in Section B and using p predicted values from Appendix E, pages 2 - 4, calcula;e Projected Noble Gas Release Rate. -C.3.3.3 Complete Section C using Projected Noble Gas Release Rate and values listed in Appendix C. CONTROLLED DOCUMENT

c. CONTROLLED DOCUMENT p PVNGS EMERGENCY PLAN QOcsouas 3; i IMPLEMENTING PROCEDURE EPIP-14A _I_.. - _4 REVISION RELEASE RATE DETERMINATION 5 Page 10 of 25-- -"l N 4.3.4 Release Rate Projection From an Isolated Containment Using - ~ ~ - Design Basis Leak Rates and External Containment Radiation ,j Monitors (Apo'endices E and F) N ygg

q.

This section is to be performed using information from external containment Radiation Monitors. If a LOSS OF C00LAhT ACCIDENT has occurred and the In-Containment high range monitors are inoperative, this p section must be performed. Projections [.. -s - - 'should be compared to field measurements W i and/or lab analyses. Protective action j taken on the basis of projections may be i considered excessive once actual field data are available. Projections are a reasonable [ . _ M S. - -_ - ___2.__.__-___ u basis for decision when adequate field or lab data are not available. To calculate C release rate based on PASS Grab Sample Data, use the IBM-PC in conjunction with information obtained per procedure 74CH-9ZZ47, " Core Damage Assessment". 4.3.4.1 Complete Section A of Appendix E, page 1, except area monitor readings. .1 - 4.3.4.2 Obtain instrumentation readings from the external 'C containment monitors in the Auxiliary Building. Mark the highest reading on Appendix F, on appropriate curve, along with date and time. ,1 4.3.4.3 Using Appendix F, obtair. the ccrrel.ited readings for a RU-148 and RU-149, by drawing horizental lines through points marked in step 4.3.4.2. Ignore time scale. ._4.3.4.4 Transfer the highest RU-148 and kU-149 intercept values h (in r/hr) to Appendix E, page 1, Section A, and proceed to step 4.3.3.2.

(

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2 c ;; 7 CONTROLLED DOCUMENT 1 4 ...y ~ PVNGS EMERGENCY PLAN PROCEDURE f ..T N O. APPENDIX A._ ( IMPLEMENTING PROCEDURE o EPIP-14A -Page-1 of 2 REVISION RELEASE RATE DETERMINATION 5 Ng= 11 of 25 = - - __cRELEASE RATE DETERMINATION FROM AN EFFLUENT RELEASE POINT Section A: Release Data RX. SHUTDOWN: Date Time EFFECTIVE AGE f,. REL START: Date Time Section..B : Noble Gas Release Rate Determination e E eo e e Part 1 Plant Vent (Aux & Radwaste Bldg, Cntmt Refueling & Cntet Power Access Purge) y f _ y,- HAN-J01A (30,000 cfm) HAN-J01B (30,000 cfm) g HRN-J01A (25,500 cfm) Noble Gas HRN-J01B -(25,500 cfm) Cone Conversion Noble Gas CPN-J01A (16,500 cfm) Effective Age (RU-143 or Constant Release i. __.CPN-J01B (16,500 cfm) Correction RU-144) (cc-Ci/cfm Rate I - CPN-J02 ( 2,200 cfm) Factor (App - B) (pCi/cc) sec-pCi) (C1/s'ec) TOTAL FLOW RATE.(cfm) X X X 4.72E-04 = a Part 2. Condenser Air Removal System Vacuum. Pump A (60_.cfm): Noble Gas Vacuum Pump B (.60 cfm) Cone Conversion Noble Gas [- Vacuum Pump C (60 cfm) Effective Age (RU-141 or Constant Release Vacuum Pump D (60 cfm) Correction RU-142) (cc-C1/cfm e Rate Steam. Packing Exhaust Factor (App B) (pCi/cc) sec-pCi) (Ci/sec) TOTAL FLOW RATE (cfe) X X X 4.72E-04 = ^ Part 3. Fuel. Building Vent HFN-J01A (21,750 cfm) Noble Gas HFN-J01B (21,750 cfm) Conc Conversion Noble Gas HFA-J01 (6,000 cfm) Effective Age (RU-145 or Constant Release HFB-J01 (6,000 cfm) Correction RU-146) (cc-Ci/cfm Rate C; Factor (App B) (UCi/cc) sec-pCi) (C1/sec) TOTAL FLOW) ATE (cfm) X X X 4.72E-04 = CONTROLLED DOCUMENT ~~

..,._.a., - - - - - - - - - - - - - - - - - - - ~ ~ CONTROLLED DOCUMENT T /1 PVNGS EMERGENCY PLAN PROCEDURE . ( N O. 1 APPENDIX A-l k. IMPLEMENTING PROCEDURE EPIP-14A Page 2 of 2 ~~ ~ REVISION RELEASE RATE DETERMINATION 5 P_ age _12 of 25 d TOTAL EFFLUENT NOBLE GAS RELEASE RATE (Ci/sec) = ~ - - ' ~ ~ ~ Section C: I-131 Release Rate Determination Table Used: l l It Failed Fuel l l Total-Core Inventory ~~ - [. Noble Gas Total Iodine - ~ ~ - - '._. Release to ~ Rate Noble Gas Total Iodine (Section B) Ratio Volatile Release Rate d (Ci/sec) (Appendix C) Factor (Ci/sec) E .X'. ~ X .25 = ^ bi h, ~5f e e Total Iodine I-131 to i-Release Rate ~ Total Iodine I-131 J (Ci/sec) ~~~ ~ Ratio' Release Rate .E ~ (Appendix C) x (Ci/sec) ~. . i. ~ if m 5. 9x. ,e .t.bB.mo.. e= 6.~ ~, ')' e - E.! ~ M. ~59 CONTROLLED DOCUMENT s n .-..-,..--n,,.,--n...

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RELEASE START:

Date Time EFFECTIVE AGE:

Section B: Noble Gas Release Rate Determination ( NOTE: Enter N/A for non-affected steam generator. Monitor Monitor Monitor Steam Line Number Reading Correction Factor Concentration [" (mr/hr) (pC1/cc) p RU-139 X = (higher reading channel, if applicable) ({ ~ RU-140 X p. = (higher reading channel, if applicable) .!:L M Noble Gas Steam Density Steam Noble Gas Concentration Conversion Factor Flow Release ' Rate (pCI/cc) (cc-Ci-hr/lb-pCi-se) (lb/hr) (Ci/sec) lIV 7 RU-139 X X = h RU-140 X X = i RU-139 Noble Gas RU-140 Noble Gas Total Noble

p Release Rate Release Rate Gas Release Rate

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PVNGS EMERGENCY PLAN Q cewse .o.. gppgg9g sc IMPLEMENTING PROCEDURE EPIP-14A Page 3 of 3 - - f REVISION RELEASE RATE DETERMINATION 5 Page 17 of 25 -- - 2 Reactor Coolant Steam Density ~~ =. =. : System / Steam Converstion Factor Temperature (*F) (cc-Ci-hr/lb-p Ci-sec) ~ 200 2.65E-04 220 1.82E-04 240 1.28E-04

== 1 - -~ i 260 9.25E-05 280 6.81E-05 =- 300 5.08E-05 320 3.86E-05 340 2.97E-05 p 360 2.33E-05 i-380 1.84E-05 400 1.47E-05 420 1.18E-05 440 9.58E-06 { ~ 460 7.81E-06 -N 480 6.42E-06 500 5.31E-06 520 4.39E-06 540 3.67E-06 I 560 3.06E-06 I 580 2.53E-06 b 600 2.10E-06 620 1.74E-06 440 1.42E-06 660 1.14E-06 680 8.75E-07 NOTE The Steam Density Conversion Factor compensatss for s+.eam density changes, converts pCi to C1, and converts flow rate to release rate. b This table was developed frcm Table 1 of the ASME Sterun Tables using the specific volume (f t /lb) of 8 saturated vapor at a given temperature (*F). ma CONTROLLED DOCUMENT ~

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r 'T spip.14A .page 1 cf,-- REVISION RELEASE RATE DETERMINATION 5 _Page 18 of 25 ~ 0 RELEASE RATE PROJECTION FROM AN ISOLATED C0hTAINMEhT USING DESIGN ~ LEAK RATES AND AREA MONITORS OR EXTERNAL CONTAINMENT RADIATION MON Section A: Plant Data T REACTOR SHlTI'DOWN: Date Time RELEASE START: Date Time EFFECTIVE AGE: RU-148 reading or: r/hr RU-149 reading or: r/hr Appendix F Correlation Appendix.F Correlation Section B: Highest of RU-148 and RU-149 Readings (or Appendix. F correlations) , Highest of . p~ m . T: '3 Monitor D Readings (Section A) (r/hr) Section C: Noble Gas Release Rate Projection based on area monitors Projected c E Noble Gas Projected Projected Concentration Leak Rate Conversion Noble Gas (homograph) (Tech Specs) Constant Release Rate (VCi/ce) (cc/sec) (pCi to Ci) (Ci/sec) X 8.52E+02 X 1E-06 = 1 Section D: 1-131 Ralease Rate Projection based on area monitors Projected Iodine-131~ Projected Projected Concentration Leak Rate Conversion I-131 (Nomograph) (Tech Specs) Constant Release Rate bn (pCi/cc) (cc/sec) (pCi to Ci) (Ci/sec) F X 8.52E+02 X 1E-06 = s s Section E: Core Damage Estimate based on. nomograph N1 % of fuel rods are damaged. CONTROLLED DOCUMENT ~ ~ ^ * * .,--.n-.-,-- - - - - - ~

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SUMMARY

-~ --' This NOMOGRAPH relates the indicated dose rate at either high range in-containment area monitor to the airborne concentrations of either noble gases or radiciodines in the containment. As the Airborne concentration is related to the extent of core damage (given releases from the reactor coolant system), the nomograph also identifies core damage after consideration of decay. INSTRUCTIONS FOR USE: CAUTION CLASS 9 EVENTS, SUCH AS LOSS OF CONTAINMENT OR SPRAY FAILURE, ARE NOT ASSUMED IN NOM 0 GRAPH. NOM 0 GRAPH N1 MAY NOT TRIGGER ACTIONS IF CLASS 9 ' - T' EVENT EXISTS. 1. Enter time, date, and your name in legend space on blank N1 NOM 0 GRAPH. NOTE ~ A sample N1 NOMOGRAPH is provided at the end of these ll instructions. A blank N1 Nomograph is provided on the preceding page. 2. This NOMOGRAPH requirer data frem either high range in-containment area radiation monitor (13-J-SQA-RE-148 or 13-J-SQB-RE-149). If you have not already done so, obtain a current reading from either monitor. If monitor data are not available or if data are of questionable validity, refer to Appendix F and Section 4.3.4 for correlation methods to obtain a ___ reading. 'l 3. Enter monitor number and reading (R/hr) or highest of RU-148 and RU-149 - ~ ~ readings on the NOMOGRAPH legend. ~ ( 4. Locate the left hand vertical axis that is labeled " Current RAD /HR". -~ 7 e -h ~~ *' CONTROLLED DOCUMENT ~

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,v. PVNGS EMERGENCY PLAN PROCEDURE '(,. IMPLEMENTING PROCEDURE N O. AppghgIX g .EPIP-14A Page-4-of 7'~ ~~ !I RELEASE RATE DETERMINATION 5 Paste 21 of 25 ~~ bn II 5. Make a mark on the axis at a point corresponding to the value of ths ' 1 radiation monitor reading. ~ 's." Ibcate' tNe portion of the horizontal axis that is labeled " Time After ' O Shutdown" (Effective Age). 7. If the time since reactor trip is known, place a mark on the horizontal axis corresponding to that time. If the time is not known,.4 kip to Step 11 as' ~ --"@ ,.3 decay will not be. considered. _ :. n- ~~~ ._8. _. Draw a vertical;line through the mark on the decay time scale. ~~l. ...9. . Draw a horizontal line (parallel to the horizontal axis) from the mark on the ~ ,~~ " current RAD /HR" axis (the mark that was made in Step 5) to the right.until it intersects with the vertical decay time line (the line drawn in Step 8). 10. Now, draw a curved line to the right para 11cl to the curves already shown on - ^~--~the~ NOMOGRAPH until the line intersects the " Reference RAD /HR" axis. Make a mark at this intersection point. Skip Step 11 and proceed to Step 12. 11. Since'no decay can be assumed, place a mark on the " Reference RAD /HR axis at ~ the value corresponding to the area radiation monitor reading. (This is the same value as that plotted in Step 5). CAUTION ~ ~ f THE ESTIMATE OF CORE DAMAGE WILL BE LOWER THAN ACTUAL IF DECAY TIME IS IGNORED. ESTIMATED ERROR IS GREATEST AT LONG DECAY TIMES. ~1 12. Draw a horizontal line (parallel to the horizontal axis) to the right J from the. mark en the " Reference RAD /HR" axis that passes through both~ ,j g " Core D'amage" axes. ~ .[, 13. Identify the " Core Damage" axis that is the same as the area menitor whose readings are being used (either RU-146 or 149). 14. Make a mark at the intersection of that axis with the line drawn in Step Dj 12. 4.:g 1-CONTROLLED DOCUMENT ~ ~ ^ -

c(:T~ CONTROLLED DOCUMENT r L PVNGS EMERGENCY PLAN PROCEDURE r- .A T NO. APPENDIX E 4( IMP,LEMENTING PROCEDURE EPIP-14A Page-5--of-7 ~ ~ ) REVISION t... RELEASE RATE _ DETERMINATION 5 P_ age _22_of 25 a I l_S. Read the core damage estimate. The estimate represents the percentage of fuel rods in the core that have been damaged. l; l'

p CAUTION THE ESTIMATE 0F CORE DAMAGE WILL BE LOWER THAN ACTUAL

~ ~ IF PRIMARY SYSTEM INTEGRITY HAS BEEN BREACHED. ~ ~ 16. ~Locat'e the current area menitor dose rate scale on the horizontal axis. ~ ~ l ~~ ~' ~~~ f_" Make 'a mark along the horizontal axis at a point corresponding to the~ _ t.. ~ ~~ 1 ~... ~ current mon 1 tor dose rate. I^ ~ 18 Draw a vertical line.through the mark on the horizontal Current RAD /HR 'a'xis, intersecting all four curves shown in the region. ~~ 'J# 19. Make a mark at each of the intersections with the two curves that ~ correspoind to the monitor whose dose rate is plotted (either RU-148 or 149).~ ~ ~ 20. Locate the normalization factor portion of the horizontal axis. Make a mark on the horizontal axis at the value that corresponds to the t ___.- normalization factor obtained from the vertical axis in Step 15. 21. Draw a vertical line through the mark on the horizontal normalization factor axis. 1 22. Draw'~a horizontal line to the right from the mark on the Iodine 5 calibration curve (Step 19) until it intersects with the normalization m - ~ ' - - - - factor line (Step 21).

23. ~ifake a m' ark at this intersection.

~ 2 '+. Draw a 45' line down and to tne right from the mark (Step 23), parallel to the lines already shown on the NOMOGRAPH, until it intersects the right hand axis. 25. Make a mark at this point. This represents the airborne iodine-131 estimate. 3. ~ CONTROLLED DOCUMENT i ~

~._ I cd,: 3.' ~ CONTROLLED DOCUMENT 1 i PVNG$5 EME,RGENCY PLAN PROCEDURE ^ i... NO.. 2. .s APPENDIX E ~ IMPLEMENTING PROCEDURE EPIP-14A hge_6_of..$7-_._. _y REVISION RELEASE RATE DETERMINATION 5 Page 23 of 25- ' ~ ~, _26 . Return to the mark on the noble gas calibration curve (Step 19). Draw a- ~ ' horizonta' l' line to' the right until it intersects the normalization -factor line (Step 21). (This step is similar to Step 22). 2h--Make rinark at this intersection. b 1 i 28. Draw a 45* line down and to the right from the mark (Step 27), parallel to 'i the lines already shown on the NOM 0 GRAPH until it intersects the right hand ~ ~.. ~ ~ _f-axis. '- (l - - - - ~ - --29.-%ke rinark at this point.__This represents the airborne noble gas estimate. [ ~ ~

30. 'RetbiU to procedure Section 4.3.3.3.

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F-94 i

j a a t. e i~!' f. V v /[![! DEPT. EEAD DATE PRB/PRG/TRRG REVIEW < W6 DATE / APPROVED BY /[/(([/ DATE / // k EFFECTIVE DATE GA1 6 bi-DN-1668A/0196A j-- CONTROLLED DOCUMENT

CONTROLLED DOCUMENT e i PVNGS EMERGENCY PLAN Q cswas C;. IMPLEMENTING PROCEDURE sPIp.27 REVISION POST ACCIDENT SAMPLING AND ANALYSIS 3 Page 2 of 24 i 0 REVISION HISTORY [ l Rev. No. Date Revised Pages Comments S A,U,6, lo, si, [ h th/d N 81,13,44 l6 Jk #17fD C: i i i J _j '. i J ~I _ ~ N l c C f CONTROLLED DOCUMENT k

. zz. CONTROLLED DOCUMENT t DVNGSEMERGENC.Y PLAN QCEDURE l l ~ _; s IMPLEMENTING PROCEDURE EPIP-27 REVISION ~ { ~ POST ACCIDENT SAMPLING AND ANALYSIS 3 Page 3 of 24 . m ;.. TABLE OF CONTENTS m -h SECTION PAGE NUMBER 1.0 OB_JECTIVE _2. 0 RE_FE_RENCES_ - - - - + . _3 0_ _ LIMI.TATIONS_ AND_P_REQAUTIONS -- 2 4<0_. DETAILED _ PROCEDURE ___ - - ---8 4 1___ Personnel _ Indoctrination / Responsibilities ~8^ E 2 4.2 Prerequisites 9 f ._.__-4,.3____Chemis.try_ Sampling and Analysis Instructions for Handling PASS Grab Samples 11 L.. ..4 4._.. Primary Coolant and Containment Sumo Sampling Instructions 12 4_. 5 Containment _ Air Sampling and Analysis Instructions 12 0 __4.6_._ Core Dam _ age Assessment Instructions --k 4.7 Radiological Protection Sampling and Analysis Stack Effluent Sampling Instructions ---13 4.8 Onsite Transfer of Samples 16 4.9 Onsite Analysis of PASS and Effluent Samples - -17 ~ 4.10 Offsite Shipment of Post Accident _ _. _ _ _ _. _ Sample Instructions - --18 -4 APPENDICES PPendix A - RMS Filter Change / Grab Sample Data Sheet -f A l ~~ Appendix B - Accident Sample Analysis (Offsite) l ~~~ TrisismitH1'Torm 22 ~ " ppe~ndix CT ost Accident Sample Analysis Results 23 P ~~ ..- _ Appendix D - Site Route Map 24 L __ f v [ L' s CONTROLLED DOCUMENT l ~ ~ ~

CONTROLLED DOCUMENT _ .: B PVNGS EMERGENCY PLAN PROCEDURE NO. G. lMPL-EMENTING-PROCEDURE EPIP-27 ~_ [ REVISION pnRT ACCIDNT kAMPT.TNG AND ANALYSIS 3 Page 4T74 1: 1.0 OBJECTIVE To provide instructions for evaluating and handling PASS grab samples.. This procedure also provides for the analys'is_Mf ] ASS f, s pies tc, meet NUREG-0737. (' p

2.0 REFERENCES

t 2.1 Implementing References [ 2.1.1 74CH-9XC15, " Sampling Instructions" ~. . rq i '~ "'1 2.1.2 74CH-9XC24, "Onsite and Offsite Analysis of Post Accident Samples" ~ 2.1.3 74CH-9ZZ47, " Core Damage Assessment" i;@2f ' 2.1.4 NU,EG-0737, " Clarification of TMI Action Plan Requirements", ~ Oct. 1980 -:e 2.1.5 75RP-9ZZ64, "RMS Radioactive Sample Collection" .M[ 2.2 Developmental References ... q,l 2.2.1 EPIP-02, " Emergency Classification", Rev. 2 i 1-- ?.. 2.2.2 EPIP-16, "Inplant Surveys and Sampling", Rev. 2 4 . -. K 2.2.3 EPIP-17, "Onsite/Of fsite Surveys and Sampling", Rev. 2 kN ~ 2.2.4 EPIP-18, " Emergency Exposure Guidelines", Rev. 2 hj F,) 1 EPIP-29, " Area / Equipment Monitoring and Decontamination", 2.2.5 Rev. 2 U. ,y 2.2.6 ANSI N45.2.9, " Requirements for Collection, Storage and ~~* Maintenance of Quality Assurance Records for Nuclear Power s Plants, 1974" 2.2.7 NCP01, " PASS Training", Rev. 1 ~ E. 2.2.8 Operations and Maintenance Manual for Digital Radiation ]' Monitoring System, 10407-13M-997, August 2, 1982 0 2.2.9 PVNGS Emergency Plan, Rev. 5 e 4, f ~ CONTROLLED DOCUMENT ~~ . a

-4Wea e.. .*8.M' Se.e.-a.e g,eg,,.g,,,,,,,pg J,,_,, ,g4 Gi,,, ga, ,9,,, _,,g g_ CONTROLLED DOCUMENT a i ~ ~ ~ PVNG5 EMERGENCY PLAN, PROCEOURL ' = NO. IMPLEMENTING PROCEDURE rpip.27 .i-i d s REVISION POST ACCIDENT SAMPLING AND ANALYSIS 3 Page 5 of 24. :': - I i \\ 2.2.10 'IMI Lessons Learned Implementation Report, Section II, _ ~ ~ ~ -~ j F.1.1.A, May, 1982 ~ .a ~,.. _. l '.~~~ l_)).2. 2.11. ~ il'0 -CFR 20, " Standards for Protection Against Radiatilon", 1983: ..'.' ] a

- t ::

2.2.12 49 CFR 173 "Transporation", 1983 g 2.2.13 74CH-9ZZ06, " Boron (Potentiometric)", Rev. 2 .Z._ ::.' g i' 2.2.14 74CH-9ZZ35, "pH (Potentiometric)", Rev 3 -b : p 2.2.15 74CH-92Z65, " Gas Chromatograph Op'eration and Calibration", Rev. 1 2.2.16'a~ 4CH-9ZZ66, "The Determination of Primary to Secondary Leak - 'E

; - : _- ;. 1.2 s--

~ 7 +; Rate", Rev. O h ""'[ ~ 2.2.17 74CH-9ZZ72, ".'on Chromatograph Operation and Calibration", 8.+ ., R,ev.. O ~ A' 2.2.18 74CH-9ZZ90, " Operation and Calibration of the Post Accident Sampling System", Rev. O 2.2.19 740P-1SS01, " Nuclear Sampling Instructions", Rev. 0 M:i-2.2.20 75AC-9ZZO4, " Shipment, Receipt and Storage of Radioactive ~ ' : -h ' ' ' ' ' ~ ~ ~ Materials", Rev. 0 '- ~ 2~.2.21. 75AC-9ZZ15, " Radiological Access Control", Rev. 0 ' ^ --f ~

2.2.'22 75RP-9ZZ11 "Special Dosimetry", Rev. O

- -yI l ~ ' 2.2.23 75RP-9ZZ41, " Operation, Calibration and Performance Testing b l........ .... _...of Tennelec LB 5100", Rev. 0 1 2.2.24 75RP-92Z46, " Radioactive Contamination Survey Procedure", c;;.;- 'h.*V' 2 1 ~~

2. 2'.15' 75RP-92Z47, " Radiation Survey Procedure", Rev. 1 p

3' 2.2.26 75RP-92Z48, " Airborne Radioactivity Sampling and Measurement", Rev. 2 2.2.27. 75RP-9ZZ49, " Issue and Return of Respiratory Equipment", Rev. 1 I 2.2 28 75RP-9ZZ50, " Performance Testing of Laboratory Scaler Counting Systems", Rev. 1 f' F= - ~ ~ CONTROLLED DOCUMENT ~ _y

_. - -... -. = = = = = CONTROLLED DOCUMENT -e ~' PVNGS EMERGENCY PLAN PROCEDUPE ~ 2-1F NO. [ sj __ _IMPLE_MENTING _ PROCEDURE EPIP-27 ~~ t -b ~ 2' POST ACCIDENT SAMPLING ND ANALYSIS 3 Page 6 of 24-

. 2.2c29. 75RP-9ZZ57, " Packaging and Labeling of Radioactive

~ - :n. : =:::: , Materials", Rev. 0 1

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2-2 30:275RP-9ZZ59, " Preparation of Shipping Documents", R$v. 0 2.2.31 75RP-9ZZ61, " Radioactive Material Storage and Control", Rev.-1 ._.:a::__ r . 2.2.32 78AC-0ZZ06, " Document and Record Turnover Control", Rev. 1- ~ l em. 2.2.33 74CH-9XC33, " Post Accident Radioactive Sample Analysis and' l Handling" i ::::

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_ _. : t: n - 3.0 LIMITATIONS AND PRECAITTIONS NOTE

a-....

.. Plastic coveralls and rubber boots are T.) recommended when handling liquid samples. y 3.1' At -a minimum, the following protective clothing shall be worn 10 l when obtaining, handling, or transporting post eccident samples: t ( 3.1.1 Cloth coveralls I - 1:4 3.-1,2 c : Cloth glove liners ~ .g 3.1.3 Rubber gloves [ 3.1.4 Cloth hood g... [. r NOTE .b V" Alarming dosimeters are optional. .- :3.2 - -At.a -minimum, the following dosimetry is required: ~ 3.2.1 Whole body TLD a 3.2.2 High range dosimeter ..p .n.... 3.2.3 Extremity badges for personnel who handle the sample rt b .j . - - - 3. 3 -The-following guidelines shall be followed when h'andling PASS y samples: e y,, ... 1 - 3. 3.1 : : Use syringe shields, if available. 1. .f - CONTROLLED DOCUMENT

l c. CONTROLLED DOCUMENT t PVNGSfMERGENOY PLAN [ROCEWRE o.

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. u ~ T IMPLEMENTING PROCEDURE rpip.27 n REVISION c POST ACCIDENT SAMPLING AND ANALYSIS 3 Page 7 of-24 ........_3,3.2 Minimize handling of the glass portion of the syringe. 3.3.3 Perform all operations in a fully operational fume hood. \\ ~- ' ' ~ ~ ~ ~3.3.4' Ensure that analytical instruments are shielded.

e c.:3~d'$'='RPT$Uhniciansshallconductsurveysandtimekeepingto l

ensure exposures are kept below limits. .4 i ......,3.3.6. Use. remote handling devices such as tongs where possible. ' y 3.3.7 Samples shall be sealed and should be wrapped in plastic prior to removal from the fume hood. Samples should be placed in shields prior to removal from the hood if possible_. - - l i q 3.3.8 Rubber gloves shall be worn when handling samples. L 3.4 All personnel taking, handling, or analyzing PASS samples shall ~ i",. check dosimeters frequently. ,,, 3.5 The RP, Technician shall continuously monitor radiation' levels during all activities. I 3.6 Entry into areas with radiation levels in excess of those shown U on the Radiation Monitoring System (RMS) or levels set by the Radiological Protection Coordinator (RPC) shall require verbal authorization from the Radiological Protection Coordinator and the Emergency Coordinator. 3.7 Do not enter areas of high airborne radioactivity without proper respiratory equipment and proper dosimetry. Respiratory requirements will be determined at the time of entry. Highly contaminated smears should not be counted in an automated 3.8 system. 1 . _.~~ ..~3.9 Maintain personnel exposure ALARA by taking all practicable A precautions based on existing conditions. l 3.10 Radiation exposures exceeding PVNGS Administrative Radiation p Exposure Limits or 10 CFR 20 occupational limits shall be p I -authorized in accordance with EPIP-18, " Emergency Exposure - I ~ . Guidelines". ~2 ' ' 3.11' Only ona post accident sample may be obtained in a three hour P period. Additional samples should be obtained and analyzed i sequentially, allowing three hours per sample. u. CONTROLLED DOCUMENT 9 ~ - "

w CONTROLLED DOCUMENT i ~ s[ ~ PVNGS. EMERGENCY PLAN [ROCEDURE -2 L o. ny.; - IMPLEMENTING PROCEDURE _a ~" 4 Epip.27 4 REVISION 'I POST ACCIDENT SAMPLING AND ANALYSIS 3 Page 8 of 24 - - _ - i 3.12._ Personnel involved in post accident sampling activities shall be - h es'corted by a Radiation Protection Technician with an operable high; range dose rate meter. These meters shall have a range of

d

4

._r at least 1000 R/hr. l '._2 ...3.13 Transmit analysis results to the Radiological Protection / O.hemistryCoordinator(s). ._m ..: s ~ 3.14 Upon event termination, the Chemistry Coordinator shall transmit .d.a,ta.to DDC for storage. 9 2, ~ 3.15 To ensure chemical concentrations are not diluted below the

=: _

._ miiiim' um sensitivity of the specific analysis required, multiple . n .. [ ~ .. ' =[ samples,,mayberequiredwithvaryingdilutions. 4 3 1,6, Additional dilution may be required on the 0.1 to 4 ml diluted .:.a samples obtained from PASS to facilitate performance of the i .+r d equired, analysis.

.F

. g.3 L . W.") 3.17 PASS Samples shall normally be analyzed in th6 I?it I (affected . unit). lab, if the affected unit lab is unavailir.la, the Unit II (unaffected unit) lab should be used as a Back-up-Facility. - L. .s. ~ 4.0 'DETAI' LED p'OCEDURE R '[ ..j.' '4.1.?]erso'nnelIndoctrination/ Responsibilities 4.1.1 The Radiological Protection Coordinator in conjunction with .the Chemistry Coordinator shall: _l' ....4'.T.1.1 Establish the, counting priority. n.f - 2 I 4.1.1.R J eport results to the Emergency Coordinator as required. 1 4.1.1.3 Determine the analysis location of collected samples. y

f..

' 4.1~.1. 4' Brief technicians prior to their taking a sampic. 4.1.2.. Chemistry Technicians shall perform sample analysis and .~ ~ ~. ~~~~ record results. t Sampling and analysis shall ba conducted in accordance with 4.1.3 station procedures as noted in this procedure. i 4.1.[4 ~ ; Die Unit Radiation Protection Supervisor shall provide l technical support for the inplant survey teams in ~ coordination with the RPC. ~~ ~ ~" J CONTROLLED DOCUMENT T

CONTROLLED DOCUMENT 1 s n ( PVNGS EMERGENCY PLAN PROCEDURE - - - l N. s - _ IMPLEMENTING PROCEDURE EPIP-27 '~ ~ y REVISION POST ACCIDEhT SAMPLING AND ANALYSIS 3 Paie 9 of_24'~ U ~-

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. : - 4.~1. 5- 'Al-1 Po~st Accident Sampling System (PASS) samples shall be* ... '. l.~ ' i

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+tollected and analyzed by the chemistry staff or by trained

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- a. c.: personnel at an authorized offsite facility. -~ ~-"' 4.1.6 One Radiation Protection Technician and one Chemistry .._...g =.

2:..r Technician are required for PASS sampling; one to monitor

~ T.' _~ ;.. ' and one to perform the sampling and analysis. ..._.- : 4 l. 7 : Th~e' fo'11owing supplies are needed to perform the collection ~: .. 'N of plant effinent particulate and iodine filters: ~ [ . _ c. : ;; ..::: : 4el.7.1 Transfer shield. -~- ..} ~ .;:_.n ... :.e 3 .r". ; e 4.1.7.2 Four foot tongs. [ - 4.,1.7,3

Four foot latch handle for operating lever on

~ r:2 particulate / iodine sample assembly. g [ 4.1.7.4 Replacement Silver Zeolite cartridge and filter disc in a L'

particulate / iodine (PI) filter assembly.

4.1.7,5 Radioactive material tag. p 4.1.8 The following supplies are needed to perform the collection of a PASS grab sample: ~ ~ ~ ~ 4l ^ ': - $5 4.1.8.1 Sample syringe a 4.1.8.2 Syringe transfer shield i ~ Evacuated 8 al glass vial for gas samp"les 4.1.8.3 4.1.8.4 Radioactive material tag 4.1.9 Dispose of all post accident samples at the discretion of the -r RPC and in accordance with existing RP procedures . - 4. 2 ??rerequisites c :' 4.2~.1: -An ALERT or more severe emergency has been classified per the ~ provisions of EPIP-02, " Emergency Classification". f. 4.2^.2r: Radiation Protection Laboratory counting equipment shall be ~ T ( calibrated and operational per existing RP procedures. .h'. A CONTROLLED DOCUMENT 1

CONTROLLED DOCUMENT ~ b ~ ~ j IFCP NGS EMERGENCY PLAN PROCEDURE NO. C ~ k ^ IMPLEMENTING PROCEDURE EPIP-27 I REVISION POST ACCIDENT. SAMPLING AND ANALYSIS 3 Page 10 of 24 - .f ._ 4.2.3... Chemistry counting and analytical equipment shall be ~ j . calibrated and operational per existing chemistry procedures, and with analytical sensitivities defined in Appendix C. - ' ': 1 Final dilutions of all samples shall also be recor(ed on z.-.._ .::u :r-Appendix C. - ${

.. = :

4.2.4 All required equipment and reagents shall be available and y prepared prior to beginning analysis of post accident samples. L h = u

...4,2.5 Smear samples and airborne particulate and iodine samples shall be obtained in accordance with EPIP-16, "Inplant Surveys and Sampling" and EPIP-17, "Onsite/Offsite Surveys and Sampling".

4.2.6 Access the controlled area by using the emergency access REP er 9999 or as otherwise directed by the RP coordinator. 4.2.7 The monitor and channel number of the filter (s) to be changed 4-.. i@ .s ah ll.be determined by the Radiological Protection Coordinator by using the RMS. 4.2.8 Results of analyses shall be recorded on Appendix C. -) Prior-to the beginning of analysis of any post-accident U -- 4.2.9 samples, an area radiation study shall be conducted and the Radiation Protection Coordinator and the Chemistry Coordinator notified of the results immediately. Q ~,. 4.2.10 Prior to the beginning of analysis of any post-accident b i sample an iodine cartridge sample shall be obtained and l

n quantitated for radio-iodine general area concentrations.

I The Radiation Protection Coordinator and the Chemistry Coordinator shall be notified immediately of the results. =: .,z:+- u - w:. u g t 't:..

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~ CONTROLLED DOCUMENT i ! i - PVNGS EMERGENCY PLAN PROCEDURE -T NO. IMPLEMENTING PROCEDURE EPIP-27 REVISION POST ACCIDENT SAMPLING AND ANALYSIS 3 Page 11 of 24 !~ ~ F!' NOTE --f ..-.=

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Radiation Monitor RU-26 (10R full scale) .a

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e: -- and RU-158D (10'R full scale) are located I ..k -.n in the sampling area. If RU-26 is deflected full scale, notify the _. Radiological Protection Coordinator .i _n_. 2: {onsite) or Radiation Protection Monitor (onshift) for further instructions and evacuate personnel to an area with low ~'.. 2:_e5

. 2:

radiation levels as' determined by Radiation --2 ~ I' ' ' Protection personnel. ' y 4.3 Chemistry Sampling and Analysis - Instructions for Handling Grab ~ ' Samples. - 2 '. L NOTE _-. ;.c ~- (. Sampling room radiation levels shall be } i determined by Radiation Protection Technician prior to entry by Chemistry / '= -- personnel. t.. 4.3 W 'After isolation of a sample in the PASS remote grab sample / init',1 verify the completion of the sampling system flush. ~ r -4.3.2 The Chemistry Technician obtaining the PASS remote grab sample shall be escorted by a Radiation Protection Technician with the appropriate dose rate instruments. ( ~ _:.. 2 NOTE I' ~ n ~ Collection and analysis of PASS

remote grab samples should be accomplished without exceeding an accumulated dose of 5 REM to the whole body and 75 REM to the e.xtremities of any individual.

4.3.3 The Radiation Protection Technician shall closely monitor the radiation levels during access to the sample collection and sample handling. f E CONTROLLED DOCUMENT ~~-

~ i CONTROLLED DOCUMENT Z ~ PROCEDURE 33 3,- 3,r 'E PVNGS EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-27 EE' ^ {f REVISION i POST ACCIDENT SAMPLING AND ANALYSIS 3 Page 12 of 24'.- -fw NOTE

9 Pass Samples shall normally be analyzed in i/

, m the Unit I (affected unit) lab, however, if i' I'

-2" the affected unit lab is unavailable, the Unit II (unaffected unit) lab should be used

~ ,[2 [_ - - - - - -.[ i, as a Back-up Facility. ((~ [2 :l ] ~ ] ' 4.3.4 If radiation levels (2 500 mrem /hr) preclude the analysis -- " ~- of the PASS sample in the affected unit radiochemistry (. -..,'..~ notify the Chemistry and Radiological Protection Coordinators ~~ laboratory within the 5 REM whole body dose restriction, ( and request further instructions. . 4. 3._5_ After _ collecting a gaseous PASS grab sample, quickly transfer

:: - ;.lj the syringe contents into an evacuated 8 ml gas sample vial.

~ -- -~ '- Place the syringe and the sample vial into the shielded carrying case. NOTE vf. ? Processed samples and radioactive waste are to be stored in a shielded ares within the y radiochemistry laboratory or other p designated area. ~ ~ " - - ' 4'. 3 '. 6 Move the shielded sample to a low dose rate area, resurvey .the shielded container and decontaminate container to less g 2 than.1000dpm/200cm removable contamination if necessary. 4 4.3.7 On site movement of samples shall be done in accordance with section 4.8. 4.4 Primary Coolant and Containment Sump Sampling Instructions

4.4.1 PASS sampling of primary coolant and/or the containment sump shall be completed in accordance with procedure 74CH-9ZZ90,

" Operation and Calibration of the Post Accident Sampling System". .U s ' a. .s,: 4.5- . Containment Air Sampling and Analysis Instructions [ 3-4.5.1 PASS sampling and analysis of containment air shall be t; completed in accordance with procedure 74CH-9ZZ90, " Operation and Calibration of the Post Accident Sampling System". E.adN f CONTROLLED DOCUMENT T ~

CONTROLLED DOCUMENT ~ 1 PVNGS EMERGENCY PLAN 70

3 3-- ;

ceouse 1 E IMPLEMENTING PROCEDURE EPIP-27 f ~ ~~ REVISION f t POST ACCIDENT SAMPLING AND ANALYSIS 3 Page 13 of 24 l .~ -- =- T CAUTION V - -8: l DOSE RATES IN THIS AREA MAY EXCEED 100 [ e - e: i R/HR. IF RADIATION MONITOR RU-156-C INDICATES GREATER THAN 10 R/HR, NOTIFY THE RADIOLOGICAL PROTECTION COORDINATOR AND WAIT FOR FURTHER INSTRUCTIONS IN A LOW DOSE RATE

AREA.

^ ( s 4.5.2 As an alternative, a containment air sample may be obtained from the Radiation Montior (RU-1) located at the 100' level ~ [' of the Auxiliary Building. 4.5.3 Access routes shall be determined by the Radiological Protection Coordinator at the time.of the accident. 4.5.4 Continuously monitor dose rates during access, egress and performance of collection. NOTE Containment iodine and particulate samples 32 for post accident analysis must be limited 2 - to 9 R/hr contact readings or equivalent to 3.0 mei activity content. 4.5.5,. Grab s.ampling of containment air shall be in accordance with y - ~ ~ ~ ~ ~ ~ procedures in 75RP-9ZZ64. i .4.5.6 Grab sample analysis shall be in accordance with procedure ~74CH-9XC33 " Post Accident Radioactive Sample Handling and .. Analysis" and 74CH-92Z65 " Operation and Cali,bration of the a Gas Chromatograph". ~ ~4. 6~ Core' Damage Assessment Instructions a 4.6.1 Evaluation of damage to the core through analysis of the - y samples shall be in accordance with pocedures in 74CH-92Z47, ." Core Damage Assessment". .:p ~ '.f0 4.7 Radiological Protection Sampling and Analysis - Stack Effluent ~~# Sampling Instructions CONTROLLED DOCUMENT

i CONTROLLED DOCUMENT ~ s.- PVNGS EMERGENCY PLAN QCEWRE [ 2' j h IMPLEMENTING PROCEDURE EpIo-27 _ _ _.. l._ U _~ l REVISION POST ACCIDENT SAMPLING AND ANALYSIS 3 Page 14 o'f 24.'~ ^ -i f i 4.7.1 Access routes to Plant Vent (RU-144), Fuel Building Exhaust t (RU-146) and Condenser Vacuum Exhaust (RU-142) Monitors shall be discussed by the Radiological Protection Coordinator and l and the technicians designated to pull the samples lat the ,-g time of the accident. .7 _..s-: r ,f NOTE _..r The following instructions apply to --- r Radiation Monitors RU-142, RU-144 and RU-146 only. .4.7.2

Replacement of Particulate and Iodine Filters i

- r

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w. NOTE e Continuously monitor dose rates during --.3 , collection. Take dose rate readings on the j -9 filters and the transfer pig. Limit sample ,,_ rate on the iodine cartridge and particulate filter sample assembly to 9R/Hr on contact. NOTE ~ ..~ Verify that the sample point (s) selected by ~ },. ;, * ~ ,T. the Radiological Protection Coordinator is/are logged out on the RMS terminal prior to leaving the office. 4.7 3 5 'Close the inlet and outlet sample flow valves of the ~ Particulate / Iodine channel (s) on the high range ,..,. monitor selected by the RPC. 3 ^ ',' [4.7.~2!2~IRemovelidfromtransfershield. ~ 4.7.2.3 Open the shielded door by lifting up latch. ~ 4.7.2.4 Insert four foot latch handle over the sample assembly ., lever. .. ) ~~ 4.7.2.5' Turn lever counterclockwise to release spring tension. 2 4.7.2.6 . Insert four foot tongs and remove the filter assembly. , 33) 4.7.2.7 Place filter assembly in the transfer shield. i 4.7.2.8 Quickly place lid back on top of the transfer shield. w - CONTROLLED DOCUMENT _ _ _c

~ 90 & T ~.. . i CONTROLLED DOCUMENT ~ PVNGS EMERGENCY PLAN [ROCEDURE 77 y 7~, o N '_.__ ___.-IMPLEMENTING PROCEDURE EpIP-27 . 2.' I ~ 2 - ~ ~ REVISION POST ACCIDENT SAMPLING AND ANALYSIS 3 Page 15 of 24:.~ _ 4.7.2_.9..,, Place the new filter assembly in the sample assembly. . - I ~ [ ~ ~~ ./.[h10.jurnleveronthesampleassemblyclockwiseusingthe ._h four foot latch handle to allow spring tension to seal the sample assembly. - L

4. 7.~ 2.11 Close the shielded door and latch.

Insure the door is securely latched. [ 4.7.2.12 Open the inlet and outlet sample flow valves for the Particulate / Iodine channel (s) where filters were changed. .3.___ . _b The 4 foot handling tongs will be needed f for sample analysis. The tongs shall be i ~~. ~ ^ ~ ' kept with the transfer shield. [ a;n i D " '4.7.2.13 Deliver the samples to the location determined by the Radiological Protection Coordinator, and in accordance F with 4.8. 4.7.2.14 Go to the appropriate microprocessor corresponding to the monitor for which the filters were changed and using either KLIC, KPIC, or SMIC acquire the PI channel total flow, start time, and stop time.. 4.7.2.15 Using the RMS key, place the microprocessor in LOCAL or ENABLE Mode. ~ 4.7[.2.16 After notifying the Shift Supervisor, step the filter for the channel filter (s) that were changed. 4.7.2.17 After the filter has been stepped, return the Local F-Indication and Control Unit (KLIC), Portable Indication I and Control Unit (KPIC), or Skid Mounted Indication and I Control Unit (SMIC) to the REMOTE or DISABLE mode; press l' .. the TEST-LT CK button to verify the lights and LED i . display are functional and the system is in the REMOTE i-mode. ~ ~ ' 4~. 7. 2.18 Notify the Data Acquisition and Control Unit (DCU) i 47].}, operator that the monitor is returned to REMOTE mode and [ is ready to be brought on line. l 4.7.2.19 InformtheRadiationProtectionMonitorofthefi$ter change time and he should update the RMS data base. ^

1 +~

' CONTROLLED DOCUMENT

c M,. CONTROLLED DOCUMENT ~ PVNGS EMERGENCY PLAN QCEDURE ,9 -M IMPLEMENTING PROCEDURE Epip-27 ? REVISION POST ACCIDENT SAMPLING AND ANALYSIS 3 _Page 16 of 24 - 4.-7. 2.20 Tag the transfer shield with a Radioactive Material Tag stating the monitor or Particulate / Iodine channel number -.u .:in the Item Description section. Include sampling ' -information. 4.7.2.21 Prepare Appendix A, "RMS Filter Change / Grab Sample Data [

. Sheet" for review by the Radiological Protection Coordinator or his designee.

- 4.7.3-Noble Gas Sampling Instructions -u 4.7.3.1 Sampling at the effluent points for noble gases shall be in accordance with procedures in 75RP-9ZZ64. 4.8 Onsite Transfer of Samples NOTE .. ::ln f" During any sample movement, the RP Technician .e shall ensure that exposure to personnel not involved in the transfer is minimized. h NOTE = . Notify Security upon initiation of sample collection or as soon as it is determined that a ^- sample must be transferred. Notification shall a include preferred route, gate numbers, and expected time of transfer. 4.8.1 The Radiation Protection Technician will need ropes, signs, tape,-and step off pads for establishing a radiological controlled area. r -- 4.8,2.. All transfers will use the most direct route accessible as ._shown on Appendix D. The Radiological Protection Coordinator

j...should be consulted for current conditions.

4.8.3 . Site ve.hicles may be used for transfers between units and to the~offsite shipping point. 4.8.4 The minimum Radiological Controlled Area (RCA) which shall be ..3 established in a non-affected unit shall be at, each end of Grd the corridor leading to the hot lab. .s ? 4.8.5 The RCA may be reduced later after evaluation by the [ Radiation Protection Department. ~ l-t CONTROLLED DOCUMENT l y 3.s. -_-.n.

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4- -...A.- .u. e. ..,-_,--.M..-... 'm 4--- = 1 :. CONTROLLED DOCUMENT ~ ~ ^ - = PVrTGB EIMEMGIENCY PLAN QCEDWE 7t IMPLEMENTING PROCEDURE spIp.27 ' i 2 b g POST ACCIDENT SAMPLING AND ANALYSIS 3 Page 17 of 24 I p I- { . 4.9 Onsite Analysis of PASS and Effluent Samples .4.9..lf,j Analysis of PAS's Liquid Grab Samples j ~~ v 4.9.1.1 Analyze the sample for gamma isotopic content accordance with 74CH-9XC33, " Post Accident Radioactive _ }.: Sample Analysis and Handling". ~ ~~ 4.9.1.2 Analyze the sample for boron concentration in accordance t with 74CH-92Z06, " Boron (Potentiometric)". NOTE ..:~ ~ Chloride analysis shall be performed 24 hrs post accident. L 4.9.1.3 Analyze for chlorides in accordance with 74CH-9ZZ72, ,q " Ion Chromatograph Operation and Calibration". if-Sg If the total gas or gas stripping section of PASS is inoperable, analysis of total gas or gaseous gamma isotopic concentration is not possible. 4.9.1.4 Analyze for pH in accordance with 74CH-9ZZ35, "pH ~~ ~ (potentiometric)." 4.9.2 Analysis of PASS Grab Samples ~ 4. 9.'2. I ' Analyze PASS gas and grab sampics for gamma Jsotopic [ ~ content in accordance with 74CH-9XC33, " Post Accident j-Rad'ioactive Sample Analysis and Handling". t g. J I n e i CONTROLLED DOCUMENT

n,.

CONTROLLED DOCUMENT PVNGS EMERGENCY PLAN PROCEDURE 3:q7 - = N O. 1. I ~ U IMPLEMENTING PROCEDURE EPIP-27 REVISION 1 POST ACCIDENT SAMPLING AND ANALYSIS 3 Page 18 of 24 -l NOTE i .,o l If additional analyses are desired a r 2 : 3 normal sample must be obtained. l Permission to collect normal reactor

.. c 2

coolant, containment recire, containment sumps, auxiliary building sumps or .;....2 containment atmosphere samples is a post .. ;.. :e accident environment must be obtained with.the concurrence of the Chemistry Coordinator and.the Radiological Protection Coordinator. .-::.: c 4.9.3 Liquid PASS grab samples shall be analyzed for the following: 4.9.3..l. Chloride in accordance with 74CH-9ZZ72; I 4.9.3.2 Boron in accordance with 74CH-9ZZ06; [ .j l ~ ~~ 4.9.3.3 Gamma isotopic in accordance with 74CH-9XC33. [. 4.9.3.4 pH in accordance with 74CH-9ZZ35. 4.9.4 Gaseous PASS and effluent grab samples shall be analyzed for the following: 4.9.4.1 Hydrogen and oxygen in accordance with 74CH-9ZZ65. 4.9.4.2 Gamma isotopic in accordance with 74CH-9XC33. - 4. 9.5 Analysis shall be performed per the instructions of the Chemistry Coordinator using the appropriate procedure. U 4.10 Offsite Shipment of Post Accident Sample Instructions 4.10.1 Transfer post accident samples to the area designated by the Radiological Protection Coordinator. k 4.10.2 Request a " sole use" closed transport vehicle through the Administrative and Logistics Coordinator. l L' CONTROLLED DOCUMENT ~ ~~

J. .L 2.._.. ._.i__-_-_-.__.. ^ J ? ~ CONTROLLED DOCUMENT 1 ~ ~IiNGU5M5RGEPICY PLAN pesouns , g 3g . 'j IMPLEMENTING PROCEDURE Epip.27 i hl _ __ __c _ _ _ _ _ _ _ _. . ~ ~ ~ ~ ~ REVISION l POST ACCIDENT SAMPLING AND ANALYSIS 3 Page 19 of 24.. ' ' NOTE .a If background radiation levels preclude the performance of surveys, contain any [ potential contamination and perform surveys as soon as practicable in a low background radiation area. . :.. c. NOTE f~ The lab at Arizona. State University has a L limit of 5 R/hr at 1 foot for the unshielded a ^ sample container. Ensure the sample is below this prior to shipping. _ l 4.10.3 Survey the shielded syringe container and/or transport [ pig. Portable shielding may be used to reduce shield contact dose rates. If portable shielding is not g y (; W consistent with exposure reduction benefits or would W preclude safe sample movement, notify the Radiological 1 Protection Coordinator for further instructions. a NOTE The contamination limits stated below are less than 10 percent of the 49 CFR 173, 0 " Transportation Limits for Significant Contamination". i, 4.10.4 Decontaminate the shielded container to less than 1000 2 2 ~ dpm/100 cm beta-gamma and less than 20 dpm/100cm 1 -- alpha if possible. If this is not possible, decontaminate 2

)

to within 10% of the DOT limits (2200 dpm/100 cm j 2 beta gamma and 220 dpm/100 cm alpha). e y j ' L' s O

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~ ~ " ~ ' ~ CONTROLLED DOCUMENT

-= y CONTROLLED DOCUMENT ~ J P 3\\ i 2 ~ - PVNGS EMERGENCY PLAN @ cpWRE ' i y IMPLEMENTING PROCEDURE EPip-27 f REVISION !l POST ACCIDENT SAMPLING AND ANALYSIS 3 Page 20 of 24 ~ a __~ , NOTE Prior to transporting a PASS sample or other '= post accident grab samples to an offsite j -r-3 analytical facility, make the following .. a:: n notifications : - } (1) Affected unit Shift Supervisor i (2) Radiological Protection Coordinator (3) Chemistry Coordinator i .a 1. 2 J - (4) Security Director (for onsite transport route control) .....: 4. (5) Administrative and Logistics Coordinator (for notification of the offsite analytical facility) .:~;::- .4.10.5. Shielded syringe sample carrying cases and/or transport g, . pig reading less than 200 mR/hr on contact may be . transported without additional shielding. 4.10.6 If the contact dose rate on the shielded container is greater than 200 mR/hr, place the shielded container on a l hand truck or cart and add additional shielding to [l ~ ~ ~ attenuate the dose rate to less than 200 mR/hr. The unattenuated dose rate shall be clearly indicated on the outside of the shielding. 4.10.7 Determine packaging and leveling requirements in l accordance with procedure 75RP-9ZZ57, " Packaging and Labeling of Radioactive Materials". u 4.10.8 Prepare all shipping documents in accordance with ~ l . procedures 75RP-9ZZ59, " Preparation of Shipping Documents" v l '~ &nd'75AC-9ZZO4, " Shipment, Receipt, and Storage of I Radioactive Materials". ~ 4.10.9 Transport the sample to the " sole use" closed transport vehicle is accordance with Section 4.8. Load and s(cure the sampic for shipment. 4.10.10 Ensure that the~ shipping documents contain a completed i " Accident Sample Analysis (Offsite) Transmittal Form" l (Appendix B). "N/A" all unnecessary data spaces. c l l 4.10.11 Retain record and data forms in accordance with i 78AC-0ZZ06, " Document and Record Turnover Control". 1 ?:'SO CONTROLLED DOCUMENT ~ ' - " " "

.._......_.m.. CONTROLLED DOCUMENT ~ ~ -~ ~ e e PROCEDURE h ~ PVNGS EMERGENCY PLAN N O. APPENDIL A - i ~- IMPLEMENTING PROCEDURE EPIP-27 _P.aze_l if f 5__ REVISION ~ POST ACCIDENT SAMPLING AND ANALYSIS 3 Page 21 of 24 - RMS FILTER CHANGE / GRAB SAMPLE DATA SHEET i Date - -- Ic. -. Particulate Filter - Honitor RU # Channel # Sample Flow Rate P Date/ Time On Off Sample Volume tl Monitor Feading Filter Gross Activity 3 S - II.- Iodine Cartridge Monitor RU # Channel # Sample Flow Rate Date/ Time On Off Sampfe Volume e Monitor Reading Cartridge Gross Activity s. ~; 1 III. Noble Gas Monitor RU # Sample Time Sample Volume If B Monitor Reading Sample Gross Activity . + IV. Remarks:

(

c h i Performed by: Reviewed ty: Date: Date: ) i F A CONTROLLED DOCUMENT ~~ ..n._.._._.

.__..._.._.-...~.~.2. ~ . r ---- J. ~ l c,.--.. CONTROLLED DOCUMENT s - ~ PVNGS EMERGENCY PLAN PROCEDURE NO .. q APPENDIX 2 - k IMPLEMENTING PROCEDURE ~ cpip.27 Page 1 of 1- .h .= - REVISION POST ACCIDENT SAMPLING AND ANALYSIS 3 Page 22 of 24 - ^.2 Ii! ACCIDENT SAMPLE ANLYSIS (OFFSITE) TRANSMITTAL FORM 4 I L' Sample No.

== Description:== M + .je Type: Filter Cartridge Liquid / Gas (vol. cc) g ~ _p Radiation leve1E@~l cm mR/hr @ a ft, mR/hr lT Isotopic (GeLi) Alpha Beta Transuranics ,_t' m Analysis Required: .....y Strontium Special Instructions: ~ .q . g: t -N v.- b t p Sent by: Time /Date: wg Analyzed by: Time /Date: . A ~ Results transmitted by: Time /Date: Attach all output /results to this sheet and return to PVNGS with sample wastes. Huturned by: Timo/Datn: y Verified by: Time /Date: Rev'iewe'd bW ' - ~~ Time /Date: ~ s t... ct CONTROLLED DOCUMENT S ~ ~ <. 4 .m. O. we.*--wee ao em. w *_ W

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-. i ~ CONTROLLED DOCUMENT I ,. e ~~ PVKGYEMERCliERCY PLAN QCENRE 7; ; 3q c. - = / APPENDIX C ( IMPLEMENTING PROCEDURE EPIP-27 Page 1 of 1: E- -2 REVISION ~ ~ ~ ~ -~ POST ACCIDENT SAMPLING AND ANALYSIS 3 Page 23 of 24 POST ACCIDENT SAMPLE ANALYSIS RESULTS A. LIQUID ~ i 1 Dilution Minimum -- Observed -Analysis-------Procedure Ratio Sensitivity Results~ ~~"~~~~ T ~-- -Gamma-Isotopic- -74CH-92Z48 N/A (Attach j - Printout) Boron .74CH-92206 10 ppm w/ or Autotitrator L 74CH-9ZZO4 f Chloride 74CH-9ZZ10 0.05 ppm . y. f Corrected Results: (Observed Results X Dilution Ratio) Gamma Isotopic (Attach Printout) Boron 1,~ Chloride = _. _.. _. _ B. GASEOUS p Dilution Minimum Observed Analysis----_ Procedure Ratio Sensitivity Results T ~ ~ ~ ~ ~ ~ ~ --- Gamma Isotopio- --74CH-92Z48 N/A Hydrogen 74CH-9ZZ65 d L -- - C.- RECORDS - --- -Record all results in accordance with procedure 74CH-9ZZ99, " Records and "~~~ I Reports". s 9 e CONTROLLED DOCUMENT ~ ~ ~~ .... _.... _ _ _... _.. _ ~... _. _. _ _... _.. _ _.

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CONTROLLED DOCUMENT ~ I ...o -3O e ~ ~ ~~ PVNGS EMERGENCY PLAN PROCEDURE ^ii g N O. APPENDIkD - - - H IMPLEMENTING PROCEDURE Epip.27 Page i nr Y fT REVISION V1 POST ACCIDEffr SAMPLING AND ANALYSIS 3 Page 24 of 24 f sj _ :.=- -. =: :- l1 Site Route Map I ~ ~ [ f i' f,7

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CONTROLLED DOCUMENT --3 r ~~ PVNGS EMERGENCY PLAN PROCEDURE p,~ No. [ ( IMPLEMENTING PR.O._CEDURE ,.~.. EpIp.38 ~ [ EMERGENCY EQUIPMENT AND f REVISION 3 SUPPLY INVENTORY 4 Pagn 1 nf 9 /. E fI ~ ASSIGNED COPY [ & 94 PVNGS ~ .C, b 1-l .i \\- [I I 1 ////hh DATE/[/)~fhp .1, DEPT. HEAD ///ff(((( // "/[M PRB/PRG/ EW DATE APPROVED BY -. / //,///' DATE /2 37 /L. EITECTIVE D /- 86 DN-1670A/0196A e r . CONTROLLED DOCUMENT T O

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^ CONTROLLED DOCUMENT - ~ ~ ~ ~ 4 = =L PVNGS EMERGENCY PLAN Q cswas -n u h___. --GMPLEMENTING PROCEDUR. E .E. PIP-38 _ IEMERGENCY EQUIPMENI' AND ~ ,fSUPPLY INVENTORY '4 Paon 3 M 34 i I h TABIS OF CONTENTS SECTION ~ PAGE NUMBER 1.O OBJECIIVE ._~.5 ~~ 2--. _._ g

2.0 REFERENCES

5 - -~ _L.0 LIMITATIONS AND.. PRECAUTIONS ..... _.'.T5 - ~ ~ 4.0 DETAILED PROCEDURE' 6 4.1 Personnel Indoctrination / Responsibilities ~6---- -

4.2-~ Prerequirites 6

4.3 Instructions - -- ~ APPENDICES - - ~ s 6 -Appendix-A -Emergency-Storage at Unit One CR/STSC 9 i -Appendix-B - Emergency-Storage at Unit One OSC 11 - Appendix-C - -Emergency Storage at Service Building 14 -.- _L. Appendix-D --Emergency-Storage at TSC 17 I .7 Appendix E----Emergency-Storage at EOF 19 .. r Appendix-F - Emergency Vehicle Supply Inventory 21 i i y - Appendix G- - Maryvale-Samaritan Hospital Emergency Kit 24 j .. _ 7 - Appendix-H --Good Samaritan Hospital Emergency Kit 25 l ._ s Appendix I - PVNGS Ambulance Emergency Kit 26 Appendix J -- Offsite Ambulance Emergency Kit 27 l - Appendix K - Offsite Survey Team Emergency Kit A 28 PY240004 dese2) i . CONTROLLED DOCUMENT ~

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~ CONTROLLED DOCUMENT F - - - -r y Fv'NG5 EiviERGENCY PLAN PROCEDURE ';G 5 37 5 % N O. s j IMPLEMENTING PROCEDURE 1 spip.38 l REVISION iJ EMERGENCY EQUIPMEhT AND

J SUPPLY INVEh70RY 4

Page 4 of 34 !/ l Y-APPENDICES (Cont'd) ar.. .s PAGE NUMBER r. (. Appendix L - Offsite Survey Team Emergency Kit B 30 t-h- t, m,,,; Appendix M - Emergency Onsite Evacuation Decontamination Kit 32 I, \\A Appendix N - Offsite Decontamination Kit 33 p ,1 L........ . ~.... _.

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. ~. I CONTROLLED DOCUMENT ~ [ ~~ PVHDS EM5RGENCY PLAN 2: 'i PROCEDURE nO. (l~ IMPLEMENTING PROCEDURE -. y EPIP-38 REVISION ~ EMERGENCY EQUIPMENT AND SUPPLY INVENTORY 4 Paga 9 nf % ~ r S 1.0 OBJECTIVE 1.1 To provide a means of assuring the operational readiness and I availability of equipment required for implementation of the PVNGS Emergency Plan. er.v ur 1 - u w ire.n n : -- _t ec:

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_.;3 t ~~"'{' .;.f-p u g.2. 0 REFERENCES- 'r ? >-.., a c. _ = c ~ ~ ~ ' " t~ 2.1 Implementing References ~ ~ ' 2.1.1 78AC-0ZZO6, " Document and Record Turnover Control" 2.1.2 75PR-0ZZ01, " Radiation Protection Program" 2.1.3 75PR-0ZZO2, " Respiratory Protection Program" 2.1.4 60AC-0ZZO2, " Control of Nonconforming Items" ( 2.2 Developmen'tal References 2.2.1 NUREG 0654, Rev. 1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in i Support of Nuclear Power Plants" 2.2.2 NUREG 0696, Feb. 1981, " Functional Criteria for Emergency Response Facilities" 2.2.3 PVNGS Emergency Plan, Rev. 5. 3.0 LIMITATIONS AND PRECAUTIONS 3.1 First-Aid equipment and supplies shall be maintained under the direction of the Safety Director. m 3.2 Equipment a'id supplies utilized on a daily basis but which may be used during an emergency shall be maintained through existing surveillance procedures. 3.3 For the purposes of this procedure, "immediately" shall be defined as one (1) working day. L ~. _., q . CONTROLLED DOCUMENT ~ e

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.:e PVNDS EMERGENCY PLAN @'CEWRE G M3 h-IMPLEMENTING PROCEDURE "E5 ~ EpIp.3S N REVISION EMERGENCY EQUIPMENT AND ~" ~[* SUPPLY INVENTORY 4 Page 6 of 34 .I 4.0 DETAILED PROCEDURE -S 4.1 Personnel Indoctrination / Responsibilities .i ~~ ~ " ' ' 4.' l.1 'In order. to insure the availability of equipment which may be i required during the course of an emergency at PVNGS, the Site I Emergency Planning Supervisor or his designes shall be responsible for conducting a quarterly inventory of emergency # = -'= equipment and supplies. In addition, an inventory shall be ..,d. conducted within five (5) working days after any drill using '~ emergency equipment and/or supplies. Only those kits utilized in the drill shall be subject to the post-drill . inventory. ~ ~ 4.2 Prerequisites .,~ ~ NONE l y 4.3 Instructions /..; 4.3.1 Dedicated emergency equipment and s6pplies located in the emergency lockers shall be inventoried quarterly and after each drill. Emergency lockers / kits are maintained at the ~ following locations: (1) Control Room /STSC of each unit ~ (2) Operations Support Center (OSC) of each unit (3) Service Building (alternate OSC) (4) TSC (5) EOF (Command Center) (6) Emergency Vehicle-(7) Maryvale Samaritan Hospital (8) Security Building (9) Annex Building, Security Desk .3 (10)PVNGS Ambulance (11) Good Samaritan Hospital ~4.3.2 Addit 1onal equipment and supplies are also maintained near ~ the Access Control Point and OSC. I t 4.3.3 Inventory is accomplished by the Onsite Emergency Planning ( ~ Group utilizing Appendices A through N. Each appendix contains the designated equipment for a specified emergency storage location. .Y I

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f4:-: PVNGS ENiERGENCY PLAN @. esome -+ G-IMPLEMENTING PROCEDURE EPIP-38 2 .. s "9 w EMERGENCY EQUIPMENT AND ~4 Page 7 of 34 I-SUPPLY INVENTORY r-4.3.3.1 All blanks shall be filled on each appendix when A. 2._ inventoried. 4.3.3.t If the shelf life of the. battery as indicated by the 1 ._, -~~- ~- manufacturer has expired, replace the battery. t ....~. 4}3 3.h If no shelf life is indicated, obtain a battery tester t ^' 'rfrom the Radiation Protection Instrument Calibration L . [l,' i _ ' ~ l [_. Group and test the battery. If the battery output falls

- in the red band of the tester, discard it and replace

., ~ _ _, _ -,_ - '- ~fwith a new battery. c. . c e r :- n :J. - H ... lies (mir umekn. c, . :n.r ' 4.3 4 Instruments and communications equipment stored in the ' ' " ' emergency lockers shall be tested quarterly and after each

J use.

Calibration of radiation survey instruments shall be conducted by the Radiation Protection Section and at intervals established by the Radiation Protection Section. g 4.3.5 Respirators and respiratory protection equipment shall be .>7 maintained by the Radiation Protection Support Group. c' Repair, replacement, change-out shall be performed at intervals established per 75PR-0ZZ01, " Radiation Protection f< ~ ' Program", and/or 75PR-0ZZO2, " Respiratory Protection Program." [ ~" p, 4.3.6. . Onsite Emergency Planning Group shall coordinate with Radiation Protection to ensure that in each emergency kit each type of personal dosimetry (i.e., 0-200 mR pocket dosimeters, 0-1R pocket dosimeters, Alarming dosimeters) 1 should have the same calibration due date. l 4.3.7, Instruments found to be deficient or inoperable shall be promptly repaired or replaced. Instruments shall be removed from service prior to their calibration due date. If a ? replacement is not immediately available to return to the y, kit, four (4) working days shall be allowed for p repair /recalibration of the subject instrument. 'l l L u. n It! ~~~ C. ONTROLLED DOCUMENT 1 ~ _ ~.,. _

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.l" CONTROLLED DOCUMENT t PVNGS EMERGENCY PLAN PROCEDURE ':'3 - 7' GR ...s NO. 'c' IMPLEMENTING PROCEDURE EPIP-38 ' ~L~~ w. EMERGENCY EQUIPMENT AND SUPPLY INVENTORY 4 Page 8 of 34 L F i\\:l 4.3.8 Materials and supplies found to be deficient or missing shall I '~ ~ ~~~" ~ ~ be replaced as soon as possible (generally within five (5) ~~ - working days). Materials / supplies that must be purchased l ~~~ ~ (i.e., Purchase Request, R.O.S., etc.) shall be noted in the + ~~ comments section of the appropriate appendix. The specific }. ~ P.R. or.R.O.S. should be tracked via normal purchasing e 1. ~ group / warehouse methods. ..' ' ^ ~ '..... '.'.~~.*. s. .a = ~ ~ ~ 4.3:.9." Rec ~ o~rds of the inventory and checks of emergency equipment ~~ ~ hall be transmitted to DDC by the Supervisor, Site Emergency s r Planning as per 78AC-0ZZ06, " Document and Record Turnover , Control", with a copy forwarded to the Manager, Emergency ~. Planning and Preparedness. .'4.3.10Calibrationrecordsofradiationsurveyinstrumentsshallbe maintained by the Radiation Protection Section. 0 r t l. 6 e t I i '.I) l k'; ~~~ CONTROLLED DOCUMENT

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~ CONTROLLED DOCUMENT I p PVNG5 EMERGENCY PLAN PROCEDURE % C. 3 i,a.9,y N O. APPENDIXB.,if~; IMPLEMENTING PROCEDURE ...w EpIp.se Page 1 of 3'. TH +- REVISION EMERGENCY EQUIPMENT AND SUPPLIES INVENTORY 4 Page 11 of 34 EMERGF.NCY STORAGE AT UNIT ONE OSC BATTERY SERIAL CALIBRATION RECHARGE / NUMBER DATE/ INITIALS _DUE DATE REPLACEMENT i* .1 =6 _.Handahald portable radios / U / .: r F. _J. ..v - : _x. c o = 2 w.t e : r. / / .22:t:: .;Ti*- I / Y. / ?3 1 6-Pak radio charger / 6 Radio holsters / ~ . - Ej ~n' 6 Spare batteries / -.-i r -. 1 Frisker w/ probe / 1 Portable Ion Cha-% r Survey Meter / .- 2 Portable air samplers / -l 0. / p_ _.1 '100' extension cord / !-] 4 A/S heads / 1 Particulate A/S filters

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REVISION EERGENCY EQUIPMENT AND SUPPLIES INVEhTORY

'4 Page 16 of 34 EMERGENCY STORAGE AT SERVICE BUILDING (CONT'D) BATIERY ~~ SERIAL CALIBRATION RECHARGE / ~:~

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NUMBER DATE/ INITIALS DUE DATE REPLACEMENT I 20 Ixtremity TLD rings / ~; - 1 Tweezers,. pair / ~ ~ ~ ' :.* - 4 Grease pencils / - 6 Hand-held radios / ' ~ ~ ' ' ' ~ " " I . ~ ~ - / -3 / 6 Radio holsters / 2 - 6 Spare radio batteries / -~ . -~~ 1 Radio charger; 6 pak--- / Q _ ---- ..('b- ---~ ~ Kit Seal No. S n Comments: .. f a.. V ~ _ _.. _ - - Performed by: - N j Signature Date 1 ~ _ ~......, ( p -*9 ..h n-re e m

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~10 Potassium Iodide, KI, BTL, .- 14--Tabs /BTL- - --- / h -- 1 ~ Full' Set, Site Maps-- / 1 Tweezers, pr. / ~ ~ k ~ -- --I Surgeon's gloves, box / p -4 Grease pencils / Q ly (: p.; j g ... _.... -.--Kit Seal No. . __.... [ lComments: y.) t (. !~. b. l, - - ---Performed by: Signature Date CONTROLLED. DOCUMENT O

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1 D CONTROLLED DOCUMENT - 2 f ~ pyggg EMERGENCY PLAN PROCEDURE a " '4 G 5 U/ ( __g; = /- NO. APPENDIX Fr-. --. y 9 v-IMPLEMENTING PROCEDURE r P 1,C Epip.38 pag. 1_o REVISION k EMERGENCY EQUIPMEhT AND ._ SUPPLIES INVENTORY 4 Page 21 of 34 EMERGENCY VEHICLE SUPPLY INVENTORY ) (R.E.R.V) BATIERY i. SERIAL CALIBRATION RECHARGE / } ~f_]~-- NUMBER DATE/ INITIALS DUE DATE REPLACEMENT I 1 Frisker w/ probe / ~

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10 Signs with inserts

/ 2 Shampoo / 5 Soap / - -- - -- h 1 Hair clippers / [F 2 Shaving cream / 1 Disposable razors (pkg) / - Wash cloths / _. 4 ___ Towels __.. _ _ _ _. _ _ / -_-_..-._--a f 1 Q-Tips (pkg) /

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- - - --Smears-(box with folders) / Fl. 300' Barrier rope / U 2 Clipboards / - --- h -Papers yellow,-lined f; (pkg) / g 5 Pens / pencils / c.s O: 'l Log book / 20 RAM labels / [ 2 Tape, Duct / i rvaaca asia:n b CONTROLLED DOCUMENT

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